ML20214L184
| ML20214L184 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/20/1986 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 JEW-86-805, TAC-61635, NUDOCS 8612020596 | |
| Download: ML20214L184 (218) | |
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SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-805 November 20, 1986 Director of Nuclear Reactor Regulation Attention: Frank J. Miraglia, Jr.
Division of PWR Licensing-B U S Nuclear Regulatory Commission Washington D C 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit il DISTRICT RESPONSE TO NRC REQUEST FOR INFORMATION
References:
- 1. NRC to SMUD September 15, 1986
- 2. (Proposed) Outline Rancho Seco Nuclear Generating Station Safety Evaluation - 10/17/86
Dear Mr. Miraglia:
In order to gather additional technical information necessary for the preparation of an SER supporting the restart of Rancho Seco, a NRC technical team, under the direction of Mr. Leo Beltracchi, visited the site from September 29 through October 2, 1986 to meet with District personnel. During that meeting, the District discussed in detail, with the NRC team, the items in Table I of the " Audit Agenda" contained in reference 1.
Attachment 1 documents the District's response to selected items as requested by the audit team and presented by the District during the meeting.
^
Additional supporting technical information as requested by the team is also included in the attachment.
Since the attached information is in response to Reference 1, and will be used by the NRC staff for Reference 2, the District is providing the following cross reference as suggested by the NRC Rancho Seco Project Manager Mr. Syd Miner:
Item Number in Attachment Item Number in Item Number in Reference 2 to this letter Reference 1 (SER Outline) 1.0 9.9 3.1.5; 4.6 2.0 9.5 3.1.5; 4.6 3.0 9.6 4.6 0 4.0 9.8 4.5; 4.6 5.0 N/A 3.1.5; 4.5; 4.6 6.0 N/A 3.1.5; 4.5; 4.6 8612O20596 861120 PDR ADOCK 05000312 P PDR DISTRICT HEADQUARTERS O 6201 S Street, Sacramento CA 95817-1899
I:
Frank J. Miraglia, Jr. November 20,1986 l JEW 86-805 I
I In addition to the above audit items, the District intends to provide the NRC staff the following information as discussed with the audit team:
Item Number Anticipated Item Description in Reference 2 Submittal Date Revised RG 1.97 Implementation Submitted on Schedule 4.5 11/14/86 SPDS Upgrade Sumrary Report 4.6 12/31/86 SPDS Isolation Test Results 4.6 12/31/86 SPDS Updated Reliability Analysis 4.6 12/31/86 Summary of Modifications Made to the Control Room for Restart 3.6.5 12/31/86 Control Room Status Report or Addendum 3.6.5 4/1/87 Proposed Tech Spec Addition for RG 1.97/SPDS (Not required for N/A 4/1/87 Restart)
Comparison of SPDS to RG 1.152 4.6 4/15/87 In addition to the above, the District will meet with the NRC staff to walk-through the hardware and software for two selected RG 1.97 signals to the SPDS. The District understands that it will suggest one of the signals while the NRC staff will select the other. The District anticipates completing this evaluation during January 1987 as mutually agreed upon by members of the District and NRC staffs.
Finally, as discussed with Mr. Syd Miner, the District will propose amendments to the Rancho Seco Technical Specifications covering the SPDS and RG 1.97.
This proposed Tech Spec is not required for restart. However the District intends to administratively adhere to the provisions of the proposed Tech Soec while remaining in compliance with existing applicable Technical Specifications.
4
_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
r Frank'J. Miraglia, Jr. ' November 20, 1986 JEW 86-805 If you have any further questions, please feel free to contact Ray Ashley, our Manager of Nuclear Licensing.
Sincerely,
. Y }
o n E. Ward Deputy General Manager, Nuclear Attachments cc: Sydney Miner, NRC, Bethesda Tony D'Angelo, NRC, Rancho Seco i
v -- - ,v p <,-,e,
Frank J. Miraglia, Jr. November 20,1986
. JEW 86-805 If you have any fureher questions, please feel f ree to contact Ray Ashley, out-Manager of Nuclear Licensing.
Sincerely, Or~ r =l *
- YAK rh John E. Ward Deputy General Aanager, Nuclear Attachments cc: Sydney Miner, NRC, Bethesda Tony D'Angelo, NRC, Rancho Seco bc: W. K. Latham w/o attachment J. E. Ward w/o attachment K. Perkins/G. Coward w/ attachment R. L. Ashley w/o attachment D. Poole/B. Croley/T. Tucker w/ attachment D. Gillispie/G. Cranston w/ attachment T. Lutkehaus/J. Shetler w/o attachment S. Knight -w/o attachment R. Colombo w/o attachment P. G. Delezenski w/ attachment- '
G. C. Andognini (MS 200) w/o attachment Fourth Floor Files w/ attachment l Licensing Files (MS 37) w/ attachment l R.S. Adm. Files (MS 203) w/ attachment Plaza 50 Files w/ attachment' J. Williams w/ attachment D. Prosch w/ attachment D. Scott w/ attachment JD/dpn
24.6 S fety ParcsetCr Dicpicy'Syctem (SPDS). .
- a. . Upgrade to Safety Grade
~1.0 Describe the steps needed to restart an upgraded SPDS.upon a
. total. loss of power to the system.
1.0 Response The SPDS Operating Manual (N17.06 - IM01) section 5.2.1 states' that *the Display System requires no operator action'to start up-other than turning on the power'. This feature was tested
' during the completion of the SMUD' SPDS SOFTWARE . VALIDATION PLAN with satisfactory results. Therefore, upon restoration of power, the SPDS is self-starting and requires no operator action.
2.0 Describe,the. features of the design process and of the display system that serve as guards against common mode f ailures/ errors.
2.0 Response ,
The SPDS, after. restart modifications have been completed, will consist of 2 color monitors, 2 video generators, 2 SPDS computers, 2 control panels jone for each display) and 2 input interface modules. .,The system will be provided_ input data from 2 redundant channels of the Anatec data acquisition system. -The Anatec data acquisition system consists of a Central. Control Unit (CCU) cabinet and ten remote multiplexer cabinets located throughout the plant. .The data acquisition system will be completely channelized with class 1 sensors being. input to channel A and channel B class 1 multiplexers respectively.
The: Central Control Unit cabinet consists of 2. identical central control units, 2 identical receiver / transmitters, 2 identical CCU diagnostic panels and 2 identical de power supplies for redundant operation. It also contains one central control unit select unit (CSU). This CCU select unit, presently controls the
. polling operation of the two CCU's. Under normal operation it alternates between the two CCU's.~ That is, each redundant CCU interrogates and receives data from all ten multiplexers,
-alternately.
4 If a failure of one of the CCU's occurs, the good CCU is
< selected by the CSU continuously until the bad CCU is restored to normal operation. If the CCU select unit fails, the primary
'" CCU (CCU 91) is automatically selected. Since, the CCU select unit is a single unit-(not redundant), it could be considered a
- single point of failure. But, since it automatically selects I CCU $1 to continuously operate, one of the redundant channels
=
continues to provide all of the SPDS data collected from all ten multiplexers. The channel of SPDS provided by CCU $2 would not receive any information, but the display that is still operating on SPDS channel l can display all of the SPDS plant data.
i
! NRCCRM f
Since the CCU select unit could be a common mode failure point, evaluation has been conducted to determine if it can be removed and the CCU's operated properly without it. This evaluation which has included acquiring technical advice from a manufacturer's engineer has resulted in a decision to retain the select unit in the system for proper operation and provide isolation test results of the built-in isolation. The manufacturer's engineer verified that isolation between CCU's was built into the select unit. The failure mode of the SPDS would still be as described above even if the select unit was removed and a failure of one CCU was considered.
To ensure against common mode failures each independent channel of the SPDS and the data acquisition system will be provided with independent clasz 1 battery / diesel backed A-C power.
All RG 1.97 category 1 variables will originate'from class 1 sensors and be processed through class 1 multiplexers powered as described above. All SPDS inputs are duplicated on IDADS.
The potential for software programming being a common mode failure point within the SPDS has been reduced by programmer verification and validation (VEV), pre-installation testing, post-installation testing prior to turnover to operations, and normal operations usage of the SPDS.
The SPDS program was generated under B&W Special Products and Inspection Services Working Instruction Number 4, Software Development. Under this instruction, a functional requirements document was produced that listed all features included in the system, interface requirements. Detailed programming flow charts were prepared from the functional requirements document.
A test plan outline for software testing was prepared from the flowcharts. A review of the functional requirements document and flowcharts was performed to assure that the design (as reflected in the flowcharts and drawings) met the requirements of the-functional requirements document. This review was conducted by the design engineer, his supervisor, and an independent engineer. After comments were incorporated, the three reviewers documented the review by signing the flowcharts and hardware drawings.
An independent review was also conducted by a qualified individual from outside the original designer (s) management structure. This independent V&V was conducted to a V&V plan.
All comments and responses were documented. All correspondence generated by the V&V were placed in the QA file for the system.
Software coding followed the flow chart development. The test plan outline was filled in during coding to assure all logic was tested. Detailed hardware drawings and parts listed were reviewed to assure hardware / software compatibility. Detailed test procedures were prepared from the filled in test plan outline to test the final hardware and software. All features in the functional requirements document were exercised. A review of the final software and test plan was conducted by a qualified individual from outside the original designer (s)
NRCCRM -2 -
management structure. This review checked the final dIsign against the design requirements and assured that all requirements were verified in the final system test. , All comments and resolutions were in writing, all correspondence placed in the QA file, and reference to final documentation made via comment in the software.
System testing (Pre-installation) was performed in accordance with approved procedures by personnel other than the designer (s). Items not meeting acceptance criteria were corrected. Errors necessitated a paper prepared by the designer that documented the nature /cause of the error, proposed fix, additional retesting required, and expected effect on system performance.
An operations ranual for the SPDS were prepared and tested for usability by personnel other than the designer. Working Instruction Number 4 also includes instructions for Documentation, Design Change and Design Package preparation.
After delivery, the SPDS was installed in the plant under Modification Description 660. After installation was complete, Special Test Procedure #636-SPDS Acceptance Test (post-installation testing) was performed by the District Startup Organization prior to system turnover to operations.
The SPDS was operating in the Control Room for one full fuel cycle for operator familiarization, equipment burn-in, procedure revision, and operator training prior to declaring the SPDS to be operational.
The described design process and display systen features are felt by the District to adequately guard against common mode failures / errors.
3.0 Describe the maintenance and configuration control program for the display system. Provide the procedures that will be used to modify the software.
3.0 Response Maintenance is defined as the tests, inspections, calibrations, checks and cleaning performed on equipment on a routine basis to assure operability within predescribed specifications. The SPDS uses inputs from the Anatec Central Control Units (CCU's) and Uniplex Field Multiplexer's (UFM's). These components are calibrated in accordance with I.414, Anatec Calibration (Attachment 1). The inputs to the Anatec equipment are received from the plant process instruments and control devices. The plant instruments and control devices are calibrated in accordance with I-Oll, General Calibration Procedure (Attachment 2). A number of procedures provide the instructions for loop calibration. An example of these procedures is provided in ,
I-038, Rosemount Model 1153B, ll53D Pressure Transmitter NRCCRM -3 -
n
+-
-Calibration / Rochester Instrument Panel Analog Isolator Calibration (Attachment 3).
Enclosure:
7.5 of.this procedure
'shows a typical instrument loop that sends a signal to the SPDS. Enclosure 7.ll of this procedure shows the calibration
~
form used to document calibration _of RCS wide' range pressures.'
The SPDS response to this calibration -is required to-be -
documented on the form. The expected response is noted in parenthesis. "The SPDS Operating Manual (N17.06-IM01) section 6
' states that periodic inspection / cleaning of the reusable metallic filters is required on a monthly basis. This activity will be performed / documented in.accordance with I-405, SPDS' Maintenance. This procedure is under. development.
NEP 4109, Rancho Seco Configuration Control Procedure (Attachment 4), provides the program for assuring the integrity of the physical plant hardware. -This includes the SPDS hardware. The District controls the SPDS software configuration using B&W software and QA procedures and District administrative procedures. Changes to software are made by B&W (at the request of the District) using Special Products and Inspection Services Working Instruction Number 4, Software l
Development.(Attachment 5). These changes are sent to the i
-District in the form of SPDS Operating Manual drawing changes l ' and as Read Only Memory (ROM) replacements. . ROM replacement constitutes a database change to the SPDS and is controlled.by District procedure AP.52, Software Change. Procedure (Attachment 6).
'4.0 Provide the documents and data that illustrate the upgraded SPDS complies with industry and regulatory criteria and standards for safety-related systems (ie, IEEE sto 323-1974, Standard for Qualification of class lE Equipment for Nuclear Power Generating Stations, IEEE sto 344-1975, Recommended Practices for seismic Qualification of Class lE Equipment for Nuclear Power, etc.) per RG 1.97.
4.0 Response Documentation is presently available for seismic qualification
'of the SPDS cabinet H4SPDS and all Anatec Multiplexer system-cabinets. If necessary, after modifications to affected cabinets, an analysis will be performed and documentation made available. All new cable routings will be routed in seismically qualified conduits and cable trays. Documentation showing compliance with IEEE std 323 is not currently available, but compliance with the separation, isolation, redundancy, and environmental requirements will be demonstrated prior to restart. Environmental qualification will only be required-for sensor inputs since all portions of the system except field sensors are in a mild environment.
NRCCRM. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
In compliance with IE Bulletin 79-OlB, Order for Modification, dated October 24, 1982, and 10CFR50 Appendix A, Criterion 4, and NURBG 0696, Safety Parameter Display System (SPDS);
modifications were performed to upgrade the necessary components important to safety. These components were designed using the following general design criteria:
Replacement parts shall conform to DOR Guidelines, " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment". Where possible, new equipment shall conform to NUREG 0508, Staff Position on Environmental Qualification of Safety Related Electrical Equipment, Category s 1, or IEEE 323-1974, Qualifying Class lE Equipment for Nuclear-Power Generating Stations. Additionally, new equipment will be installed as Seismic Class 1 in accordance with IEEE 344-1975 and Bechtel Design Guide C2.7.
Equipment located inside the reactor building shall be designed to withstand the environmen,t resulting from the Design Basis Accident (DBA) as defined in the FSAR. This includes maximum temperature of 286*F, pressure of 52 psig, 100% humidity, flooding to 8 feet above basement floor, chemical spray consisting of Boric Acid buffered with Sodium Hydroxide, and gamma radiation of 4 X 106 rads at 30 days. In addition, the equipment shall withstand a beta radiation dose of 9 X 107 rads at 200 days and will be designed for a " qualified' life" of 40 years at a service temperature of 80'F.
Equipment required to function during or after a Main Steam Line Break (MSLB) will be purchased or upgraded to survive the conditions postulated following a MSLB. The conditions postulated are: maximum temperature, 373'F; maximum pressure, 54 psig; humidity, 100%.
Equipment located outside the reactor building shall be designed for use in that particular area. Generally, the equipment will be designed for a 40 year service life and a DBA radiation dose. The 480 volt transfer switches will be designed to meet separation requirements of IEEE 384-1977 and IEEE 308-1978.
Inputs for (open/close) containment isolation valve position shall be provided for display to the SPDS. Conduit, tray, and cable for the valve position input shall be Class 1, including seismic classification.
Engineering Change Notices (ECNs) are on file documenting these changes to the plant configuration and the District's commitment to comply with IEEE std 323-1974 and IEEE std 344-1975 for modifications.
NRCCRM -5 -
w
$ 5.0 Provide a power ~ supply schematic for the SPDS and associated hardware.
5.0 Response The SPDS will be a QA class 1 and seismically class 1 system. Circuits having direct interface with'SPDS cabinets H4SPDS, H2SP'(CRT Cabinet) and B4CDAL '(CCU Cabinet) will be ' class 1 routed in Class 1 raceways..
The power supply will be from class 1 UPS system.
Sketchea 1 through 3 show the power supply arrangement for the SPDS and associated cabinets.
-6.0 Provide documentation'of the intent to meet ~the 10CFR50 Appendix R requirements for SPDS/RG 1.97 cables.
6.0 Response All RG 1.97 category i variables, except Neutron flux, are channel oriented. Circuits of those variables that are required for Appendix "R" events are routed through the fire areas assigned for that particular channel. Channel "A" variables are routed through channel-
"A' fire area and channel "B" variables are routed through channel "B" fire areas. In fire areas where circuite of channel A and channel ~B coexist, circuits of the channe! not belonging to that fire area have been wrapped except inside the Control Room.
In the event of a fire in the Control Room, the SPDS cabinet itself will~
be assumed lost. In that case, alternate shutdown capability is available.in the 4160V west switchgear room through the emergency shutdown panel, H2SD. Therefore, there is no need to wrap the redundant SPDS circuits inside the Control Room.
~
Since Control Room indication from SPDS isJnot duplicated outside the Control Room, a fire in the Control Room will have no impact on safe shutdown instrumentation available at the emergencyLahutdown panel, H2SD. At the present time however, SPDS is not credited for safe shutdown during an Appendix "R" event since alternate independent indication'is available in the Control Room as well as at'the emergency shutdown panel, H2SD.
However, the following Appendix "R" criteria will be applied:
- 1. Channel "A" instrumentation signal, power and control circuits will be routed independent and separated from Channel "B" circuits in all fire areas outside the control room.
- 2. There will be no crisscross of power supplies i.e., Channel "A" instrumentation has Channel "A" power only and Channel "B" instrumentation has Channel "B" power only. See Table 1.
- 3. Appendix "R" separation between the two Channels will be maintained and the design changes will be reviewed and if cables have to be routed in the same fire zone, those cables not belonging in that fire zone will be wrapped for fire protection.
The present SPDS cable routing design package has been routed through the Appendix "R" review group and has been approved without any need for fire wrap. The appendix "R" review group has documentation on file and can be provided if required.
NRCCRM -6 -
y Table 1 shows the channel orientation of category 1 variables.
TABLE 1 CHANNEL ORIENTATION OF RG 1.97 CATEGORY l VARIABLES CHANNEL CLASSIFICATION MULTIPLEXER REMARKS EQUIPMENT DESCRIPTION TE 21030 RCS Hot Leg Temp. B S4CDARS TE 21033 RCS Hot Leg Temp. A H4CDAR3 PT 21050 RCS Pressure B H4CDAR5 PT 21051 RCS Pressure A H4CDAR3 LIT 20509 Cntat Sump Lvl A H4CDAR3 LIT 20510 Cntmt Sump Lvl B H4CDAR5 LT. 20507A S/C Lvl A H4CDAR7 LT. 20507B S/G Lvl B H4CDAR9 LT. 20508A S/G Lvl A H4CDAR7 LT. 20508B S/G Lvl B H4CDAR9 PT 20544A S/G Pressure A H4CDAR7 PT 20544B S/G Pressure B H4CDAR9 PT 20545A S/G Pressure A H4CDAR7 PT 20545B S/G Pressure B H4CDAR9 PT 53621 Cntmt Pressure A H4CDAR3 PT 53622 Cntmt Pressure B H4CDARS XE 01005 Core Exit Temp T-core A H4CDAR3 XE 01007 Core Exit Temp T-core B H4CDAR5 XE 01009 Core Exit Temp T-core A H4CDAR3 XE 01011 Core Exit Temp T-core B H4CDAR5 XE 01013 Core Exit Temp T-core A H4CDAR3 XE 01016 ~ Core Exit Temp T-core B H4CDAR5 XE 0' 019 Core Exit Temp T-core A H4CDAR3 XE Cir23 Core Exit Temp T-core A H4CDARS XE 01025 Core Exit Temp T-core B H4CDAR5 XE 01028 Core Exit Temp T-core B H4CDAR5 XE 01032 Core Exit Temp T-core A H4CDAR3 XE 01035 Core Exit Temp T-core B H4(PARS XE 01039 Core Exit Temp T-core A H4CDAR3 XE 01043 Core Exit Temp T-core B H4CDAR5 XE 01047 Core Exit Tenp T-core A H4CDAR3 XE 01050 Core Exit Temp T-core B H4CDAR5 AE 53811 Cntmt H2 Concentration A H4CDAR3 AE 53812 Cntmt H2 Concentration B H4CDAR5 Neutron Flux signals Neutron Flux to SPDS will be upgraded to class I r
NRCCRM -7 -
i TABLE I (Continued).
CHANNEL CLASSIFICATION MULTIPLEXER ' REMARKS EQUIPMENT DESCRIPTION e
LT 21503A Pressurizer Lvl A- H4CDAR3 LT 21503B Pressurizer Lvl 'A H4CDAR3 LT 21503C Pressurizer Lyl- B 'H4CDARS FT 31902 AFW Flow B H4CDAR5' FT 31903 AFW Flow A H4CDAR3 FT 31802 AFW Flow - B H4CDAR5 FT 31803 AFW Flow _ A H4CDAR3 LT 35809 Condensate Storage A H4CDAR3 Tank Level LT 35810 Condensate' Storage B' H4CDAR5 Tank Level R 15049 Cntmt Hi Range Radiation A H4CDAR3 R 15050 'Cntat Hi Range Radiation B H4CDAR5 LT 20001A Hot Leg Lvl A H4CDAR3
'LT'20001B Hot Leg Lvl B H4CDAR5 LT 20002A _ Hot Leg Lvl' A H4CDAR3 UT 20002B Hot Leg Lvl B H4CDARS SPV 53603 Cntat Isolation valve A H4CDAR3 HV-20611 Cntat Isolation valve B H4CDARS SFV 53504 Cntat Isolation valve A H4CDAR3-SFV 53503 Cntat Isolation valve B H4CDARS HV 20001 Cntat Isolation Valve A H4CDAR3 HV 20002 Cntat Isolation Valve B H4CDAR5 HV 20003 ~ Cntet Isolation Valve' ~A H4CDAR3 HV 26105 Cntat. Isolation Valve -A H4CDAR3 HV 26106 Cntat Isolation valve B H4CDAR5 SFV 53610 Cntat Isolation valve B H4CDARS SFV 53605 Cntmt Isolation Valve A H4CDAR3 SPV 53604 CntatLisolation Valve B H4CDAR5 SFV 53612 Cntat Isolation Valve B H4CDAR5 SFV 53613 Cntat Isolation Valve A H4CDAR3 SFV 53616 Cntmt Isolation valve B d4CDAR5 SFV 22023 Cntat Isolation Valve A H4CDAR3 SPV 22009 Cntat Isolation Valve B H4CDARS ,
SPV 24004 Cntat Isolation Valve A H4CDAR3 SFV 24013 Cntat Isolation Valve B H4CDARS l
.SFV 53615 Cntat' Isolation valve A H4CDAR3 SFV 60002 Cntmt Isolation valve B H4CDARS SFV 60004 Cntat Isolation Valve B H4CDAR5 SPV 60001 Cntmt Isolation Valve A H4CDAR3 SFV 23604 Cntat Isolation valve A H4CDAR7 l
f NRCCRM -8 -
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TABLE I (Continued)
CHANNEL ,
CLASSIFICATION MULTIPLEXER REMARKS EQUIPMENT . DESCRIPTION SFV 60003 Cntat Isolation Valve A H4CDAR3 SFV 66308 Cntat Isolation Valve A H4CDAR3 SFV.66309 Cntat Isolation Valve B H4CDARS SFV 70001 Cntat Isolation Valve A H4CDAR3 SFV 70002 Cntat Isolation Valve B H4CDAR5 SFV 70003 Cntmt Isolation valve A H4CDAR3 SFV 72501 Cntat Isolation valve A H4CDAR3 SFV 72502 Cntmt Isolation Valve B H4CDAR5 SFV 92520 Cntat Isolation valve B H4CDAR5 S
NRCCRM -9 -
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EFFECTIVE DATE 03-27-86 Original
.. WP2525P f
D-0079P I.414 ANATEC CALIBRATION 1.0 PURPOSE
.1 To establish the calibration procedure for analog input and digital input cards of the Anatec Data Acquisition System.
.2 To verify proper operation of the Central Control Unit (CCU) and Uniplex Field Multiplexer (UFM).
2.0 REFERENCES
1
.1 SMUD System Manual TM 219-0015
.2 Operation and Maintenance Instructions Uniplex Field Multiplexer TM
~
600-1001
.3 Technical Manual Central Control Unit TM 600-3001
.4 User's Manual for the System Diagnostic Unit UM 600-5095 .
.5 Technical Description for the I/O Exerciser Test Set DN 600-1625 3.0 SPECIAL TOOLS / EQUIPMENT
.1 Anatec SDU, P/N 600-5095
.2 I/O Exerciser Test Set, P/N 600-1625
.3 Multimeter, Fluke 8060A or equivalent
.4 Millivolt and Current Source, Transmation 1040 or equivalent j .5 Voltage Source, Analogic AN3100 or equivalent
.6 AC Voltage Source, HP Calibrator HP6920B or equivalent
.7 Input Test Connectors for Analog and Digital Input Card
.8 Anatec Test Box
.9 Record all test equipment used on Enclosure 7.5, Test Equipment Usage Log.
s._ I.414-1 Attachment 1
l l
i l
4.0 LIMITATIONS / PRECAUTIONS
.1 Observe all electrical safety precautions.
.2 140 VDC or 115 VAC may be present on input terminal board for card type 600-1179-6. ,
.3 Calibrate one point at a time if plant conditions do not permit simultaneous calibration of entire analog or digital input card.
.4 Coordinate with Electrical Tech Department before calibrating switchyard
. computer points at H4CDAR2 T812,13,14, and 15 when calibrating one point at a time.
.5 Do not remove or install circuit board in the CCU while power is applied.
.6 Do not remove or install the following dedicated circuit cards in' the UFM while power is applied.
.1 600-1143 UFM Coupler Assembly J-1
.2 600-1310 Coder / Decoder J-2
.3 600-1309 UFM Diagnostic Bus Interface J-3
.7 Notify Control Room prior to commencing test.
~g.
5.0 ACCEPTANCE CRITERIA - -
.1 When calibrating analog input cards 600-1146-2, 600-1146-3, 600-1146-4, and 600-1147-6, the "AS LEFT" count value shall be as follows.
.1 #333 2 for 20% calibration.
.2 #CCC t 2 for 80% calibration.
.2 When calibrating analog input card 600-1147-14, the "AS LEFT" value shall be as follows.
.1 #333 t 5 for 20% calibration.
.2 #CCC t 5 for 80% calibration. ,
.3 When testing digital input cards 600-1179-1 and 600-1179-6, verify response data LED 01,-D2, 03, 04, DS, 06, D7, or 08 on the I/O Exerciser changes state when tested.
.4 Consult the I&C Engineer if the above criteria cannot be attained.
I.414-2 Attachment 1
6.0 PROCEDURE r
.1 CCU - UFM Operation
.1 On the CCU diagnostic panel (in H4CDAL), depress the reset switch and verify that all three LED indicators on that panel are off.
See Enclosure 7.3.
.2 On the CCU Select Unit, verify the CCU Select Keyswitch is in
" AUTO' position and that 'CCU 1 SELECTED" and "CCU 2 SELECTED' indicators are switching and the " INHIBIT
- indicator is off.
.3 If the system diagnostic unit is connected up to the system, press the " DIAG OV" key. Verify that " LINK l' is Up, " LINK 2" is Up, and the 10 UFNs in the system show no alarm. If any alarm exists, it will be represented by any combination of the following letters.
.1 C - Burst of Communication Errors.
.2 H - Hardware Error. See Enclosure 7.1.
.3 0 - Diagnstic Error.
.4 P - Power Supply Error.
.5 0 - Override Alarm. -
J k
.6 A - Analog Calibration Alarm. .
.2 UFM Calibration
.1 UFM 1 (H4CDAR1) Function Cards
.1 Calibrate analog input cards in J4, JS, and J6 per Step 6.3.2.
.2 Calibrate analog input cards in J7, and J8 per Step 6.3.3.
.3 Test digital input cards in J10, Jil, J12, and J13 per Step 6.4.1.
.4 Calibrate analog input cards J9, J14, and J15 per Step 6.3.1.
.2 UFM 2 (H4CDAR2) Function Cards
.1 Calibrate analog input cards in J4, JS, and J6 per Step 6.3.4.
.2 Test Digital input cards in J10 and J11 per Step 6.4.1.
.3 Calibrate analog input cards J12, J13, J14, and J15 per Step 6.3.5. Coordinate with Electrical Tech Department before lifting any field wires. ,
A. I.414-3 Attachment 1
-l PROCEDURE (Continued) 6.2 .3 UFM 3 (H4CDAR3) Function Cards
.1 - Calibrate aaalog input cards in J4, J5, J6, J7, and J8 per Step 6.3.1.
.2 Calibrate analog input card in J9 per Step 6.3.2.
.3 Calibrate analo3 input card in J10 per Step 6.3.3.
.4 Test digital input cards in J12 through J19 per Step 6.4.1.
.4 UFM 4 (H4COAR4) Function Cards
.1 Calibrate analog input cards in J4 per Step 6.3.1.
.2 Calibrate analog input card in J5 per Step 6.3.2.
.3 Calibrate analog input card in J6 per Step 6.3.3.
.4 Test digital input cards in J10, J11, and J12 per Step 6.4.1.
.5 Test digital input card in J14 per Step 6.4.2.
.5 UFM S (H4CDARS) Function Cards ,
.1 Calibrate analog input cards.in J4, J5, J6, J7, and J8 per Step 6.3.1. -
f.
.2 Calibrate analog input card in J9 per Step 6.3.2.
.3 Calibrate analog input card in J10 per Step 6.3.3.
.4 Test digital input cards in J13 through J19 per Step 6.4.1.
.6 UFM 6 (H400AR6) Function Cards
.1 Calibrate analog input cards in J4, J5, and J6 per Step. 6.3.1.
.2 Calibrate analog input card in J7 per Step 6.3.2.
.3 Calibrate a'nalog injut card in J8 per Step 6.3.3.
.4 Test digital input cards in J10, J11 J12, and J13 per Step 6.4.1.
.7 UFM 7 (H4COAR7) Function Cards
.1 Calibrate analog input cards in J4, JS, and J7 per Step 6.3.1.
.2 Test digital input cards in J9, J10, J11, J15, and J20 per Step 6.4.1.
I.414-4 Attachment 1
+-
l PROCEDURE (Continued) 6.2 .7 .3 Test digital input cards in J12, J13 J14. J16, and J19 per Step 6.4.2.
.8 UFM 8 (H4CDAR8) Function Cards
.1 Calibrate analog inpu.t cards in J4 per Step 6.3.1.
.2 Test digital input cards in J10 through J18 per Step 6.4.1.
.3 Test digital input card in J20 per Step 6.4.2.
.9 UFM 9 (H4CDAR9) function Cards
.1 Calibrate analog input cards in J4, JS, and J7 per Step 6.3.1.
.2 Test digital input cards in J9, J10, Jil, JIS, and J20 per Step 6.4.1.
.3 Test digital input cards in J12, J13, J14, J16, and J19 per Step 6.4.2.
.10 UFM (H4CRAD10) function Cards
.1 Calibrate znalog input card in J4 per Step 6.3.1.
. .2 Test digital input cards in J9 through J19 per Step 6.4.1.
.3 Test digital input card in J20 per Step 6.4.2.
.3 Analog Input Card Calibration '
l
! .1 Analog Input Card 600-1146-2 Calibration 1
.1 Insert I/O Exerciser in any UFM slot J4 through J20.
.2 Monitor channel on input card to be calibrated with the I/O Exerciser. Refer to data sheets (Enclosure 7.4) for FL/GL listing.
.3 Remove the input cable and connect the test connector to J2 of the analog input card to calibrate all 8 inputs at once, or, lift the field wires at the terminal board and connect a
) current source to calibrate one point at a time. Refer to TB configuration for the 600-1146 analog input card in Enclosure
( 7.2.
.4 Apply 4.00 t .01 MA through a 253.2 ohm resistor for a 20%
count value on the I/O Exerciser. Record the response' data
) value in the "AS FOUND" column of the data sheet (Enclosure 7.4).
L I.414-5 Attachment 1
~
l' PROCEDURE (Continued) 6.3 .1 .5 Change the current to 16.00 t .01 MA for an 80% count value. Record the response 'talue in the "AS FOUhD" column of the data sheet.
.6 Adjust "0FFSET" and " GAIN' adjustments as necessary to obtain a 20% reading of $333 2 2 counts and an 80% reading of #CCC i i 2 counts for the channel. Record the "AS LEFT' values in the data sheet.
.7 If calibrating one point at a time, reconnect the field wires for the point just completed.
.8 Repeat Steps 6.3.1.2 to 6.3.1.7 for channels 2 through 8.
.9 If test connector was used, remove it and reconnect input connector to J2 of input card.
.10 Remove I/O Exerciser.
I .2 Analog Input Card 600-1146-3 Calibration
~
.1 Insert I/O Exerciser in any UFM slot J4 through J20.
.2 Monitor channel on input card to be calibrated with the I/O
- Exerciser. -Refer to data sheets (Enclosure 7.4) for FL/GL - -
listing.
Remove the input cable and connect the test connector to J2 of j .3 the analog input card to calibrate all 8 inputs at once, or, lift the field wires at the terminal board and connect a voltage source to calibrate one point at a time. Rrfer to TB configuration for the 600-1146 analog input card in Enclosure 7.2.
.4 Apply 2.000 .002 volts for a 20% count value on the I/O Exerciser. Record the response data value in the "AS FOUND" column of the data sheet (Enclosure 7.4).
.5 Change the voltage to 8.000 .002 volts for an 80% count '
value. Record the response value in the "AS FOUND" column of
'he data sheet.
.6 Adjust '0FFSET' and " GAIN" adjustments as necessary to obtain a 20% reading of #333 1 2 counts and an 80% reading of #CCC t 2 counts for the channel. Record the "AS LEFT" values in the data sheet.
.7 If calibrating one point at a time, reconnect the field wires for the point just completed.
i i
I.414-6 1
l Attachment 1
,v
PROCEDURE (Continued)
.f~~
- 6.3 .2 .8 Repeat Steps 6.3.2.2 to 6.3.2.7 for channels 2 through 8.
.9 If test connector was used, remove it and reconnect input connector to J2 of input card.
.10 Remove I/O Exerciser.
.3 Analog Input Card 600-1146-4 Calibration
.1 Insert I/O Exerciser in any UFM slot J4 through J20.
.2 Monitor channel on input card to be calibrated with the I/O Exerciser. Refer to data sheets (Enclosure 7.4) for FL/GL '
listing.
.3 Remove the input cable and connect the test connector to J2 of the analog input card to calibrate all 8 inputs at once, or, lift the field wires at the terminal board and connect a voltage source to calibrate one point at a time. Refer to T8 configuration for the 600-1146 analog input card in Enclosure 7.2. -
.4 Apply -6.000 t .002 volts for a 20% count value on the I/O Exerciser. Record the response data value in the "AS FOUNO" column of the data sheet (Enclosure 7.4).
. .5 Change the voltage to &6.000 t .002 volts for an 80% count ~ i value. Record the response value in ihc "AS FOUNO" column of the data sheet.
.6 Adjust "0FFSET" and " GAIN" adjustments as necessary to obtain a 20% reading of #333 2 counts and an 80% reading of #CCC t 2 counts for the channel. Record the "AS LEFT" values in the data sheet.
1
( .7 If calibrating one point at a time, reconnect the field wires for the point just completed.
.8 Repeat Steps 6.3.3.2 to 6.3.3.7 for channels 2 through 8.
.9 If test connector was used, remove it and reconnect input connector to J2 of input card.
.10 Remove I/O Exerciser.
.4 Analog Input Card 600-1147-14 Calibration
.1 Insert I/O Exerciser in any UFM slot J4 through J20.
N, I.414-7 Attachment 1
PROCEDURE (Continued)
.6.3 .4 .2 If calibrating one point at a time, replace the reference junction RTO at the terminal board with a 100 ohn 1% resistor.
.3 Monitor channel on input card to be calibrated with the I/O Ex6tciser. Refer to data sheets (Enclosure 7.4) for FL/GL listing. ,,
.4 Remove the input cable and connect the test connector to J2 of
-the analog input card to calibrate all 8 inputs at once, or, lift the field wires at the terminal board and connect a millivolt source to calibrate one point at a time. Refer to T8 configuration for the 600-1147 analog input card in Enclosure 7.2. -
.5 Apply 3.82 ! .01 MV for a 20% count value on the I/O Exerciser. Record the response data value in the 'AS FOUNO" column of the data sheet (Enclosure 7.4).
.6 Change the voltage to 15.28 t .01 My for an 80% count value. Record the response value in the "AS FOUNO" column of the data sheet. ,
.7 Adjust " CHANNEL OFFSET" and " GAIN' adjustments as necessary to obtain a 20% reading of #333 t 5 counts and an 80% reading 4 of #CCC i 5 counts for the channel. Record the 'AS LEFT" ~
values in the data sheet.
.8 If calibrating one point at a time, reconnect the field wries
. ;h -"
for the point just completed.
.9 Repeat Steps 6.3.4.3 to 6.3.4.8 for channels 2 through 8.
.10 If test connector was used, remove it and reconnect input connector to J2 of input card.
.11 If a 100 ohm resistor was installed, remove it and reconnect the reference temperature RTD. l
.12 Remove I/O Exerciser. l 1
Analog Input Card 600-1147-6 Calibration l
.5
.1 Insert I/O Exerciser.in any UFM slot J4 through J20.
.2 Monitor channel'on input card to be calibrated with the I/O Exerciser. Refer to data sheets (Enclosure 7.4) for FL/GL listing.
1 I.414-8 l
Attachment 1
PROCEDURE (Continued) r j 6.3 .5 .3
~ Remove the input cable and connect the test connector to J2 of the analog input card to calibrate all 8 inputs at once, or, lift the field wires at the terminal board and connect a millivolt source to calibrate one point at a time. Refer to TB configuration for the 600-1147 analog input card in Enclosure 7.2. .-
.4 Apply -60.00 t .01 MV for a 20% count value on the I/O Exerciser. Record the response data value in the "AS FOUND" column of the data sheet (Enclosure 7.4).
.5 Change the voltage to +60.00 t .01 NV for an 805 count value. Record the response value in the "AS FOUNO" column of the data sheet.
.6 Adjust " CHANNEL OFFSET" and " GAIN" adjustments as necessary to obtain a 20% reading of #333 t 2 counts and an 80% reading of #CCC t 2 counts for the channel. Record the 'AS LEFT" values in the data sheet.
.7 If calibrating one point at a time, reconnect the field wries for the point just completed.
.8 Repeat Steps 6.3.5.3 to 6.3.5.7 for channels 2 through 8.
. .9 If test connector was used, remove it and reconnect input ,
connector to J2 of input card.
.10 Remove I/O Exerciser.
.4 Digital Input Card Test
.1 Digital Input Card 600-1179-1 Test
.1 Insert I/O Exerciser in any UFN slot J4 through J20.
.2 Monitor first 8 digital input (FL/13) on card to be tested with I/O Exerciser. Refer to data sheets (Enclosure 7.4) for FL/GL listing.
.3 To test one point at a time, skip to Step 6.4.1.13.
.4 Remove the input cables at J1 and J2 of the digital input card and connect the Anatec test box connector to J1 to test the first 8 inputs at once.
.5 On the Anatec test box, turn test switch to " AUTO.*
\- I.414-9 I -
l.
Attachment 1
PROCEDURE (Continued) 6.4 .1 .6 Verify response data LEDs D1, D2, D3, 04, DS, D6, D7, and 08 sequentially change state. Check off " LED CHANGE STATE" blocks on data sheet (Enclosure 7.4).
.7 On Anatec test box, turn test switch to MANUAL."
.8 Remove test connector from J1 of the digital input card and connect it to J2 and monitor the second 8 digital inputs (FL/14) to be tested with the I/O Exerciser.
.9 Repeat Stops 6.4.1.5 to 6.4.1.7.
.10 Remove test connector from J2 of digital input card.
.11 Reconnect input cables to J1 and J2 of digital input card.
.12 Skip to Step 6.4.1.20.
.13 Remove field wires at the terminal board. Refer to TB configuration for the 600-1179 digital input card in Enclosure 7.2.
.14 Short the input V+ to RTN at the terminal board.
.15 Verify the corresponding response data LED 01, 02, 03, 04, DS, .
06, 07, or 08 changes state. Check off " LED CHANGE STATE' .]
. .) . '
block on data sheet (Enclosure 7.4).
.16 Remove short at terminal board input and reconnect field wires.
.17 Repeat Steps 6.4.1.13 to 6.4.1.16 for the remaining 7 digital inputs.
.18 Monitor the second 8 digital inputs (FL/14) to be tested with I/O Exerciser.
.19 Repeat Steps 6.4.1.13 to 6.4.1.17 for the remaining 7 digital inputs.
.20 Remove I/O Exerciser.
.2 Digital Input Card 600-1179-6 Test NOTE:
140VDC or 115VAC may be present on input terminal board.
.1 Insert I/O Exerciser in any UFM slot J4 through J20.
I.414-10
- Attachment 1
PROCEDURE (Continued)
I 6.2 .2 .2 Monitor first 8 digital input (FL/13) on card to be tested with I/O Exerciser. Refer to data sheets (Enclosure 7.4) for FL/GL listing.
.3 Remove field wires at terminal board. Refer to TB-configuration for the~ 600-1179 digital input card in Enclosure 7.2.
.4 Apply 115VAC to the input V+ and RTN at the terminal board.
.5 Verify the corresponding response data LED 01, 02, 03, D4, 05, C6, 07, or 08 changes state. Check off " LED CHANGE STATE" block on data sheet (Enclosure 7.4).
.6 Remove 115VAC from terminal board and reconnect field wires.
.7 Repeat Steps 6.4.2.3 to 6.4.2.6 for the remaining 7 digital inputs.
l
.8 Nonitor the second 8 digital inputs (FL/14) to be tested with I/O Exerciser. .
.9 Repeat Steps 6.4.2.3 to 6.4.2.7 for the remaining 7 digital inputs.
. .10 Remove I/O Exerciser.
~ ..
7.0 ENCLOSURES
.1 Housekeeping Codes
.2 T8 Configuration for 600-1146, 600-1147, and 600-1179 Boards
.3 CCU Diagnostic Panel
! .4 Data Sheets
.5 Test Equipment Usage Log I
t I.414-11 Attachment 1
ENCLOSURE 7.1 HOUSEKEEPING CODES HSKP Bit No. Description PSB LS8 10 0A Normal UFM response A = 0 - no alarm A = 1 - power supply 0 = 0 - no alarm 0 alarm for contact status input check (all l's or all O's check)
.11 00 UFM interrogate dropped to PIO (i.e., PIO to PIO) 00 10 No FL/GL response. Function card did not respond to interrogate request.
C1 10 Multiple FL/GL response. More than one function card responds to interrogate request. -
01 11 Bad UFM bus.
00 11 No response from UFM or ba'd UFM parity.
.~
l I.414-12 l
l l
Attachment 1
ENCLOSURE 7.2 T8 CONFIGURATION FOR 600-1146 AND 600-1147 BOARDS g
600-1146 600-1147 T8 No. T8 No.
4 4+
~
IN 9 10+
IN 11 23+
3TN CH-6 CH-6 15 27-IN l 16 29+
\ I.414-13 l
l Attachment 1
ENCLOSURE 7.2 (Continued)
TB CONFIGURATION FOR 600-1179 BOARDS 600-1179 T8 No.
I V+ 23 V+
CH-1 CH-9 2 RTN 24 RTN 4 V+ 26 V+
CH-2 CH-10 S RTN 27 RTN 6 V+ 28 V+
9 V+ 31 V+
E il V+ 33 V+
CH-S CH-13 12 RTN 34 RTN 14 V+ 36 V+
.,) ~
~
15 RTN 37 RTN, 16 V+ 38 V+
CH-7 CH-15 17 RTN 39 RTN 19 V+ 41 V+
CH-8 CH-16 20 RTN 42 RTN I.414-14 Attachment 1
ENCLOSURE 7.3
- g. CCU DIAGNOSTIC PANEL N
O!s
.J w
a.
33 8 '
4 5
e E
? O !s s 5 g
';a; p%
2 O
e g$
u -
Y ad I diO 1 4
i.
/ I.414-15 k
l l
Attachment 1 ,j
ENCLOSURE 7.4 DATA SHEET UFM 1 (H4CDAR1)
AS FOUNO-DATA AS LEFT DATA UFM F,k 9k (#333) (#CCC) (#333) (#CCC) 20% 80% 20% 80%
^
001 01 00 001 02 00 J4 001 03 00 T84 001 04 00 600-1146-3 001 05 00 0-10VOC 001 06 00 '
001 07 00 {
001 08 00 001 01 01 001 02 01 JS 001 03 01 '
T85 001 04 01
~
600-1146-3 001 05 01 r 0-10VOC 001 06 01 (
001 07 01 001 08 01 001 01 02 _
'02
)-
001 02 J6 001 03 02 _
TB6 001 04 02 .
600-1146-3 001 05 02 0-10VDC 001 06 02 001 07 02 001 08 02 001 01 03 001 02 03 J7 001 03 03 __
TB7 001 04 03 600-1146-4 001 05 03 10VOC 001 06 03 001 07 03 001 08 03 Performed By Date _,
Reviewed By Date I.414-16
' Attachment 1
5 ENCLOSURE 7.4 (Continued) g .. . DATA SHEET'UFM 1 (H4CDARI) (Continued)
AS FOUNO DATA LAS LEFT DATA 91 5 fL EL (#333) (#CCC) (#333) (#CCC) 205 805 205 805 001 01 04 001 02 04 J8 001 03 04 TB8 001 04 04
'600-1146-4 001 05 04 110VDC 001 06 04 001 07 04 001 08 04 001 01 09 001 02 03 J9 001 03 09 TB9 001 04 09 600-1146-2 001 05 09 0-5V0C 001 06 09 ,
001 07 09 001 08 09
. UFM EL Ek LED CHANGED STATE (a)
~
001 13 00 01 001 13 00 02 _
001 13 00 03 J10 001 13 00 04 TE10 001 13 00 05 600-1179-1 001 13 00 06 OI DRY 001 13 00 07 CONTACT 001 13 00 08 001 14 00 01 001 14 00 02 001 )
14 00 03 '
001 14 00 04 ~-
001 14 00 05 001 14 00 06 001 14 00 07 1 001 14 00 08 l
4
. Performed By Date Reviewed By Date g I.414-17 l
Attachment 1
l.
l ENCLOSURE 7.4 .(Continued)
DATA SHEET UFM 1 (H4CDAR1) (Continued)
Mff3 & E LED CHANGED STATE (1) 001 13 01 01 001 13 01
02 ~
001 13 01 D3 J11 001 13 01 04 T811 001 -13 01 05 600-1179-1 001 13 01 D6 DI DRY 001 13 01 D7 CONTACT 001 13 01 D8 001 14 01 D1 001 14 01 02 001 14 01 D3 001 14 01 04 001 14 01 DS 001 14 01 06 001 14 01 07 001 14 01 08 001 13 02 D1 001 13 02 D2 __
001 13 02 03 J12 001 13 02 04 -
T812 600-!179-1 001 001 13 13 02 02 05 06
.)- .
DI DRY 001 13 02 07 CONTACT 001 13 02 08 001 14 02 01 001 14 02 D2 001 14 02 03 001 14 02 04 001 14 02 05 001 14 02 06 001 14 02 07 001 14 02 08 Performed By Date Reviewed By Date I.414-18 Attachment 1
i ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 1 (H4CDAR1) (Continued)
UFM FL EL LEO CHANGE 0 STATE (2) 001 13 03 01 001 13 03 _
02 001 13 03 03 J13 001 13 03 04 TB13 001 13 03 05 600-1179-1 001 13 03 06 OI DRY 001 13 03 07 CONTACT 001 13 03 08 001 14 03 01 001 14 03 02 001 14 03 03 001 14 03 04 001 14 03 05 001 14 03 06 001 14 03 07 001 14 03 D8 AS FOUNO DATA AS LEFT DATA MM EL SL (#333) (#CCC) (#333) (#CCC) 20% 80% 205 805
~
001 01 07 -
001 02 07 J14 001 03 07 T814 001 04 07 600-1146-2 001 05 07 0-SV0C 001 06 07 001 07 07 001 08 07 001 01 08 001 02 08 J15 001 03 08 TB15 001 04 08 600-1146-2 001 05 08 0-SVOC 001 06 08 001 07 08 001 08 08 Performed By Date Reviewed By Date l s. _ . I.414-19 Attachment 1.
^
i l-.
ENCLOSURE 7.4 -(Continued)
DATA SHEET UFM 2 (H4C0AR2)
AS FOUND DATA AS LEFT DATA Vf.5, f.L gk (#333) (#CCC) (#333) (#CCC) 205 801 201 805
~~
002 01 00' 002 02 00 J4 002 03 00 T84 002 04 00 600 1147 002 05 00 TYPE T T/C 002 06 00 002 07 00 002 08 ' 00 002 01 01 002 02 01 J5 002 03 01 TBS 002 04 01 600-1147-14 002 05 01 . s TYPE T T/C 002- 06 01 002 07 01 002 08 01 02 002 01 ~
002 02 02 J6 002 03 02 T86 002 04 02 600-1147-14 002 05 02 TYPE T T/C 002 06 02 002 07 02 002 08 02 Performed By Date Reviewed By Date I.414-20 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 2 (H4CDAR2) (Continued)
AS FOUND DATA AS LEFT DATA UFM & R (#333) (#CCC) (#333) 20%
(#CCC) 80%
20% 80%
002 01 03 002 02 03 J12 002 03 03 T812 002 04 03 600-1147-6 002 05 03 t 100MV 002 06 03 002 07 03 002 08 03 002 01 04 002 02 04 J13 002 03 04 T813 002 04 04 600-1147-6 002 05 04 -
i 100MV 002 06 04 002 07 04 002 08 04 05 l' 002 002 01 02 05 .) '
J14 002 03 05 T814 002 04 05 600-1147-6 002 05 05 t 100MV 002 06 05 002 07 05 002 08 05 002 01 06 002 02 06 J15 002 03 06 T815 002 04 06 600-1147-6 002 05 06 t 100MV 002 06 06 002 07 06 002 08 06 Perforned By Date Reviewed By Date I.414-22 Attachment 1
L w & Ee- -
, ENCLOSURE 7.4 (Continued) 7 OATA SHEET UFM 2 (H4C0AR2) (Continued) 9f3 f.1 gi LED CHANGED STATE (1)
'002 13 00 01 002 13 00 02 002 13 00 03 J10 002 13 00 04 T810 002 13 00 05 600-1179-1 002 13 00 06 OI DRY 002 13 00 07 CONTACT 002 13 00 08 002 14 00 01 1 002 14 00 02 002 14 00 03 002 14 00 04
'002 14 00 05 002 14 00 06 i 002 14 00 07 002 14 00 08 -
002 13 01 01 002 13 01 02 002 13 01 03 J11 002 13 01 04 T811 002 13 01 05 600-1179-1 002 13 01 06 OI DRY 002 13 01 07 CONTACT 002 13 01 08 002 14 01 01 002 14 01 02 002 14 01 03 002 14 01 04 002 14 01 05 002 1, 01 06 002 14 01 07 002 14 01 08 Performed By Date Reviewed By Date 4
k I.414-21 Attachment 1
. ENCLOSURE 7.4 (Continued) je- DATA SHEET UFN 3 (H4COAR3)
AS FOUNO DATA AS LEFT DATA Mf3 f( SL (#333) (#CCC) (#333) (#CCC) 205 80M 20M 805
~
003 01 00 003 02 ~ 00 J4 003 03 00 T84 003 04 00 600-1146-2 003 05 00 0-5VOC 003 06 00 '
003 07 00 003 08 00 ,
003 01 01 003 02 01 J5 003 03 01 T85 003 04 01 600-1146-2 003 05 01 -
0-SVOC 003 06 01 003 07 01 003 08 01 f.
( .. 003 01 02 _-
003 02 02 J6 003 03 02 __
T86 003 04 02 600-1146-2 003 05 02 0-SVOC' 003 06 02 003 07 02 r
003 08 02 003 01 03 __
! 003 02 03 J7 003 03 03 T87 003 04 03 600-1146-2 003 05- 03 0-SVOC 003 06 03 .
003 07 03 003 08 03 Performed By Date Reviewed By Date
- t. I.414-23 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 3 (H4C0AR3) (Continued)
AS FOUNO DATA AS LEFT DATA EE f.L EL (#333) (#CCC) (#333) (#CCC) 205 80% 205 805 003 01 04 '
003 02 04 J8 003 03 04 TB8 003 04 04 600-1146-2 003 05 04 0-SVDC 003 06 04 003 07 04 003 08 04 003 01 05 003 02 05 J9 003 03- 05 T89 003 04 05 600-1146-3 003 05 05 ~
0-10V0C 003 06 05 003 07 05 003 08 05-003 003 01 02 06 05 _
')-
J10 003 03 06 T810 003 04 06 600-1146-4 003 05 06 10VOC 003 06 06 003 07 05
- 003 08 06 __
Performed By Date Reviewed By Date 1
, I.414-24 Attachment 1
ENCLOSURE 7.4 (Continued)-
r- OATA SHEET UFN 3 (H4C0AR3) (Continued)
H [L gk LEO CHANGED STATE (1) ,
003 13 07 01 003 13 07 02 003 13 07 03 J12 003 13 07 04 T812 003 13 07 05 600-1179-1 003 13 07 06 OI ORY 003 13 07 07
- CONTACT 003 13 07 08 003 14 07 01 003 14 07 02 003 14 07 03
~i 003 14 07 04 003 14 07 05 003 14 07 06 003 14 07 07 003 14 07 08 ,
003 13 00 01 003 13 00 02
. 003 13 00 03 (s J13 003 13 00 04 .
T813 003 13 00 DS 600-1179-1 003 13 00 06 OI ORY 003 13 00 07 CONTACT 003 13 00 08 003 14 00 01 4 003 14 00 02
, 003 14 00 03 003 14 00 04 003 14 00 05 003 14 00 06 003 14 00 07 003 14 00 08 Performed By Date Reviewed By Date l
- t. I.414-25 Attachment 1
i l
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 3 (H4C0AR3) (Continued)
UFM & E LED CHANGED STATE (s) 003 13 01 01 003 13 01 -
02 003 13 01 03 J14 003 13 01 04 TB14 003 13 01 05 600-1179-1 003 13 01 06 DI DRY 003 13 01 07 CONTACT 003 13 01 08 003 14 01 01 ~
003 14 01 02 003 14 01 03 003 14 01 04 003 14 01 05 003 14 01 06 003 14 01 07 08 003 14 01 .
003 13 02 01 003 13 02 02 003 13 02 03 . . , .
04 J15 003 13 13 02 02 05 S) '
TBIS 003 600-1179-1 003 13 02 06 -
DI ORY 003 13 02 07 CONTACT 003 13 02 08 003 14 02 01 003 14 02 02 003 14 02 03 003 14 02 04 003 14 02 05 003 14 02 06 003 14 02 07 003 14 02 08 Date Performed By Date Revicwed By I.414-26 Attachment 1
ENCLOSURE 7.4 (Continued) f- DATA SHEET UFM 3 (H4CDAR3) (Continued) 973 & E LEO CHANGE 0 STATE
.. (2) 003 13 03 ~~
01 003 13 03 02 003 13 03 03 J16 003 13 03 04 TB16 003 13 03 05 600-1179-1 003 13 03 06 OI DRY 003 13 03 07 CONTACT 003 13 03 08 003 14 03 01 003 14 03 02 003 14 03 03 003 14 03 04 003 14 03 05 003 14 03 06 003 14 03 07 003 14 03 06 .
003 13 04 01 003 13 04 02 p, 003 13 04 03
\ J17 003 13 04 04 '
T817 003 13 04 05 600-1179-1 003 13 04 06 OI DRY 003 13 04 07 CONTACT 003 13 04 08 003 14 04 01 003 14 04 02 003 14 04 03 003 14 04 04 003 '4 04 05 003 14 04 06 003 14 04 07 003 14 04 08 l
Performed By Date i
Reviewed 8y Date l
.. I.414-27 Attachee, I -- ___ _ _ _ . _ _ _ . . _ . _ _ ___ _ _ __
l s.
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 3 (H4CDAR3) (Continued) y[M, Ek & LED CHANGED STATE (a) 003 13 05 --
D1 003 13 05 02 003 13 05 03 J18 003 13 05 04 T818 003 13 05 DS 600-1179-1 003 13 05 06 OI DRY 003 13 05 07 CONTACT 003 13 05 D8 003 14 05 D1 003 14 05 02 -
003 14 05 03 003 14 05 D4 003 14 05 05 003 14 05 06 ~ '
003 14 05 07 003 14 05 08 .
003 13 06 D1 003 13 06 02 003 13 06 D3 J19 003 13 06 C4
--) -
T819 003 13 06 05 600-1179-1 003 13 06 06 DI DRY 003 13 06 07 CONTACT 003 13 06 98 003 14 06 01 003 14 06 02 003 14 06 03 003 14 06 04 003 14 05 05 003 14 06 06 003 14 06 07 003 14 06 08 Performed By Date ReviLwed By Date I.414-28 Attachment 1 j
- r. .
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 4 (H4C0AR4)
/_
AS FOUND DATA AS LEFT OATA UFM F1 G1 (#333) (#CCC) (#333) (#CCC) 20% 20% 20% 80%
00 004 01 004 02 00 J4 004 03 00 T84 004 04 00 600-1146-2 004 05 00 0-SVOC 004 06 00 004 07 00 004 08 00 004 01 01 004 02 01 JS 004 03 01 185 004 04 01 600-1146-3 004 05 01 -
0-10VDC 004 06 01 004 07 01 004 08 01 004 01 02 004 02 02 .'
J6 004 03 02 TB6 004 04 02 600-1146-4 004 05 02 10VOC 004 06 02 004 07 02 004 08 02 Performed By Date Reviewed By Date l
I.414-29 V.
Attachment 1
+
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 4 (H4CDAR4)
Mf!, [L SL LEO CHANGE 0 STATE (2) 004 13 00 D1 004 13 00 --
02 004 13 00 D3 J10 004 13 00 04 T810 004 13 00 05 600-1179-1 004 13 00 D6 DI DRY 004 13 00 07 D8 g CONTACT 004 13 00 B
004 14 00 D1 004 14 00 02 004 14 00 03 004 14 00 04 004 14 00 05 004 14 00 06 004 14 00 D7 004 14 00 08 _ (
004 13 01 D1 004 13 01 D2 004 13 01 D3 J11 004 13 01 04 3.
004 13 01 05 J.'
T811 600-1179-1 004 13 01 03 DI ORY 004 13 01 07 CONTACT 004 13 01 08 004 14 01 01 004 14 01 02 004 14 01 03 004 14 01 04 004 14 01 05 004 14 01 06 004 14 01 D7 004 14 01 08 Performed By Date Reviewed By Date I.414-30 Attachment 1
ENCLOSURE 7.4 (Continued) r, DATA SHEET UFM 4 (H4C0AR4)
VfM R $1 LED CHANGED STATE (d
004 13 02 01 004 13 02 02 004 13 02 03 J12 004 13 02 04 TB12 004 13 02 05 600-1179-1 004 13 02 06 O! DRY 004 13 02 07 63NTACT 004 13 02 08 004 14 02 01 004 14 02 02 004 14 02 03 004 14 02 04 004 14 02 05 004 14 02 06 004 14 02 07 004 14 02 03
- 004 13 04 01 004 13 04 02 004 13 04 03 J14 004 13 04 04 TB14 004 13 04 05 600-1179-6 004 13 04 06 0! 140VOC 004 13 04 07 OR 115VAC 004 13 04 08-004 14 04 01 004 14 04 02 004 14 04 03 004 14 04 04 004 14 04 05 004 14 04 06 004 14 04 07 004 14 04 08 Performed By Date Reviewed By Date I.414-31
.ttachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 5 (H4CDARS) (Continued)
AS FOUNO DATA AS LEFT OATA MER EL EL (#333) (fCCC) (#333) (#CCC) 20% 80% ,, 20% 80%
005 01 00 005 02 00 _
J4 005 03 00 TB4 005 04 00 600-1146-2 005 05 00 0-SVOC 005 06 00 005 07 00 005 08 00 005 01 01 005 02 01 J5 005 03 01 TBS 005 04 01 600-1146-2 005 05 01 0-SVOC 005 06 01 005 07 01 -
005 08 01 005 01 02 005 02 02 J6 005 03 02 ,
TB6 005 04 02 .;/ ~
600-1146-2 005 05 02 0-SVOC 005 06 02 005 07 02 005 08 02 005 01 03 005 02 03 J7 005 03 03 . .
T87 005 04 03 600-1146-2 005 05 03 0-SVOC 005 06 03 005 07 03 005 08 03 Performed By Date Reviewed By _
Date I.414-32 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 5 (H4CDARS) (Continued)
UFM & E LED CHANGED STATE (2) 005 13 00 01 005 13 00 02 005 13 00 03 J13 035 13 00 04 TB13 005 13 00 05 600-1179-1 005 13 00 06 O! DRY 005 13 00 07 l
CONTACT 005 13 00 -
08 005 14 00 01 005 14 00 02 005 14 00 03 005 14 00 04 005 14 00 05 005 14 00 06 '
005 14 00 07 005 14, 00 08 _
005 13 01 01 005 13 01 02 005 13 01 03 J14 005 13 01 04 -
T814 600-1179-1 005 005 13 13 01 01 05 06
') -
DI ORY 005 13 01 07 CONTACT 005 13 01 08 005 14 01 01
- 005 14 01 02 ,
005 14 01 03 t 005 14 01 04 005 14 01 05 005 14 01 06 005 14 01 07 005 14 01 08 .
Performed By .
Date Reviewed By Date I.414-34 Attachment 1
ENCLOSURE 7.4 (Continued) f' OATA SHEET UFM 5 (H4C0AR5) (Continued)-
AS FOUND DATA AS LEFT DATA MER FL SL (#333) (#CCC) (#333) (#CCC) 205 805 205 805 005 01 04 -
005 02 04 J8 005 03 04 T88 005 04 04 600-1146-2 005 05 04 0-5VOC 005 06 04 005 07 04 005 08 04 005 01 05 005 02 05 J9 005 03 05 T89 005 04 05 ._
600-1146-3 005 05 05 0-10VOC 005 06 05 005- 07 05 005 08 05 005 01 06 005 02 06 J10 005 03 06- _ .
T810 005 04 06 --
600-1146-4 005 05 06 t10VOC 005 06 06 005 07 06 005 08 06 Performed By Date Reviewed By Date
- I.414-33 Attachment 1
I ENCLOSURE 7.4 (Continued)-
I j~ DATA SHEET UFN 5 (H4CDARS) (Continued) f l
UFN & g( LED CHANGE 0 STATE (2) 005 13 02 _
01 005 13 02 02 005 13 02 03 _
J15 005 13 02 04 T815 005 13 02 05 600-1179-1 005 13 02 06 DI ORY 005 13 02 07 CONTACT 005 13 02 08 005 14 02 01 005 14 02 D2 005 14 02 03 005 14 02 04
( 005 14 02 05 l 005 14 02 06 005 14 02 07 005 14 02 08 .
005 13 03 01 005 13 03 02 005 13 03 03
-g". J16 005 13 03 04
( T816 005 13 03 05 ^
600-1179-1 005 13 03 06 O! ORY 005 13 03 07 CONTACT 005 13 03 08 005 14 03 01 005 14 03 02 005 14 03 03 005 14 03 04 005 14 03 05 ,
005 14 03 06 005 14 03 07 005 14 03 08
[
Performed By Date Reviewed By Date v I.414-35 P
, Attachment 1
ENCLOSURE 7.4 (Contin $ed)
DATA SHEET UFN 5 (H4CDARS) -(Continued) yf3 & R LED CHANGED STATE (a) 005 13 04 "
D1 005 13 04 D2 005 13 04 03 J17 005 13 04 04 T817 005 - 13 04 05 600-1179-1 005 13 04 06 DI ORY 005 13 04 07 CONTACT 005 13 04 08 005 14 04 D1 005 14 04 02 005 14 04 D3 005 14 04 D4 005 14 04 DS 005 14 04 06 005 14 04 D7 005 14 04 08 -
005 13 05 01 -
005 13 05 02 005 13 05 03 04 J18 005 13 05
- TB18 005 13 05 05 -
600-1179-1 005 13 05 D6 DI ORY 005 13 05 D7 CONTACT 005 13 05 08 005 14 05 01 005 14 05 02
! 005 14 05 03 005 14 05 04-
. 005 14 05 05 005 14 05 06 005 14 05 07 005 14 05 08 1
l Performed By Date Date j Reviewed By
, i i
I.414-36 2
' . Attachment 1
CNCLOSURE 7.4 (Continued) . !'
,- DATA SHEET UFM S (H4CDARS) (Continued)
UFM f_( Sk LED CHANGED STATE (2) 005 13 06 D1 1
005 13 06 D2 005 13 06 D3 J19 005 13 06 04 T819 005 13 06 05 600-1179-1 005 13 06 06 DI DRY 005 13 06 07 CONTACT 005 13 06 D8 005 14 06 D1 005 14 06 02 005 14 06 03 005 14 06 04 005 14 06 05 005 14 06 D6 005 14 06 07 005 14 06 D8 .
s Performed By Date Reviewed By Date
(, I.414-37 Attachment 1
~
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 6 (H4C0AR6) (Continued)
ASFOUNDOhTA AS LEFT DATA Uff!! f.L SL (#333) (#CCC) (#333) (#CCC) 20% 80% 20% 80%
006 01 00 --
006 02 00 J4 006 03 00 T84 006 04 00 600-1146-2 006 05 00 0-SVOC 006 06 00 006 07 00 006 08 00 006 01 01 006 02 01 J5 006 03 01 T85 006 04 01 600-1146-2 006 05 01 0-SVOC 006 06 01 006 07 01 _
006 08 01 006 01 02 006 02 02 J6 006 03 02 -
s T86 006 04 02 -'.) .
600-1146-2 006 05 02 0-5VOC 006 .06 02 006 07 02 006 08 02 006 01 03 006 02 03 J7 006 03 03 TB7 006 04 03 600-1146-3 006 05 03 0-10VOC 006 06 03 006 07 03 ,
006 08 03 L
Performed By Date Reviewed By Date I.414-38 4
Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 6 (H4CDAR6) (Continued) .
AS FOUNO DATA AS LEFT DATA ER fi Sk (#333) (#CCC) (#333) (#CCC)
' 205 805 205 805 006 01 04 006 02 04 J8 006 03 04 TB8 006 04 04 600-1146-4 006 05 04 110VOC 006 06 04 006 07 04 006 08 04
(
Perfor1ned By Date Reviewed By Date
- -- I.414-39 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 6 (H4C0AR6) (Continued) y[g g & LED CHANGED STATE (a) 006 13 00 "
01 006 13 00 02 006 13 00 D3 J10 006 13 00 D4 T810 006 13 00 05 600-1179-1 006 13 00 06 Of DRY 006 13 00 07 CONTACT 006 13 00 08 006 14 00 01 006 14 00 02 006 14 00 03 006 14 00 D4 006 14 00 05 006 14 00 06 006 14 00 07 !
006 14 00 08 .
006 13 01 01 006 13 01 02 006 13 01 03 e J11 006 13 01 04 -
TB11 006 13 01 05 - -
600-1179-1 006 13 - 01 06 DI DRY 006 13 01 07 CONTACT - 006 13 01 08 006 14 01 D1 006 14 01 02 006 14 01 03 006 14 01 04 006 14 01 DS 006 14 01 06 006 14 01 07 006 14 01 08 Performed By Date Reviewed By Date I.414-40 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 7 (H4CDAR7)
llE!! f.L AL (#333) (#ccc) (#333) (sccc) 205 805 205 805 007 01 00 007 02 00 J4 007 03 00 TB4 007 04 00 600-1146-2 007 05 00 0-SVOC 007 06 00 007 07 00 007 08 00 007 01 01 007 02 01 JS 007 03 01 TBS 007 04 01 600-1146-2 007 05 01 0-SVOC 007 06 01 -
007 07 01
~
007 08 01 007 01 03 007 02 03 ) .
-4 J7 007 03 03 T87 007 04 03 600-1146-2 007 05 03 0-5VOC 007 06 03 007 07 03 l
007 08 03 Performed By Date Reviewed By Date I.414-42 Attachment 1
ENCLOSURE 7.4 (Continued) f DATA SHEET UFN 6 (H4COAR6) (Continued)
VfB Ek Sk LEO CHANGED STATE (t) 006 13 02 01 006 13 02 D2 006 13 02 03 J12 006 13 02 D4 T812 006 13 02 DS 600-1179-1 006 13 02 D6 01 ORY 006 13 02 07 CONTACT 006 13 02 08 006 14 02 01 006 14 02 D2 006 14 02 03 006 14 02 04 006 14 02 DS 006 14 02 06 006 14 02 07 006 14 02 08 -
006 13 03 D1 006 13 03 02 006 13 03 03
'( J13 006 13 03 04
~
T813 006 13 03 05 600-1179-6 006 13 03 06 DI 140VOC 006 13 03 07 OR 115VAC 006 13 03 08 006 14 03 01 006 14 03 02 006 14 03 03 l 006 14 03 04 006 14 03 05 006 14 03 06 006 14 03 07 006 14 03 08 Performed By Date Reviewed By Date
( I.414-41 l
l l
Attachment 1-
6 ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 7 (H4CDAR7) (Continued)
ER f.L SL LED CHANGED STATE (a) 007 13 09 '
01 007 13 09 02 007 13 09 03 J9 007 13 09 04 189 007 13 09 05 600-1179-1 007 13 09 06 DI DRY 007 13 09 07 CONTACT 007 13 09 08 -
007 14 09 01 007 14 09 02 007 14 09 03 007 14 09 04 007 14 09 05 007 14 09 06 007 14 09 07 007 14 09 ,
08 007 13 00 01 007 13 00 02 007 13 00 03
, J10 007 13 00 04 T810 007 13 00 05 -
600-1179-1 007 13 00 06 DI DRY 007 13 00 07 CONTACT 007 13 00 08 007 14 00 01
- 007 14 00 02 007 14 00 03 007 14 00 04 007 14 00 05 007 14 00 06 007 14 00 07 007 14 00 08 Performed By Date Reviewed By Date I.414-43 I
i
! Attachment 1
- ENCLOSURF 7.4 (Continued) 0ATA SHEET UFM 7 (H4C0AR7) (Continued)
Ef.E f.k 9.L LED CHANGED STATE (2) 007 13 01 01 007 13 01 02 007 13 01 03 J11 007 13 01 D4 T811 007 13 01 DS 600-1179-1 007 13 01 06 O! ORY 007 13 01 07 CONTACT 007 13 01 08 007 14 01 Ol' 007 14 01 D2 _
007 14 01 D3 007 14 01 04 007 14 01 05
, 007 14 01 06 007 14 01 07 -
007 14 01 D8 007 13 02 D'1 007 13 02 D2 '
007 13 02 03 -
J12 007 13 02 04 T812 007 13 02 05 600-1179-6 007 13 02 06 1 DI 140VDC 007 13 02 07 '
i OR 11SVAC 007 13 02 08 007 14 02 01 007 14 02 02 i 007 14 02 03 007 14 02 04 007 14 02 05
. 007 14 02 06
} 007 14 02 07 007 14 02 08 Performed By Date Reviewed By Date l
i i
I.414-44 Attachment 1
ENCLOSURE 7.4 (Continued) f DATA SHEET UFM 7 (H4C0AR7)- (Continued)
UFM & GL LED CHANGED STATE (a) 007 13 03 01 007 13 03 02 007 13 03 D3 J13 007 13 03 04 TB13 007 13 03 05 600-1179-6 007 13 03 D6 OI 140VOC 007 13 03 07 OR 115VAC 007 13 03 08 ,
007 14 03 01 007 14 03 02 007 14 03 03 007 14 03 04 007 14 03 05 007 14 03 D6 007 14 03 07 .
007 14 03 08 007 13 04 D1
. 007 13 04 02 007 13 04 03 -
J14 007 13 04 04 T814 007 13 04 05 600-1179-6 007 13 04 06 O! 140VOC 107 13 04 07 OR 115VAC 007 13 04 08 J07 14 04 01 007 14 04 02 007 14 04 03 0 17 14 04 04 0.17 14 04 05 007 14 04 06 007 14 04 07 007 14 04 08 Performed By Date Reviewed By Date g I.414-45 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 7 (H4C0AR7) (Continued)
Mf3 [L GL LEO CHANGED STATE (a) 007 13 05 01 007 13 05 02 007 13 05 03 J15 007 13 05 04 T815 007 13 05 05 600-1179-1 007 13 05 06 DI DRY 007 13 05 07 CONTACT 007 13 05 08 007 14 05 01 007 14 05 02 007 14 05 03 3
007 14 05 04 007 14 05 05 007 14 05 06 007 14 05 07 -
007 14 05 08 007 13 06 01 007 13 06 D2 w
- J16 007 007 13 13 06 06 03 04
-)-
T816 007 13 06 05 600-1179-6 007 13 06 06 DI 140VOC 007 13 06 D7 OR 115VAC 007 13 06 08 007 14 06 01 007 14 06 D2 007 14 06 03 007 14 06 04 007 14 06 05 007 14 06 06 007 14 06 07 007 14 06 08 Date
- Performed By Reviewed By Date J
!.414-46 i
Attachment 1
ENCLOSURE 7.4 (Continued)
,- DATA SHEET UFM 7 (H4C0AR7) (Continued) gfj, & E LEO CHANGED STATE (t) .
007 13 07 01 007 13 07 02 007 13 07 03 J19 007 13 07 04 TB19 007 13 07 05 600-1179-6 007 13 07 06 OI 140V0C 007 1};'6 07 07 OR 115VAC 007 13 07 08 007 14 07 01 007 14 07 02 007 14 07 03 007 14 07 04 007 14 07 05 007 14 07 06 007 14 07 07 -
007 14 07 08 007 13 08 01 C'.'~
~
007 13 08 03 .
J20 007 13 08 04 T820 007 13 08 05 600-1179-1 007 13 08 06 O! DRY 007 13 08 07 CONTRACT 007 13 08 08 007 14 08 01 007 14 08 02 007 14 08 03 007 14 08 04 007 14 08 05 007 14 08 06 007 14 08 07 007 14 08 08 Performed By Date Reviewed By Date
< s I.414-47 Attachment 1
ENCLOSURE 7.4 (Continued) 0ATA SHEET UFM 8 (H4C0AA8)
AS FOUNO DATA AS LEFT DATA gg & E (#333) (#CCC) (#333) (#CCC) 20M 80M 20M 805 008 01 00 008 02 00 J4 000 03 00 i
T84 008 04 00 600-1146-2 008 05 00 0-5VOC 008 06 00 008 07 00 _,
008 08 00 t
UFN & E LED CHANGE 0 STATE l, (2) 1 008 13 00 01 000 13 00 02 008 13 00 03 ,
J10 008 13 00 04 T810 008 13 00 05 600-1179-1 008 13 00 06
. O! ORY 008 13 00 07 CONTRACT 008 13 00 08 008 14 00 01 '
-)-
008 14 00 02 008 14 00 03
! 008 14 00 04 008 14 00 05
' 008 14 00 06 008 14 00 07 008 14 00 08 i
I i Performed By Date Reviewed By Date l
]
l I.414-48
)
Attachment I
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 8 (H4C0AR8) (Continued) 913, & E LE0 CHANGED STATE (s) 008 13 03 01 008 13 03 02 008 13 03 03 J13 008 13 03 04 T813 008 13 03 05 600-1179-1 008 ,13 03 06 DI DRY 008 13 03 07 CONTRACT 008 13 03 08 008 14 03 01 008 14 03 02 008 14 03 03 008 14 03 04 008 14 03 05 008 14 03 06 008 14 03 07 .
008 14 03 08 008 13 04 01 008 13 04 02 -
s 008 13 04 04 03 04
' ') -
J14 008 13 T814 008 13 04 05 600-1179-1 008 13 04 06 O! DRY 008 13 04 07 CONTRACT 008 13 04 08 008 14 04 01 008 14 04 02 008 14 04 03 008 14 04 04 008 14 04 05 008 14 04 06
! 008 14 04 07 008 14 04 08 j Performed By Date _
Reviewed By Date
!.414-50 i
i Attachment 1
ENCLOSUSE 7.4 (Continued)
DATA SHEET UFM 8 (H4CDARG) (Continued)
Eg & g LEO CHANGED STATE (a) 008 13 01 01 008 13 01 02 000 13 01 03 JII 008 13 01 04 T811 000 13 01 05 600-1179-1 008 13 01 06 O! DRY 008 13 01 07 CONTRACT 008 13 01 08 008 14 01 01 -
008 14 01 02 008 14 01 03 008 14 01 04 000 14 01 05 008 14 01 06 07
(
~
008 14 01 .
008 14 01 08 008 13 02 01 008 13 02 02
(, 008 13 02 03 .
J12 008 13 02 04 TS12 008 13 02 05 600-1179-1 008 13 02 06 O! DRY 008 13 02 07 CONTRACT 008 13 02 08 008 14 02 01 008 14 02 02 008 14 02 03 008 14 02 04 008 14 02 05 008 14 02 06 008 14 02 07 008 14 02 08 Performed By Date Reviewed By Date
- s. I.414-49 1
Attachment 1
]
l ENCLOSURE 7.4 (Continued) i I
7 DATA SHEET UFM 8 (H4C0AR8) (Continued) yf3 & E LED CHANGE 0 STATE (1) 008 13 05 --
01 008 13 05 02 008 13 05 03 JIS 008 13 05 04 T815 008 13 05 05
.600-1179-1 000 13 05 06 O! DRY 000 13 05 07 CONTRACT 008 13 05 08 008 14 05 01 008 14 05 02 000 14 05 03 008 14 05 04 008. 14 05 05 008 14 05 06 008 14 05 07
- 008 14 05 08 008 13 06 01 008 13 06 02
(. '
008 13 06 03 .
. J16 008 13 06 04 T816 008 13 06 05 600-1179-1 008 13 06 06 DI DRY 008 13 06 07 CONTRACT 008 13 06 08 008 14 06 01 008 14 06 02 008 14 06 03 008 14 06 04
- 008 14 06 05 008 14 06 06 008 14 06 07 008 14 06 08 Performed 8y Date Reviewed By Date l
A I.414-51 i
Attachment 1
ENCLOSURE 7.4 (Continued)
DATA $NEET UFM 8 (H4COARS) (Continued)
Vf.R & gL LEO CHANGED S* H
~
008 13 07 01 008 13 07 02 008 13 07 03 J17 008 13 07 04 Tel? 008 13 07 05 600-1179-1 008 13 07 06 O! ORY 008 13 07 07 ~
CONTRACT 000 13 07 08 008 14 07 01 000 14 07 02 008 14 07 03 008 14 07 04 008 14 07 05 000 14 07 06 008 14 07 07 07 08 f
008 14 L_
008 13 09 0'1 008 13 09 02 ' ~
008 13 09 03 '
J18 008 13 09 04 TB18 008 13 09 05 -
600-1179-1 008 13 09 06 O! ORY 008 13 09 07 CONTRACT 008 13 09 08 008 14 09 01 008 14 09 02 008 14 09 03 008 14 09 04 008 14 09 05 008 14 09 06 008 14 09 07 008 14 09 08 Performed By Date Reviewed By Date I.414-52 Attachment 1
ENCLOSURE 7.4 (Continued)
,. DATA SHEET UFM 8 (H4C0AR8) (Continued)
Et fl EL LED CHANGED STATE (a) 008 13 08 01 008 13 08 02 008 13 08 03 J20 008 13 08 04 T820 008 13 08 05 600-1179-6 008 13 08 06 OI 140VOC 008 13 08 07 OR 115VAC 008 13 08 08 008 14 08 01 008 14 08 02 008 14 08 03 008 14 08 04 i 008 14 08 05 008 14 08 06 008 14 08 07 008 14 08 08
.q.
Performed By Date l
Reviewed By Date i
1 1
I l
s !.414-53 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 9 (H4CDAR9)
AS FOUNO DATA AS LEFT OATA Mf.R f.L fik (#333) (#CCC) (#333) (#CCC) 20% 80% 20% 80%
003 01 00 009 02 00 J4 009 03 00 T84 009 04 00 600-1146-2 009 05 00 0-SVOC 009 06 00 009 07 00 009 08 00 009 01 01 009 02 01 J5 009 03 01 T85 009 04 01 600-1146-2 009 05 01 {
0-SVOC 009 06 01 009 07 01 009 08 01 -_
J7 009 009 009 01 02 03 03 03 03
- )-
T87 009 04 03 _
600-1146-2 009 05 03 0-SVOC 009 06 03 009 07 03 009 08 03 Performed By Date Reviewed By Date I.414-54 Attachment 1
ENCLOSURE 7.4 (Continued)~
, DATA SHEET UFM 9 (H4CDAR9) g[FM [1 SL LED CHANGED STATE
. (a) 009 13 09 01 009 13 09 D2 009 13 09 03 J9 009 13 09 D4 TB9 009 13 09 05 600-1179-1 009 13 09 06 DI DRY 009 13 09 07 CONTACT 009 13 09 08 009 14 09 D1 l 009 14 09 02 009 14 09 03 009 14 09 04 009 14 09 05 009 14 09 06 009 14 09 07 009 14 09 08 .
Y 009 13 00 D1
' 009 13 00 02 t' ' ' 009 13 00 03
~ 's J10 009 13 00 04 .
TBIO 009 13 00 05 600-1179-1 009 13 00 06 DI DRY 009 13 00 07 CONTACT 009 13 00 08 009 14 00 01 009 14 00 02 009 14 00 03 009 14 00 04 009 14 00 05 009 14 00 06 009 14 00 07 009 14 00 08 Performed By Date Reviewed By Date I.414-55 Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 9 (H4C0AR9)
Mf3 f,( gi LEO CHANGED STATE
(*) ,
009 13 01 ~
01 009 13 01 02 009 13 01 03 J11 009 13 01 04
, T811 009 13 01 05 600-1179-1 009 13 01 06 O! ORY 009 13 01 07 CONTACT 009 13 01 08 009 14 01 01 009 14 01 02 009 14 01 03 009 14 01 04 009 14 01 05 009 14 01 06 009 14 01 07 009 14 01 08 -
009 13 02 01 009 13 02 02 009 13 02 03 ^
J12 T812 009 009 13 13 02 02 04 05
~) -
600-1179-6 009 13 02 06 DI 140VOC 009 13 02 07 OR 11SVAC 009 13 02 08 009 14 02 01 009 14 02 02 009 14 02 03 009 14 02 04 009 14 02 05 009 14 02 06 009 14 02 07 009 14 02 08 Performed By Date Reviewed By Date 1.414-56 Attachment 1
na ENCLOSURE 7.4 (Continued)
,.. DATA SHEET UFM 9 (H4C0AR9) gg & R LEO CHANGE 0 STATE (s) 009 13 03 01 009 13 03 -
02 009 13 03 03 J13 009 13 03 04 T813 009 13 03 05 600-1179-6 009 13 03 06 O! 140VOC 009 13 03 07
. OR 115VAC 009 13 03 08 009 14 03 01 009 14 03 02 009 14 03 03 009 14 03 04 009 14 03 05 009 14 03 06 009 14 03 07 009 14 03 08 009 13 04 01 009 13 04 02 -
7 009 13 04 03 6
J14 009 13 04 04 T814 009 13 04 05 600-1179-6 009 13 04 06 O! 140VOC 009 13 04 07 OR 115VAC 009 13 04 08 009 14 04 01 009 14 04 02 009 14 04 03 009 14 04 04 009 14 04 05 009 14 04 06 009 14 04 07 009 14 04 08 l
Performed By Date Reviewed By Date l
~( !.414-57 i Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 9 (H4C0AR9)
ER EL EL LED CHANGEO STATE (1) 009 13 05 _
01 009 13 05 02 009 13 05 03 JIS 009 13 05 04 T815 009 13 05 05 600-1179-1 009 13 05 06 O! ORY 009 13 05 07 CONTACT 009 13 05 08 009 14 05 01 009 14 05 02 009 14 05 03 009 14 05 04 009 14 05 05 009 14 05 06 009 14 05 07 009 14 05 08 .
i 009 13 06 01 009 13 06 02 009 13 06 03 *s' JI6 009 13 06 04
T816 009 13 06 05 600-1179-6 009 13 06 06 O! 140VOC 009 13 06 07 OR 115VAC 009 13 06 08 009 14 06 01 009 14 06 02 009 14 06 03 009 14 06 04 009 14 06 05 039 14 06 06 009 14 06 07 009 14 06 08 Performed By Date Reviewed By Date
!.414-58 Attachment 1
ENCt.0508E 7.4 (Continued)
OATA SHEET UFM 9 (H4C0A89) f EE f.L AL LED CHANGED STATE (a) i 009 13 07 01
- 009 13 07 -
02 009 13 07 03 J19 009 13 07 04 T819 009 13 07 05 600-1179-6 009 13 07 04 O! 140VOC 009 13 07 07 08 115VAC 009 13 07 08 009 14 07 01 009 14 07 02 009 14 07 03 009 14 07 04 009 14 07 05 -
009 14 07 06 009 14 07 07 009 14 07 08 009 13 08 01 009 13 08 02
- 009 13 08 03
(' -
J20 009 13 08 04 ,
T820 009 13 08 05 600-1179-1 009 13 08 06 O! ORY 009 13 08 07 CONTACT 009 13 08 08 ,
009 14 08 01 009 14 08 02 009 14 08 03 009 14 08 04 009 14 08 05 009 14 08 06 009 14 08 07
\ 009 14 08 08 Performed 8y Date
)
Reviewed By Date l
~
f.414-59 s.
4 .
Attachment 1
ENCLOSURE 7.4 (Continued)
DATA SNEET UFN 10 (H4CDAR10)
AS FOUNO DATA AS LEFT DATA E EL ik (#333) 20M
(#CCC) 80%
(#333) 205
(#CCC) 805 010 01 00 010 02 00 J4 010 03 00 T84 010 04 00 600-1146-2 010 05 00 0-5VOC 010 06 , 00 010 07 00 010 08 00 i
E Ek 9.k LEO CHANGE 0 STATE (a) 010 13 11 01 i
010 13 11 02 010 13 11 03 .
J9 010 13 11 04 T89 010 13 11 05 600-1179-1 010 13 11 06
~
O! DRY 010 13 11 07 ' ~
CONTACT 010 13 11 08 010 14 11 01 010 14 11 02 010 14 11 03 ,
010 14 11 04 010 14 11 05 010 14 11 06 010 14 11 07 010 14 11 08 Performed By Date Reviewed 8y Date
!.414 60 Attachment 1
r , ,
ENCLOSURE 7.4 (Continued)
,_ DATA SHEET UFM 10 (M4CBAR10)
EB f.L SL LEO CHANGED STATE (t) 010 13 00 01 010 13 00 D2 010 13 00 D3 JIO 010 13 00 D4 T810 010 13 00 05 600-1179-1 010 13 00 06 O! ORY 010 13 00 07 CONTACT 010 13 00 08 010 14 00 01 010 14 00 02 010 14 00 03 010 14 00 04 010 14 00 D5 010 14 00 06 010 14 00 07 010 14 00 08 010 13 01 D1 010 13 01 02 i '
010 13 01 D3 -
^
J11 010 13 01 04 T611 010 13 01 D5 600-1179-1 010 13 01 06 DI DRY 010 13 01 07 CONTACT 010 13 01 08 010 14 01 01 010 14 01 02 010 14 01 03 010 14 01 D4 010 14 01 05 010 14 01 06 010 14 01 D' i 010 14 01 08 j Performed 8y Date
! Reviewed By Date
}
\- I.414-61 f
i i
1-
! Attachment 1
_ ~ _
ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 10 (H4CDAR10)
E!! f.( g( LED CHANGED STATE (1) 010 13 02 01 010 13 02 02 010 13 02 03 J12 010 13 02 04 T812 010 13 02 05 600-1179-1 010 13 02 06 DI ORY 010 13 02 07 CONTACT 010 13 02 08 010 14 02 01 010 14 02 02 010 14 02 03 010 14 02 04 010 14 02 05 010 14 02 06 010 14 02 07 .
1 010 14 02 08 010 13 03 01 010 13 03 02 w 010 13 03 03 'j-J13 010 13 03 04 T813 010 13 03 05 600-1179-1 010 13 03 06 Of DRY 010 13 03 07 CONTACT 010 13 03 08 010 14 03 01 ,
010 14 03 02 010 14 03 03 010 14 03 04 010 14 03 05 010 14 03 06 010 14 03 07 010 14 03 08 Performed By Date Reviewed By Date ;
l l
I.414-62 Attachment 1
ENCLOSURE 7.4 (Contirued) 7- DATA SHEET UFM 10 (H4C0AA10)
EE EL SL LEO CHANGED STATE (a) 010 13 04 01 010 13 04 02 010 13 04 03 J14 010 13 04 04 T814 010 13 04 05
, 600-1179-1 010 13 04 D6 DI DRY 010 13 04 07 CONTACT 010 13 04 08 010 14 . 04 D1 010 14 04 02 010 14 04 03 010 14 04 04 010 14 04 DS 010 14 04 06 010 14 04 07 ~
010 14 04 08 1
010 13 05 -
01 <
(- '
010 010 13 13 05 05 02 03
(,~ .
J15 010 13 05 04 --
. T815 010 13 05 D5 600-1179-1 010 13 05 06 OI ORY 010 13 05 07 CONTACT 010 13 05 08 010 14- 05 01 010 14 05 02 010 14 05 03 010 14 05 04 010 14 05 05 010 14 05 06 010 14 05 07 010 14 05 08 Performed 8y Date 4
Reviewed 8y Date i
t I.414-63 Attachment 1
i ENCLOSURE 7.4 (Continuea)
DATA SHEET UFM 10 (H4CDAR10) ,
UFM 'E g LED CHANGED STATE (t) 010 13 07 01 010 13 07 02 010 13 07 03 J16 010 13 07 04 T816 010 13 07 05 600-1179-1 010 13 07 06 OI DRY 010 13 07 07 CONTACT 010 13 07 08 010 14 07 01 010 14 07 02 010 14 07 03 010 14 07 04 010 14 07 05 010 14 07 06 010 14 07 07 4 010 14 07 08 010 13 08 Di 010 13 08 02 ~;),
010 13 08 03 .. s J17 010 13 08 04 T817
- 010 13 08 05 600-1179-1 010 13 08 06 OI DRY 010 13 08 07 CONTACT 010 13 08 08 010 14 08 01 010 14 08 02 010 14 08 03 010 14 08 04 010 14 08 05 010 14 08 06 010 14 08 07 010 14 08 08 1
Performed By Date Reviewed By Date .
I.414-64 Attachment 1
ENCLOSURE 7.4 (Continued)
, DATA SHEET UFM 10 (H4CDAR10)
Uf_4 & SL LED CHANGED STATE (a) 010 13 09 01 010 13 09 D2 010 13 09 D3 J18 010 13 09 04 TB18 010 13 09 DS 600-1179-1 010 13 09 D6 i
DI DRY 010 13 09 D7 CONTACT 010 13 09 08 010 14 09 01 010 14 09 02 010 14 09 03 010 14 09 04 010 14 09 DS 010 14 09 06 010 14 09 07 010 14 09 08 010 13 10 01 010 13 10 02
~
010 13 10 03 l J19 010 13 10 04 T819 010 13 10 05 600-1179-1 010 13 10 06 DI DRY 010 13 10 07 CONTACT 010 13 10 08 010 14 10 01 010 14 10 02 010 14 10 D3 010 14 10 04 010 14 10 05 010 14 10 06 010 14 10 07 010 14 10 08 Performed By Date Reviewed By, Date l
\_. I.414-65 i
Attachment 1'
' ENCLOSURE 7.4 (Continued)
DATA SHEET UFM 10 (H4CDAR10) l MfB f.L Sk LED CHANGED STATE (z) 010 13 .06 D1 01 0 13 06 D2 010 13 '06 D3 J20 010 13 06 D4 T820 010 13 06 05 600-1179-6 010 13' 06 06 DI 140VDC 01 0 13 06 07 OR 115VAC 010 13 06 08 010 14 06 D1 010 14 06 02 010 14 06 D3 010 14- 06 D4 010 14 06 05 010 14 06 06 ,
010 14 06 D7 010 14 06 D8 J
Performed By Date Reviewed BY Date f
I.414-66 Attachment 1
ENCLOSURE 7.5 TEST EQUIPMENT USAGE LOG SERIAL CALIBRATION TEST EQUIPMENT NUM8ER DUE DATE REMARKS
~
l l
l l
ENO I.414-67
( ;
1 Attachment 1
- .E:vvh nov.3
. 5-IC-02 I-Cll GEUERAL CALIBRATIOU PROCEDURE 1.0 PURPOSE
.1 To calibrace, functionally check and/or test plant instrument anc. control devices.
.2 To document the calibraton, checks and tests of plant instruments and control devices. .
2.0 REFERENCES
~
.1 Piping and Instrument Drawings (P&ID's)
.2 Electrical Elementary Drawings (E-200 series)
~
.3 Electrical Wiring Diagrams (E-300 series)
{ .
.4 Vendor Drawings
.5 Vendor Manuals
.6 Maintenance Procedures (I procedures) l
.7 Surveillance Procedures (SP's)
.8 Cuality Control Instruction (CCI)
)
.9 Administrative Procedures (AP's)
.10 Radiological Control Manual
.11 Test Equipment Manuals
.12 Process Standards
.13 Technical Specifications (Tech Specs)
.14 Instrument Calibration Records I
l I
- -011-1 Rev. 3 Attachment 2
J .s. m . m. A 0,o.c- j 2. .,.Le w. .6, A r-.- -.n J .- A. 7 mvn. ,. e a
.1 Consicer personnel safety requirements from all shocn hc:crcs.
Consicer personnel sareci requirements : rom :luic, .iy;rtulic cac pneuuatic systeus.
.3 Consider-the effects of all signcis en other giant systama, controls, indicatorc, harcuare anc intericcus.
.4 Determine if a System clearance is recuirec. ,
.5 Determine if c Raciation Ucrk ?er:.it is requiret.
4.0 SPECIAL TOOLS /EQUIPME"O
.1 Hone. .
5.0 TESTING /iCCEPTAUCE CRITERIA
]
.1 The instrument or control device is calibra:ec to he i~
tolerance required by Process stancarcs, Tech Specs or manufacturers instruction (as applicable).
.2 There has been a functional check of ti e inctruuen: by input-output verificaton to the uiring plane or the receiving instrument, or-there has been a functional :ect frcc the wiring plane to the instrument depencing on its cpplicacion.
6.0 PROCEDURE
.1 For Hewly Installec Instruments
.1 For each new instrument fill out an instrument data sheet (Encl. 7.2) filling in ecch block wich the appropricte information. .
.a Instrument Mumber - assignec by ILC/ Generation Engineering Cognizant Engineer via ECU/ECF pcckage.
.b Descriptor - short cescription cf instrument function
.c System - 3 lett :r sys e::. design:cion (see AP.3)
I-Oll-2 Rev. 3 Attachment 2
TL ,
G.0 PROCEDURE (Continued)
.1.1 -
.6 Location - Building ( Aux, Turb. , etc. ) , level, and any
-other information which would help to locate the instrument
.e CA Class - assigned by I&C/ Generation Engineering
~ Cognizant Engineer via ECU/DCU package.
.f P.H. Task Ho. - assigned cy ILC Clerk or HIPS Co-ordinator
.g Recal Interval - assigned by f oreman
.h Manufacturer - company which actually manufactures-item
.i Model Mo. .
.j Serial No.
.k System Vendor - distributor ithe iten is purchased f rom
-(.. .1 References - DCU package generated by I&C or Generation
~
Engineering should include applicable P&ID, Elementary, -.~
Vendor Dwg's, Wiring Diagrams. Venoor Technical Manuals
- are processed through the-SDC library via the I&C Engineer.
.m Function - this information can be gleaned from P&ID's, Elementaries, wiring diagrams, etc.
.n Operation and Calibration - Input Range, Output Range ,
Indicator Range, Type of Element, Voltage Rating and Current Rating are obtained from the manufacturer's informaton. Setpoints and their tolerances are found in ;
Process Standards or octained f rom the ILC Engineer / Generation Engineering Cognizant Engineer if not in Process Standards.
Instrument tolerances are based upon the manu'facturer's tolerance if listed in the technical manual. If tolerances are not listed in the technical manual, the
-following guidelines apply:
.1 CA Class 1 anc 2 electrcnic and pneumatic tolerance is 12% of manimum range.
I-Gil-3 Rav. 3 Attachment 2
, - __ - .=
6.0 PROC DCP.E (Continuec)
.1.1.n
.2 CA Class 3 electronic tolerance is 13; of ..;cninu;.
range.
.3 ' GA Class 3 pneun.acic :olerance is 254 maninum ranga.
.o Adcicional Information and P.euarus.- list cni acGitienci
.information which. night be helpful in locccing, calibrating or preventing dancge no the ins:rumen:.
.2 Calibrate the instrument in accordance ulch Secnict J.2 of this.procecure.
.2 Instrument Calibration Procedure .
.1 General. Guidelines
.1 cA calibration i definec as Ehe nuiustrer.: of instrument. '
characteristics to conforc' to a standard. A calibracion '
check'is the cornarison of instrument output versus a' ;-
standard.
.2 A calibration is requireo for initial setup of an instrument, change in required characteristic.or as the result of an unsatisfactory calibrction check.
.3 A calibration check is required f or periodic preventive maintenance, to verify operation of a suspec: instrument and to verify satisfcctory completicn of c caliorc ica.
.4 A calibration ano/or calibration check shoulc be performed utilizing appliccble Instrumenc Procedures, Surveillance Procedures or manufacturers prccecures.
.5 Uhere a procedure or other guidelines cre'not cvailacle, a calibr tion shall consist of applying the relevant i.
signal at the instrument input and adjusting zerc, range and linearity (where applicable) to obtain the required output.
.6 A calibration check will generally consist or apply in.,.
an input signal at five points (ie., 0, 25, 50, 75 nc 100% of span) in both the increasing cnc decreasing directions anc coopering the Occual output against the I-011-4 Rev. 3 Attachment 2
'(,
r" 3.0 ?"OCCDURS - (Continued),
.2.1
'requirec output for the'given input signal.
.7 As Found Data shall be recorded for the As Founc condition-during an instrument calibration chcch.
.3 As Left Data shall be.recorcec fcr'any calibration check performeo after.au)Latment or calibration of an instrument.
.9 Attempt to perform'end-to-end calibration checks of entire instrument loops .(sensor through final element) when practical. Utilite loop calibration forms (maintained by I&C Foreman) in recording data where applicable.
.10 When a end-to-enc loop calibration check cannot be perf ormed, check (and calibrate as necessary) the sensor / transmitter. Record the signal at the input of the next in-line unit f or the 5 calibration check points
. of the sensor / transducer. The sensor / transmitter. signal can now'be simulated in the loop utilizing the recorcec values anc a check of the other in-line units completec.
A final check shoulc he mace to verify that: the signal path is continuous by comparing the actual value of the
~ (, ~
process variable anc the final element position or incication.
.11 Upon completion.of the calibration anc/or calibration check, record the test equipment CO2 number an6 recal
' cue date, As Found/As Left values, serpoint/ reset point
-data ano applicable work request or Pil task number s on the Calibration Record Data Sheet (See Cncl. 7.2) located in the ILC. Shop.
.12 Affix a red calibration sticker for QA Class 1 or Llue calibration sticker for GA Class II to the instruments;)
~
which has been successfully calibrated anc/cr '
calibration checked, filling in the applicable instrument number, date calibrated, recal cue 6 ate an6 initials of the individuals calibracing the instrument.
.13 Select test equipment to ensure cross-contamination of systems does not occur, i.e., use gauges cesignacec for oil use on oil filled systems only, racioactive contaminated or potentially contaminatec test equipment on radioactive systems, etc.
.14 It is desireable to maintain a minimum 4 cc 1 accurac; I-Cll-5 Rev. 3 Attachment 2
+ . >
0.w .....
c2.. w ......
. .. .:-('w v..a *A
. 4 . . , c, ,.. )
- .2.1 ,
ric:.o V..en possible ue:veen.ci.4 nau; eq.tijnen: ,n a:
useC &nL' :he CCl3rance requi.*Cu f ar the CCR)or.cn: Oding Calibratec. In no cCJcLshill "he COCur2C;* ul :h0 tee .
i, equipmenc.be less.chan the ct.erance requirac icr s&tisfLCtor/ Calibraciot..
.15 Tect ecuipment..should-be sele :ec vich run;.ac: : _. r o je r .
ranging. The tesc values shoult r .. ;.1 e : . u t. '. . : . .6-900 of test eculpment range, when ,,0c_ ;_e.
.16' Electronic test eCuipment fCOtors CC JS r0ne's2:2C jrior to selection are' input andtoutju; impsc;ncO, -rr:3b Od O;*
response, voltage anu cu r r on; r c.::.ne. , .E ar :C :..rju: Inc wnich ranges of.c given' instrument.are cal.crcecc (2cr
~ ~
. . instance, some OVU AC ranges =cy not be cellar:ccL).
.17 2nsure that all test ecuipment ucec is,in ecliar ::cn cs noted by-the~ rec "Recal Due" stickor dcts.
.3- Thermo-bulbLInstrument-Calibration / Check
.1 Determine if. the thermo-bulb- is installec in a uell. If 7 the bulbLis not installed in a well, ~ determine if the ').
~'
system can be drained (if liquid) or other. safe means exists for withdrawing the bulb from-the aonitored medium.
. 2- Immerse the thermo-bulb in a cenperature_bcch cc che same depth as when installed in the systen.
.3 Use a " calibrated" thermometer to monitor tenner;;ure in the bath and for comparison vich indication /ae icn of :he instrument-being calibrated.- Ensure che chermcaunar is imuersed up to the innersion line to avois.inciccrica error.
.4 Perform a calibration-check of the thermo-bulb inccrument -.
.by varying c..ne temperature of the bc:h over t.ne range or the. instrument ano comparing the instrument incicateu values against the'value indicated by thetchernouecer.
.5 Adjust temperature of the bath to the requirec values'for the adjustments to. be made in accordance with the vencors technical manual. Ensure that the bath tempercture is stabilized prior to making any adjustments.
.6 nepeat the calibration check as outlined in Step 6.4.4 il any adjustments-vere ande in Step 6.,.5.
I-Oll-6 nov. 3 .
Attachment 2
6.0 PROCEDURE '(Continued)
.3
.7 Return the thermo-bulb to its normally installed locacicn.
.4 Thermocouple Instrument Calibration / Check UOTE:
Since junction thermocouples have output characteristics which can be accurately predicted, immersion in a temperature bath is not required to accomplish the calibration / check. .
.1 Lif t the thermocouple leads at the instrument tw be checked / calibrated-and simulate the thermocouple signal by installing a . calibrated millivolt potentiometer cr: a millivolt source and _ calibratec DVII at the input or the 7y (J instrument.
.2 neasure the ambient temperature at the physical location where the test equipment is connecteo to tne recorcer or field wires with a calibrated thermometer and perform the required reference junction compensation.
.3 Perf orm a calibration check of the instrument by applying known millivolt. values corresponding to given temperatures (depencing on the thermocouple type and its characteristics) and compare those required temperature values against the instrument indicated values.
.4 Calibrate the instrument if required in accordance uich the '.
venoor technical manual utilizing the appropriate simulated temperature inputs.
.5 Repeat the calibration check outlined in step 6.4.. above if any adjustments were made in Step 6.4.4.
.6 nemove the test equipment installed in Step 6.4.1 anc re-install the thermocouple leads at the instrument input.
.7 Verify that the instrument indicates system temperature (if knoun).
I-011-7 nev. 3 Attachment 2
t' G.0 PROCCDURE (Continued)
.5 Resistance Temperature Detector (RTD) Instrumanc Calibration / Check "OTE Since RTD's have resistance vs temperature characteristics unich can be. accurately predicted, immersion in a temperature bath is not requirec to accomplish the calibration / check.
.1 - Verify RTD continuity by_ cisconnecting the lead wires . and measuring the resistance through the RTD (should not read open circuit) .
.2 Uith the RTD lead wires disconnected, simulate a temperature signal by installing a calibrated decade box at -]) .
the input of the instrumer.c taking int a consiceracion the configuration of the RTD ( 2,3 , or t.. uire).
.3 Perform a calibration check of the instrument loop ay applying known. resistances (decace box) corresponding to given temperatures (depending on the RTD type sad ics characteristics) and comparing those requirad temperature values against the-instrument incicated values.
.4 Calibrate the instrument loop components if requirec, in accordance with the vendor technical manual utilicing the appropriate simulated temperature inputs. .
.5 Repeat the calibration check outlined-in Sce; 6.5.3 above if any adjustments .were made in Step 6.5.4.
.6 Remove the decade box installed at the instrument input and re-connect the RTD lead wires.
.7 Verify that the instrument indicates actus1 system temperature (if knoun) .
I-Oll-8 Rev. 3 Attachment 2
-e 6.0 PROCEDURE _ .(Continue 6)
.6 pressure Instrument Calibration / Check
.1 Isolate the pressure transmitter by closing the instrument isolation valve just upstream of the transmitter on the sensing line.
'iOTE :
Care must be taken in the selection of test equipment to prevent contaminating Grade A primary systems with oil
- or non-D.I. unter.-
.2 Connect a variable pressure source at the sensor input via a test tee, where available, or by disconnectins the
,- sensing line and connecting directly to the censor. .
.3 tionitor the applied test pressure uith a_ test instrument of the appropriate range ano accuracy.
.4 Perform a calibration check of the transmitter' ana associated instrument loop by applying oiscrete test pressures ano comparing the requireo output for a given pressure against the actual output of the transmitter.
.5 Calibrate the transmitter or other instrument loop components if required,-in accordance with the vendor technical manual utilizing the appropriate test pressures.
.G Repeat the calibration check outlined in Step 6.6.4 acove, if any adjustments were perf ormed in Step 6.6.5.
.7 Remove the variable pressure source an6 any test ecuipment used.,
.8 Re-connect the transmitter sensing line or cap the test tee as applicable.
.9 Re-connect the transmitter to the cysten by opening the isolation valve closec in Step 6.6.1.
s
- -C11-0 Rev. 3 Attachment 2
. _ .- . - .=. - - - - - ._
1' G.0 PROCCDUnE: (Continu ec) -
.6 CAUTIO17; Consider. personnel.safecy hazards frcm hot or high pressure liquics uhen venting.
.10 Vent the transmitter - (in liq'uio systems) :o ensure no air is trapped in-the sencing line or donector incert.als.
.11 Uhere necessary backfill sensing lines uncre s:can'is normally condensed to fill the sensing lihe and the system is in cold shutdown, or long periods of_cima uculd. lapse before sensing line vould fill from condensation.
~
.7 Differential Pressure Instrument Calibration / Check 4
!!OTE : -
,/ -
The method of isolating a -
differential. pressure
-transmitter will depend upon sensing line configuration anc instrument application.
In general, do not apply a reverse diffe2:ential,.
allow a condition which r would. fill a dry leg or leave detector sensing linas un-isolated for extended periods of time ,
in high temperature systems.
.1 Isolate the differential pressure transmitter.
.2 Connect test equipment to produce a differential pressure at sensor inputs via test tees or disconnecting sensing lines ano connecting directly to transaicter sensing ports.
.3 Test equipment usec to produce the oifferentici pressure may be an actual differential pressure source connecteu to f
I-011-10 Rev. 3 Attachment 2
6.0 PROCEDUP.E (Continued)
.7 the transmitter high and lou pressure taps or a variable pressure source connected to the transmitter high pressure tap with the lou pressure tap vented to atmosphers.
.4 Monitor the applied test diff erential pressure t ich a test instrument of the appropriate range and accuracy.
.5 Perform a calibration check of the instrument loop by applying known cifferential pressures and comparing instrument desired outputs with actual outputs.
.6 Calibrate the transmitter ano other loop components, as necessary, in accordance with the ven6cr technical manual utilizing the appropriate test differential pressures.
.7 Repeat the calibration check outlined in Step 6.7.5 above if any adjustments were made in Step 6.7.6. .
MOTE
.I.w The method of returning a -
differential pressure transmitter to service will cepend upon the test equipment used to produce the test differential pressure, the sensing line configuration and instrument applicaticn.
.8 Uhile monico' ring the transmitter output for zero shift, cisconnect the test equipment used to jrccuce the tect. .
differential pressure and return the cifferential pressure -
transmitter to service.
.9 Vent the transmitter high and low pressure less (in liquid systeus) to ensure no air is trapped in sonoin s 1;ne= or transmitter internals.
.10 Backfill sensing lines where steam is normu.-; ccadensed to fill the sensing lines anc the systerc is in ccic shundcun or long periods of time would elapse vefore sensing lines uoulc fill from condensation.
l I-011-ll Rev. 3 Attachment 2
6.0 P20CCDURE (Contintec)
.8- Controller Cclibratica
-.1 If the' controller hcs only an on-Grf runction or suicch-type cction,.see Sectica 6.2.10.
.2 For contrcliers having prcportional (gcin: conurci Only, simulate the input and verify that the greper-input vs output relationship exists f or c five ..cin: che:k.
.3 For controllers.having aultiple feecback necnaninns (prop.,-
rate, reset, derivative, integral, etc.) consult the manufacturers manual for instructions. In many cases the
'aojustments can only be made uith the systa in opera:icn to provide "real" feedback. _
.9 Switch (Pressure, Temp, Level, etc.) - Calibration / Check
.1 Apply the ' required test signal at the input of the cuitch y J/ ~
(see Steps G.3 thru 6.0).
.2 Increase and decrease the test signal to cottin the actual setpoint(s) and reset point (s) .
.3 Compare the actual values-against required vclues to determine if a6justment is required.due to being cutsice allowable tolerances.
.4 If setpoint adjustment is requirec, set the simulatec input at the required setpoint value and adjust une cuitch mechanism until the suitch just trips.
.5 Repeat Steps 6.9.2 thru 6.9.4 until no further cdjustments are required,.
.6 If deadband adjustment is required, set the simulated input at the- required reset point value and adjust the zwi:ch deadband adjust until the suitch just resets.
.7 Repeat Steps 6.9.2, 6.9.3 and 6.9.6 until no further adjustments are necessary.
.3 necord As Founc/As Left values for Required Secpoint (High and/or Low), Actual Setpoint measureo increasing or decreasing, Reset Point ceasurec increasing or decrecsing,-
I-011-12 Rev. 3 i' Attachment 2
6.0 p;-:OCEDUES (Continuec)
.9.8 Leadband (difference between setpoint-and reset point) anc Error-(in measured units) of setpoint.
.9 Uhere applicable, check that tha cevice activated by the switch responds to changes in switch states.
.10 Remove test equipment and return the switch to service.
.10 Indicator Calibration / Check
.1 Simulate the required input to the incicator anc compare the indicated vs input values.
.2 Adjust the indicator as necessary to obtain the recuired tolerances.. Depending on the instrument adjustuents f cr -
zero, span and linearity may be available. .
' ( . 11 Recorder Calibration
~.. .-
NOTE:
When recorders have more than.one range of input, ensure each individual range is checked.
.1 Simulate the recorder input (s) at one channel or point anc compare the indicatec vs input values. .
.2 Adjust the recorder as necessary per the manufacturer's technical anual.
.3 Acjust any alarm setpoints anc functionally check by adjusting the simulated input to actuate the switch.
.4 Recorc on the recorder chart or strip what actions vero performed and the date and time returned to service.
~.
-011-13 Rev. 3 Attachment 2
A c
4 5.0 2nOC CURE (COntinuec):'
.12 Calibrction of I;iscellaneous Devices
.1 Consult the_ manufacturer's technical.tcnual for specific
?cclibration proceoures.
.2 'There no specific instructions are pecliced, simulc e che input anc compare the input vs output relationship tc the-desired, making ccjustcents cs required.
.3 Functionally check, peripheral.cevices where applicable.
l 7.0 2:1 CLOSURES
.1 Instrument Data Sheet .
.2 Calib' ration Record Data Sheet 1
9
/ -
t l
k 1
I-011-14 Rev. 3 Attachment 2
ENCLOSURE 7.1 !
INSTRLMENT DATA SHEET l lDENTIFICATION __
r., ,, % .
Descriptor Mfe. Inst. Ident. i System Loestion OA Class P. M. Task No. Paeol. Inta m i Manufseturer Medal No. Sarial No. System Vandor REFERENCES P&I D Data Sheet Elementary Wiring Diagrem Vendor Drawing Tech. Manual FUNCTION Computer Point Interlocks Recorder Point Annunciator Indicator loc.
OPERATION & CALIBRATION Input Range Set Points #1 Output Range #2 Indicator Penge "
- 3 Tolerance Voltage Piting Type of Element Currant Rating ADDITIONAL INFORMATION & REMARKS l
I-Oll-15 Rer 3 l
ENCLOSL*RE 7.2 CALI32ATIO': mErn=3 MTA curr-2n r:ru causana l {l n=
l 2n l l l ln=: l 3EL : m, I mis = l=Za P=a 10== = E= f * = ~l f F =='="l % %
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f l / I / l / l / l / l / l="- / /
bh=
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Femarks un nitocAurana y sc=3 un
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1/1/1/1/ / fi/la=1/l/
if fl/l/ /i/l/l="-I/l/i
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Pemarks suvo.osto 7/7s I-011-16 Rev. 3 Attachment 2
DW'ss Rev. 2 03/26/84 I-038 ROSEMOUNT MODEL 1153B, ll53D PRESSURE TRANSMITTER CALIBRATION / ROCHESTER INST. PANEL ANALOG ISOLATOR CALIBRATION 1.0 PURPOSE
.1 To calibrate Rosemount Model 1153B, QA Class 1, pressure transmitters located outside the Reactor Building.
.2 To calibrate Rosemount Model ll53D, QA Class 1 pressure transmitters located inside the Reactor Building.
.3 To calibrate *the electronic modules in Rochester Instrument cabihets H4SCA and H4SCB that are associated with 1.1 and 1,']
(,~ .4 To complete loop form calibration on NNI Loops associated with. .
1.1 and 1.2. ,
2.0 REFERENCES
.1 Rosemount Instrument Manual 4302 (Series B Transmitter, outside Rx building), SMUD No. M19.115-10
.2 Rosemount Instrument Manual 4388 (Series D Transmitter, inside Rx building), SMUD No. M19.115-TMol
.3 Rochester Instruments manual for the 4400 Nuclear lE Signal Isolator Cabinets H4SCA and H4SCB, SMUD No. M19.117-TM01
.4 Bailey Meter Company Instruction Manuals
.5 I-Oll, General Calibration Procedure 1
(
l I-038-1 Rev. 1 Attachment 3
. . _ _ . . . - - _ _ _ = _ _ . . _ _ _ _
4 4
4 2.0 2EFERE!!CES "(Cont.);
.6 ~AP.33, Calibration and Contrci of Inspection and Tec:
Equipment; _
.7 1115.07, Series Dravings (IllII Systen)
.8- I-053, Series Drawings (Instrument Loops)
.9 Ref. 2.1 in SP 200.14, Process Instrumentation Calibration
.10 T.P.3, I! ark nequest Procedure (Enclocure.G.G lis:: inctrunants-requiring Dual verification of valving follot::.nc main:enance or--calibration)
.11-ECli-packages A-280GA, A-2912, A-2936,.A-209 C , A-3G22A, J.-36 51
' ~
E,F,G,L. A-3652 and A-3781 .
4 1 .12 Ronan';1odel X85 DigitalzCalibrator Instructioni anu Operating .
,l
+ Ianual ,
1- , .13 Trancmation I;odel 1040 Digital Calibra or Inc:rua:icn :'anual 3.0 LII;ITATIOtiS/PRECAUTICITS .
f
.1 Portions of the follotnng procecure ".cy be performed Vich :he Reactor Plant in operation. Care mu t be e::ercised to chr.: an upset of the !!III/ICS Control Systeau uoes not occur.
.2- Transmitters calibrated using this proccuuru requirs ;ual verification per AP.3, Enclocure.G.S. Enclosura 7.3 .1:.sts :.11 transmitters covered by this procedure.and providec Euci
- Verification signoff space for-.cach transcicter.
r
.3 Transmitters covered by this Jcocedure eire qualified for
- 'uclear Class lE usage and were manuf acturec; co chu requirements of 10 CF2 Part 21. Any operaticas not specifically authorizec by the appliccole inctructicr. =caumi uay not be performed on the transmitters, t
I-030-2 nav. 1 ,
4 Attachment 3
. ~ . . _ , --
1
.3.0 LICITATIC:'S/?RECAUTICUS (Cont.)
.4 '.:henever aither caver of a transmic:Or - La c ci .vv s a , cha cover 0-ring .aust be replaced anc the cover :ortaet. ac specified in this procedure.-
.5 If.for some rencon the "OD CCCP compucer is coun causing the CRT consoles to be inoperative, the ou:suc of the multi;:le::ers can be read at he synceu disgnoscic anic in the bach oc une 1* Control noon. This value is 333 co FFF (::en) ccunts lar C-1000 (1-5VCC) input. For lhe purposa of chia prccedure, other than inicial checkout, ic is permissibla tc recort counts in lieu of the compucer point analog value.
1+ .6 The UP 3465E and the Fluke 8062A (handhelc) On::' c uay not be used to calibrate the 4-20mA Rosemount Tranunic: era, covered by this procedure. The HP 3465B has the requireu accuracy on -
the 20 aADC range but overranges at 19.999 aA preventing proper range adjustment of the transmi cer. The 200 mACC scale on both D3Hs and the 20cA scale on the fluke OGG2A are less accurace than the .04mA Tolerance of the accemount ~
i Transmitter. Calibration of the Rosemount Transmictors auct be perf ormed using tlue Ronan X85 or the Transmacion _1040 -
_ s.
Digital Calibrators, or other instruments having equivalenc
+ accuracys.
1+ .7--The Rosemount level transmitters on the condensate storage tank and on the core flood tanks have dry reference lags.
Caution must be exercised not to get uacer from the uot high side leg into the dry lou side leg of the transmitter uhen
- valving it into or out of service.
, 4.0 SPECIAL TOOLS / EQUIPMENT 1+ .1 Digital Cultimeter (CHM) HP3465B or equivalent, 2 required for Section 6.3 (not to be used co calibrate'Roscucun:
Transmitters or RIS El-4420 Signal Isolacors, Sec Liuitacienz
+ and Precautions section 3.6).
1+ .2 Digital Voltmeter (CVM) EP3460C or equivalent (kept in bach
+ of Control Room)
.3 Variable calibrated pressure source, Heise C:. or C::n :cct gauge with pressure pump or equivalent i <
I-038-3 Rev. 1 Attachment 3
4.0 SPECIAL - TOOLS / EQUIP!:El:T (Cont.)
.4 , Test Gauge, Ashcrof t Digigauge 7781 or aquivalent
.5 Variable potentiometer, Helipot codel T10-A (not calibrated) 1
.6 tierriam Liquid Line Trap
.7. ;iiscellaneous Hand Tools 1
.8 Torque Nrench (calibrated) , Proto 6064-5 or equivalent ulch special socket to fit transmitter covers.
.9 Pomona Test Leads 2744 or 3G 90 tiiniature Canana Plug Test -
Leads 1++ .10 Ronan !-lodel X85 Digital Calibrator, or equivalent ,
}~ ~ , ,.
t++ . .11 Transmation PPS Digital Calibrator, !!odel 1040, or equivalent 5.0 TESTI11G/ACCEPTAITCE CRITERIA
.1 !!odule and transmitter tolerances are listed.on the data sheat enclosures and on the loop forms for the particular instrument p loops. A complete set of in-tolerance data on the enclosures or the loop forms constitues an acceptable running of this procedure.
.2 Dual verification has been completed on those cransmittere calibrated unoer this procedure and Enclosure 7.3. completed as required.
.3 Transmitters calibrated under this procedure have had their cover 0-ring replaced and the covers torqued to 200 t 10 inch-lbs (applies only to covers that were removed) and Enclosure 7.3 has been completed as required.
I-038-4 nev. 1 Attachment 3
i G.0 PROCEDURE (Cont.)
The second type of loop consists of a Class 1 Rosemount transmitter f eeding a 4-20 mADC Class lE signal through the Rochester cabinet to a multiplexer. The IIUX will feed the SPDS and/or IDADS systems where the transmitter current output ,
signal will be displayed in engineering units (example - Steam Generator Pressure: PSIG). The required display can be called up using a 5 -
character point ID number (example - P.9005).
Calibration of these loops per Section 6.2 consists of first calibrating the Rosemount transmitter, 'N' then while holding the - /-
transmitter at the specified input values, reading and recording the desired computer points on the MOD COMP CRT monitor (H1CO) in the Control Room and/or the SPDS CRT. Data sheets are provided within' this procedure (Enclosure 7.8 thru 7.14) to record transmitter and computer points data. Enclosure 7.2 lists all transmitters calibrated under this method.
The third type of loop consists of a Class 1 Rosemount transmitter feeding a 4-20 mADC Class lE signal into the Rochester Instrument cabinet multiplexer (H4CDAR5) and to a mA/mA i RIS converter feeding a I-038-6 Rev. 1 i
Attachment 3
6.0 PROCEDURE ._
"OTE:
The.following is a general .
procedure for calibration ,
of'three basic types of loops.
The first type of loop consists of a Class 1 Rosemount transmitter feeding a Class lE 4-20 -
mADC signal into the .
Rochester Instrument c'abinet (RIS), with the class lE signal also.
typically going to either
( , ,* multiplexer H4CDAR3 or -
V. H4CDARS. The 4-20 mA signal is converted inside the RIS cabinet to a voltage signal which is wired MOH-lE to the input of the UNI system.
Calibration of these Instrument Loops consists of following a general
- procedure per Section 6.1 and completing a loop calibration form obtained from the I&C Supervisor, i
while referring to the specific I-053 Series drawings and UNI U15.07 Series prints indicated on the loop form. A loop calibration will be completed on all instrument loops and data recorded on the l
appropriate loop form.
! Enclosure 7.1 lists all transmitters calibrated under this method.
s.
I-038-5 Rev. 1 1
I i
Attachment 3 L.
- 1 r
6.0 PROCEDURZ (Cont.)
UOH lE signal .to a Square Root Extractor (also in the RIS cabinet) and to an indicator in the Control Room on-panel H2PS.
Calibration of these two loops consists of following Section 6.3 of this procedure and completing the loop forms obtained from the Isc Supervisor.
As Found ano As Lef t data is required on all ~
transmitters. Uhen performing the calibrations, adjuctments should be made per the manufacturer's instruction manual to obtain the best (A-- possible calibration .'
within the tolerances specified on the
. appropriate loop forms / data sheets.. Refer to I-Oll for general calibration procedures, i
llCCZ1 Hotify the Control Room before beginning calibration on loops that involve the UNI /ICS systems. Request the Operator to place or verify the affected control loop in Manual.
I-038-7 Rev. 1 Attachment 3
I G.0 PROCEDURE (Cont.)
13E3 Computer points in the 1000. series go only to the IDADS System and may be called up on any of the eight IDADS CRT Conitors, while points in- the 9000 series go to both ICADS and SPDS. Points-designated with an
-asterick (example P900l*)
on Enclosures 7.1 and 7.2 can be displayed on a SPDS CRT by using the "Page 1" feature on the- _
~
Alphanumeric Push Button.
This will display 49 Normal operating Parameters at once.
Each loop Form / Data sheet within this Procedure specifies the Normal operating display point and provides space to record the SPDS/IDADS displays where required.
.1 Calibration of Rosemount Class lE transmitters ano associated UNI loops (transmitters are listed in Enclosure 7.1). .
.1 Calibration of RIS cabinet EI-4420 4-20 mA to t10 VDC Class lE Analog Isolators.
.1 Uhile refering to the I-drawing for the loop being calibrated, disconnect the transmitter leads from the 1+ input terminals of the RIS cabinet and connect a Digital
. Calibrator (Ref. Section 4.10 & 4.11 and Enclosures 7.15 and 7.16) in their place.
I-038-8 Rev. 1 Attachment 3 9 %
9 - ,_ . _ _ , ___._m- , - . , - - , , -- , _-____,-_a - _ - , , __ ,, , - - - - -
l
- s 6.0 2nCC00U2C (Cont.)
. l .1.
.2 Connect a DMU, set to read -lu c v10 VCC, Oc t'ac desired output terminals of the-RIS cabinet. The proper terminals are listed on the loop forms in the "0U0200 ten"IUALS" column and also on nclosurc 7.1.
.3 Apply zero input of 4 ma to analog isolator.
M Refer to Enclosure 7.7 for location of the "ero and ,
Span adjustments on the EI-4420 Analog Isolator.
7 .4 Adjust zero pot R14 for -10.000 t .050VEC, as read on the DMU. _
.5 Apply full scale input of 20 ma to Analog Isolator.
.6 Adjust span pot R24 for full scale output of +10.000 t
.050VDC, as read on the DUH.
.7 Repeat Steps 6.1.3 thru 6.1.6 until no further adjustment is necessary.
Perform a five point check and . record the isolator-
.8 output to the UUI in the space proviced on the loop form. At this time any required IDADS anc/or SPCS computer points can be recorded in the ' space proviued on-the loop form.
f
- g. .9 Disconnect the DUM from the output terminals anu the Digital Calibrator from the input terminals.
i I-038-9 Rev. 1 Attachment 3
-6.0 ? ROC DURE -(Cont.)
.l.1
.10 Reconnect tlie transmitter input leacs liftec in Step 6.1.1.1 above.
.2 Calibration of Rosemount Class 15 Trcnsmitters Feeding UUI system via Rochester Signal Conversion Cabinet and
-Associated MUI Loop.
UQIE1 i
This section may be performed independently of ,
other sections of the procedure when it is desired to check the calibration of the -
Rosemount transmitter only. When an entire loop ') ,
form calibration is 2-required. Section 6.1.1 must be. completed prior to
- calibration of the transmitter.
.1 Motify the Control Room before commencing work on any transmitter.- Request that the Operator place or verify aff ected UNI /ICS Control Loops in Manual.
.2 Isolate the desired Rosemount trancmitter and connect. -
the calibrated pressure source to its input.
l
.3 Remove the terminal board cover of the transmitter (on your left as you face the transmitter) and connect a 1
Digital Calibrator (Ref. Section 4.10 & 4.11 and Enclosures 7.15 and 7.16) in their place.
I-033-10 Rev. 1 Attachment 3
5.0 PROC: LURE (Cont.)
.l.2-UD.TEL The test terminals are connected across a diode through which'the loop signal current passes.
The indicating meter or test equipment shunts the diode uhen connected to the test terminals and-as long as the voltage across the terminals is kept below the diode's ,
threshold voltage, no _
current passes through the diode. To assure that there is no leakage -
current through the diode
(",.
when a test reading is ,
being made or when an indicating meter is connected, the resistance of the test. connection or meter should not e::ceed 10 ohms. The test terminal screws are bored to accept a miniature banana plug (Pomona 2944,~3G90 or equivalent) .
.4 Vary the input pressure as required to obtain an "As -
1+ Found"' set of readings, as read on the Digital
+ Calibrator. Record these readings for entry in the ISC Dept. calibration records.
' \. f I-03G-il Rev. 1 Attachment 3 .
G.0- PROCEDURE (Cont.)
.l.2
.5 Vary the input pressure as required to calibrate che transmitter per Rosemount Inst. Hanual 43G8 (inside che Reactor Bldg. Hodels) or 4302 (outsi6e the neactor Eldg.
- t. Models). Record an "As Left" set of readings, as read
+ on the Digital Calibrator, for-entry in the ILC Dept. -
calibraton records and on the loop form.. (
.6 After transmitter calibration is complete, establish communications with someone stationed at the 33I cabinets in the Control Room. Vary the transmitter input pressure as required and record the UMI input voltago, as read on the DVM, on the appropriate loop form. -
f
. L_
llQIE.1 These voltages will be recreated in Step 6.1.2.12
')'
_/ -
~
of this procedure while completing the. remainder of the loop calibration.
.7 Disconnect the calibration source from the transmitter input and while observing the Digital Calibrator for 1
. over ranging, place the transmitter back in service.
1
.8 Disconnect the Digital Calibrator connected in Step
. 6.1.2.3.
.9 Replace terminal board cover as follows:
.1 Remove old 0-ring.
I-038-12 Rev. 1 Attachment 3
+
.1 6.0 PnOCEEUR2 (Cont.)
s >
.2...
.2 Tf necesscry, clean = sealing areas ui:h: Eleoaci anC.
lightly grease the o-ring uith Lou Corning 55C, Silicone 0-ring Grease.
O-Ringc nocecount ?/:: 1153-0039 SCUD Stock Coc;e 4 038251
- 2. Grease, S:.'UD Stock Code 0 038912
.3 . . . . . . , ,
...a ... . ~A. . ,s. I co C... .,c.,.......,.,..
..-..m..........
.4,. , 4
.,., i. .- ,,
.e. l a c e owvC
. , ., ...s. ,... ..;.... .3n ,. w . v _ . . .. ...r .
CaliiJeateci torque urench. Re00rc ;0rt,ue cd:E;ng or.
Enclosure 7.3'.
.10 2e; eat Steps 6.1.2.9.1 ':hru G.l.2.0.4 cn electrca:.ca
' (s..
cover if. it uas renoved curing caliernt:.cn.
~
~6. .'.'.".....'..~.s' . . 4 .: .~..'
- . ..' 1.
. l .'. c v- .a'e l .s t e
" e.'. . '. . **"-
u v . . .
'..t. _~ < -t ' w~ n
.nclosure
. i.o.
. . .. . . . . .. .. .. .~ . . . . . . . ., = . .. ...u..
. . ,. . .,..o e. . ,v e. n..u, .:. 4
..c.u 3 .a...,.r4.
i s. w r .3 =. . .. a.
u; 1; :. c.
test and_connae a t 10 V C vr.r;.:..:,la i.ower .
rheir .clacc. Ref er to the 1cou f or:a rnu to :'.e .
applicaule m!I Seriac U15.07 cr= ring 1:.sta on ;ne;xura .
i . ., to wo...r e w. -
1 ..e o n e .t ...1.
,. 4.4 g r._. 3.
4
..g w w
.........e..
.13 Var */ the JoUer ' 5u?])lya to rCCrus.';*: G..e VCl ~.: 5.i 00 00 0 0 e c. -
. .. su g . a. .a .,.s. . . ,.
<~
o :. . L. . u: . , ,.
.. ..a L a. a e L. ..w.; . u . l . ....a . 6w e .
.2 o ,. ; e. n..-.....,...n ..
. . . . . , . ..2...
.e. Co r ue C' c . w . .,.a 1 w..ws ,
4
'..w..
C .' ~...e '. '. t u
. . . e- m' o v' ,., .". o r.a a.Ha .'.3- . -
- m. " ' . . - - .. . . . . . . ' . . ~ . ...- e requirac voltages.
.14 Disconnect the n.ouer su?civ. anc reconnect the :".:I .
cabinet input leads (refer to the rougacc.'re 1cci, fcr:..
for 1rcner r .
connectica points).
\
. _ t. . . s. . .,, , .. 2 Attachment 3
e..
6.0 PROCEDURE (Cont.)
.1.2 LlGZE This completes.
calibration of an Instrument Loop consisting of'a.Rosemount transmitter, the RIS Class lE mA/ Volt Conversion module and the IIIII systeu loop. Steps 6.1 and 6.2 can be repeated for any loops listec on Enclosure 7.1 that recuires a .
complete " Loop Calibration".
'N
.2 Calibration of n'osemount Class lE Transmitters feeGing signal .).
thru Rochester conversion cabinet to a mult?ple::er. =/
. .UQ23 Transmitters calibrated
. under this-section c6 not-feed a' signal to.the UliI systen and are listed on Cnclosure 7.2. Inclosure 7.3 thru 7.14 are provided to record transmitter "As Founc" and "As Left" anc the Computer point Values.
.1 Isolate the desired Rosemount trancmitter anc connect the calibrated pressure source to its input.
i
! I-023-14 Rev. 1 i
Attachment 3 i
9" ,
6.0 PROCODURE (Cont.)
.2 ..
.2 Remove the terminal- board cover of the cransmitter (on your 1+ left as you face the transmitter) anc connect a Digital
- Calibrator (Reference Sections 4.10 and 4.11 anc Enclosures 7.15 and 7.16) in their place.
UQIfd.
The test terminals are connected across a diode through which the loop signal current passes. -
The milliameter or test equipment shunts the diode when connected to the test terminals and as long as the voltage across the terminals is kept below
-/~'
V,_ the diode's threshold voltage, no current. passes
+
through the diode. To assure that there is no leakage current through the diode when a test reading is being made or when a milliameter is connected,' the resistance i of the test connection or meter should not exceed 10 ohms. The test terminal screws-are bored to accept a miniature banana plug -
(Pomona 2944, 3490 or equal) .
4
.3 Vary the input pressure as required to obtain an "As Found" 1-- set of readings as read on the Digital Calibrator. Record these reading on the appropriate enclosure (7.8 thru 7.14) .
I-038-15 Rev. 1 Attachment 3
G.0 PROCEDURE (Cont.)
.2
.4 Vary the input pressure as required to calibrate the transmitter per Rosemount Instruction IIanual 43G0 (inside the Reactor Bldg. models) or 4302 (outside the Reactor 1-* Bldg. models). Record an "As Left" set of readings, au
+ read on the Digital Calibrator, on the appropriate enclosure.
.5 After transmitter calibration is complete, establish communications with someone stationed in the Control Room.
Vary the transmitter input and record the required computer points, as read on the HlCO CRT (IDADS) and/or the SPDS CRT, as required.
.6 Place transmitter back in service by performing Steps 6.1.2.7 thru 6.1.2.11 of this procedure.
i+ .7 Repeat steps 6.2.1 thru 6.2.6 for all transmitters listed
+ on Enclosure 7.2 that require calibration.
~%~
.3 Calibration of Auxiliary Feedwater Flow Transmitters FT-31802, FT-31902 and Associated Loops _s f-RQZE1 -
This section of the procedure first calibrates the RIS cabinet mA/mA isolator and square root extractor using a simulated current input signal. Then after calibrating the transmitters, the associated indicator on .
-the H2PS panel and the IDADS/SPDS computer points (as required) are read while actually holding the transmitter at predetermined inputs.
Refer to the loop form and to either drawing I-53, Sh. 6 or I-53 Sh. 7 while performing this section.
.1 Calibration of RIS Caoinet SI-4420 4-20nA/4-20tA Isolarcr and Associated (SC-1330) Square Root Extractor I-038-16 Rev. 1 Attachment 3
6.0 PROCEDURE (Cont.)
.3.1
.10 Perf orm a five point calibration check by -varying the
' input to the Analog-Isolator and note the output of the Square Root Extractor. If in tolerance as specified on the loop form, proceed to Step 6.3.1.11. -If out of tolerance, calibrate the SC-1333 Square Root Extractor per RIS procedure A-1030-7G7 in Tab'8 of the-RIS instruction manual.
.11 Vary the input to the Analog. Isolator as required to complete the loop form. Record the output of the CA/raA converter and of the Square Root Entractor in che space provided.
g.,
.12 Disccnnect the DMtis f rom the module outputs and the Digital Calibrator from the inpuc terminals.
'*h
.13 Reconnect the transmitter input leads lifted in Step
)~ i 6.3.1.3 above.
.14 Repeat Steps 6.3.1. thru 6.3.13 for the all Aunillary Feedwater Flow Channels requiring calibration.
.2 Calibration of Auxiliary Feedwater Flow Transitters FT-31802 and FT-31902
.1 Isolate the desired AFM Flow transmitter and connect the calibrated pressure source to it's input.
~
. Remove the terminal board cover of the transmitter (on t+ your left as you face the transmitter and connect a
+- Digital Calibrator (Reference Sections 4.10 anc 4.11 and Enclosures 7.15 and 7.16) in their place.
I-038-18 Rev. 1 Attachment 3
6.0 PROCEDURE (Cont.)
.3.1
.1 Refer to the loop form ano the specified I-uug. for the loop being calibrated and aisconnect the tranaci:ter leads from the input terminals o,f the RIS cabinet.
1+* .2 Connect a Digital Calibrator (ref. Section 4.10 anu 4.11 and Enclosures 7.15 and 7.16) to the input of the RIS cabinet.
.3 Connect a DIli, set to read 1-5VDC, to the input of the square root extractor, 1(-) , 2 ( +) .
.4 Adjust input to the Analog Isolator to 4 mA.
IlOZE1 Refer to Enclosure 7.7 for
- ("; the location of the zero .
and span adjustments on the EI-4420 mA/mA isolator.
.5 Adjust zero pot R14 for 1.000 t .040 VDC, as read on the D1111.
.6 Adjust the input to the Analog Isolator to 20 mA.
.7 Adjust the span pot R24 for full scale output of 5.000 -
t .040 VDC, as read on the D!!!1.
.8 Repeat Steps 6.3-4 thru 6.3.7 until no further adjustment is necessary.
.9 Connect a 2nd Drill set to read 0 to 10 VDC to the output of the Square Root Extractor 5 (-) , 6 ( +) .
i._
I-038-17 Rev. 1 Attachment 3
m
)
w 6.0 PROCCDURE (Cont.)
. 3.2 ,,
UD.IE The test terminals are connected across a diode through which the loop signal current passes.
The milliameter or test equipment shunts the diode when connected to the test terminals and as long as the-voltage across the-terminals is kept below
- the diode's threshold voltage, no current passes through the diode. To assure that there is no leakage current throdgh
/ .< the diode when a test readin g is being made or (i
when a milliameter is connected, the resistance of the test connection or meter should not exceed 10 -
ohms. The' test terminal screws are bored to accept a miniature banana plug (Pomona 2944, 3690 or equal) .
.3 vary the input pressure as required to obtain an "As
- 1+ - Found" set of readings as read on the Digital
+- Calibrator. Record these readings for future entry in the I&C Shop Calibration Records.
.4 Vary the input pressure as. required to calibrate the transmitter'per Rosemount Instruction IIanual 4302.
1+
Record an "As Left" set of readings, as read on the
..- Digital Calibrator, on the loop form.
.5 After transmitter calibration is complete, establish communications with someone stationed in the control
> Room.
s:
I-038-19 Rev. 1 Attachment 3
k 6 '. 0 . PROCEDURE (Cont.)
.6 Vary the transmitter. input pressure as required'and record the SPDS/IDADS computer points (as required) and flow indicator readings required on the loop f orms.
.7 ' Place transmitter back in service by performing Steps 6.1.2.7 thru 6.1.2.11.of-this procedure..
.3 Repeat Steps 6.3.2.1 thru 6.3.2.7 for all Au::iliary Feedwater Flow transmitters requiring calibration.
.s
.) .
. . s.
1
.i I-038-20 Rev. 1 Attachment 3
_- . _ _ ~ , _ . _ _ , , , _ , - _ _ _
m 7.0 E;! CLOSURES
.1 List of Rosemount transmitters calibrated using ;;1:I Loop Calibration Forms per section 6.1.
.2 List of Rosemount Transmitters calibrated per section 6.2, that feed tiultiplexer only.
.3 Dual Verification of Transmicter OUT OF/IllTO Service, Cover Replacement
.4 Typical m1I Loop
.5. Typical Instrument Loop for tiultiplexer input only type loops
.6 Instrument Loop Diagram for FT-31802 (I-053 sh. 6)
.7 RIS 1E Analog Isolator SI-4420 Layout Showing Locations of Zero and Span Adjustments.
.3 Calibration Form - Cond Storage Tank Level, LT-35809, LT-35810
{,-
.9 Calibration Form - Aux Fil Pump "A" Suction and Discharge Pressure - PT-31801 and PT-31803
.10 Calibration Form - Aux F11 Pump "B" Suction and Discharge Pressure - PT-31901, PT-31903
.11 Calibration Form - RCS Ilide Range Pressure, PT-21050 and PT-21051
~
.12 Calibration Form - RB ITide Range Pressure , P'"-53621 and PT-53622
.13 Calibration Form - Auxiliary Fi1 Test Flow, FT-31050 ,
.14 Calibration Form - Auxiliary Fif Test Flows, FT-31803 anc.
FT-31903 1-.-
.15 Ronan Model X85 Calibrator Operating Instructions f or Two-ilire
+ Transmitter Simulation.
1+ .16 Transmation Model 1040 PPS Digital Calibrator Operating
+ Instructions for Two-ilire Transmitter Simulation.
s I-038-21 Rev. 1 1
Attachment 3
ENCLOSURE 7.1 ROSEHOUNT TRANSHITTERS CALIBRATED USING NNI LOOP CALIBRATION FORMS PER SECTION 6.1 l TRANSHITTER RIS INPUT HODULE OUTPUT .HUI.TIPLEXED I MNI TERMINAL NO TERMINALS DWG DRAWING-j ID TRANSHITTER MAME CAB NO FT-23606 RC Pumps Seal Inj. Flow A TB-3, 212, 213 AIA8- TB-4 22(+),23 1 F1000 N15.07-74
! FT-23805 HPI Flow loop B A TB-3, 217, 218 AIA9 TB-4 25(+), 26 3 F9001* N15.07-76 FT-23806 HPI Flow Loop D A TB-3, 222, 223 A1A10 TB-4 28(+), 29 3 F9002* N15.07-76 FT-23807 HPI Flow Loop A B TB-3, 159, 160 A1A7 TB-4 19(+), 20 5 F9003* N15.07- ,
FT-23808 HPI Flow Loop C B TB-3, 164, 165 A1A8 TB-4 22(+), 23 5 F9004* N15.07-bo i FT-26003 Decay Heat Flow "A" B TB-3, 227, 228 A1A11 TB-4 31 (+) , 32 3 F9005* N15.07-80 I
FT-26004 Decay Heat Flow "B" B TB-3, 169, 170 A1A9 TB-4 25(+), 26 5 F-9006* N15.07 l '
! LT-20501 S/G A Full Ranae Level A TB-3, 177, 178 A1A1 TB-4,1(+), 2 3 L9801* N15.07-69
~$ LT-20502 S/G B Full Ranae Level B TB-3, 129, 130 A1A1 TB-4,1 (+) , 2 3 L9802* N15.07-69 E LT-20503A S/G A Operate Level A TB-3, 182, 183 A1A2 TB-4,4(+), 5- 3 L9803* N15.07-70 l 0 LT-20503B S/G A Operate Level B TB-3, 134, 135 A1A2 TB-4, 4 (+), 5 5 L1804 N15.07-70 l $ LT-20503C S/G A Startup Level B TB-3, 139, 140 A1A3 TB-4, 7(+),8 5 L1805 N15.07-69 LT-20503D S/G A Startup Level A TB-3, 187, 188 A1A3 TB-4, 7(+), 8 3 L9806 N15.07-69 l $ L1803 N1'bO7-70 w LT-20504A S/G B Operate Level A TB-3, 192, 193 A1A4 TB-4, 10(+),11 3 .
LT-20504B S/G B Operate Level B TB-3, 144, 145 'A1A4 TB-4, 10(+) 11 5 L9804* N15.07-70 LT-20504 C S/G B Startup Level A TB-3, 197. 198 A1A5 TB-4, 13(+),14 5 L1807 N15.07-69 LT-20504 D S/G B Startup Level B TB-3, 149, 150 AIA5 TB-4.- 13 (+),15 5- L9808 N15.07-69 LT-21503A Pressurizer Level #1 A TB-3, 202, 203 AIA6 TB-4, 16(+),17 3 L9005* N15.07-61 j LT-21503B Pressurizer Level #2 A TB-3, 207, 208 A1A7 TB-4, 19(+),20 3 L9006* N15.07-P LT-21503C Pressurizer Level #3 B TB-3, 154, 155 A1A6 TB-4, 16(+),17 5 L9007* N15.07 .
N15.07-79
! LT-26505 Core Flood Tank A Level B TB-3, 179, 180 A1A11 TB-4, 31(+),32 L9001 LT-26506 Core Flood Tank B Level B TB-3, 174, 175 A1 A10 TB-4, 28+,29 5 L9004*- N15.07-79 LT-26507 Core Flood Tank A Level A TB-3, 237, 238 A1A13 TB-4, 37(+),38 3 L9003* N15.07-79 Core Flood Tank B Level A ,TB-3, 232, 233 A1 A12 .TB-4, 34, 35 g L9002 ;N15.07-79; 1 LT-26508 i NOTE:
i i
I-O -22 Rev. 1 i
I l I
' p) s s .'
I t, t
I -
ENCLOSURE 7.2 +
TRANSMITTERS CALIBRATED PER SECTION 6.2 THAT FRED BRILTIPLEXOR ONLY j
I E Tgan M I-DMG I D. , B 7 ,, , ,
FT-31803 Aux FU Flow-Isop A A TB-3,65.66 TB-3.70,71 (+)68.69(+) 54CD&R3 F1661 I-053 Sht. 6 FT-31903 Aux FU Flow-Imop B A TB-3,73,74 TB-3.79.80(+)76,77(+) B4cnant F1663 Aux FU Bypass Flow TB-4,68,69 TB-4.71,75 54CD&R6 F1670 1-053 1-053 Sht. Sht.3\7.I FT-31850 B l ,
LT-35809 Condensate Storaae Tank Level A TB-3,9.10 T5-3.15,16(+)12,13 54CD&R3 L1601 1-053 Sht. 2 t LT-35810 Condensate Storsae Tank Level B 75-3.9.10 TB-3.15,16(+)12,13(+) 54CD&R5 L1602 1-053 Sht. 2
!N g r
< e * -
P9000*
, g PT-21050 BCS U.R. Pressure 3 TB-3,25,26 TB-3.31.32+ 29 30F B4cnan% I-053 Sht. 9
! s PT-21051 BCS U.R. Pressure A TB-3.25,26 TB-3a31.32.29.30 . 54CD&R3 P9001s 1-053 Sht. 9
" TB-3,49,50 TB-3.55,56(+)52,53(+) 54CD&R3 P1807 I-053 Sht. 10 PT-31801 Aux FU Pump Dsch Pressure A
- PT-31803 Aux FU Pump Suction Pressure A TB-3,57.58 T5-3.63.64(+)60.61(+) 54CD&R3 P1809 I-053 Sht. 10 PT-31901 Aux FU Pump Dsch Pressure B TB-3.49,50 T5-3.55.56 B4cnan5 P1808 I-053 Sht. 11 l'
PT-31903 Aux FU Pump Section Pressure 3 T5-3.57.58 TB-3.63.64 54cnAR5 P1810 I-053 Sht. 11
! PT-53621 Reac Blda U.R. Pressure A TB-3,1.2 TB-3.7,8+.- 4.5+ B4CD&R3 P9051* I-053 Sht. 1(
PT-53622 Reac Blda U.R. Pressura B TB-3,1.2 TB-3.4.8 54CDAR5 P1052 1-053 Sht. 1 i
NOTE:
)
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ENCLOSURE 7.6 _,
DISTRUNINT LOOP DIEllAM FOR FT-31802
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ENCLOSURE 7.7
+ l!:',P l!
-s I ! $! '!
~ '
RIS 1E Analog Isolator II-4420 Layout lj fld Ill Showing Incations of Zero (. Span Adjustments. j gg
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i ENCLOSURE 7.8 CONDENSATE STORACE TANK LEVEL TRANSHITTERS LT-35809 & LT-35810 3-e Note 1 2 TRANSMITTER TRANSHITTER COMPUTER Note 1 3 TRANSHTTTER COMPUTER gypHT lAS FOUND AS LEFT POINT INPth AS FOUND- l TRANSMITTER AS LEFT POINT LT-35809 LT-35809 LT-35809 IDADS L1601 LT-35810 LT-35810 LT-35810 1 DADS L1602 (4.64) (4.64) (2) (4.64) (4.64) (2) 37 4.64 37.5 4.64 (8) (8) (12.5) (8) (8) (12.5T 163 8 163.5 8 313 (12) (12) ~723F (12) (12) -(13T 12 313.5 12 (16) (16) (31.3) (16J (16) (37.5) 463 16 463.5 16 (20) -(20) (50) (20) (20) (50) 613 20 613.5 20 (16) (16) (16) (16)
~~~ 463 16 NR 463.5 16 NR
~
(12) (12) (12) (12)
_> 313 12 NR 313.5 12 NR R (8) (8) (8) (8)'
,S 163 8 NR 163.5
- 8 NR s (4.64) (4.64) (4.64) (4.64')
- ! 37 4.64 NR 37.5' 4.64 MR t1W.C. MA HA MA Feet "W.C. HA MA NA Feet Tolerance i .25%=.04HA i .251=.04MA Tolerance i .25%=.04HA i .25%=.04MA Tant Equipment Used Recal Due Date Test Equipment Used Recal Due Date Test Cauge CTE- Date Test Cauge CTE- Date Digital Calibrator CTE- Date Digital Calibrator CTE- Date DHN CTE- Date DIG ( CTE- Date Performed By Date Performed By Date Reviewed By Date Reviewed By Date ,
I6C Engineer I&C Engineer
- 1) Input AP is the applied input plus the "W.C. above 4) Tank Tap is 24" above tank bottom.
centerline of Transmitter.
- 5) Velve manifold tap is 14" above Transmitter Centerline. !
- 2) LT-35809 is mounted 13" below tank bottom.
- 6) Both Transmitters have dry low side reference legs.
- 3) LT-35810 is mounted 13 1/2" below tank bottom.
I-038.' Rev. 1 '
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anamaman. 7.10 .
AUXILIARY FEEDUATER FlBIP "B" SUCTI001 & DIScil&BGE PRESSURES Ref 1-053 Sh. 11 r, _. ,a ..s. . - CTIO. P =SSU .
1 TRAIISItITTER CGIfUTER TRAIISMITTER j IMPUT lTaaansasTTTER AS 70 W AS 1.EPT POINT llIPUT AS 90U110 g TRAIISIAS p l QP01 i
PT-31901 PT-31901 PT-31901 IDADS P1808 PT-3.903 PT-31903 PT-31903 I n" 21010__
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! Tact Equipment Used Recal Due Date Test Equipment Used Recal Due Date i
'I d igital Calibrator CTE- Digital Calibrator CF-I l Test Gauge CTI- Test Gauge CTE- i
- Deat CT3- met CTE-Tarformed By Date Performed By Date i
Reviewed By Date . Reviewed By Date '
,I-038-32 Rev. I I f-*%,
! (
- 3 l 8 h -
.ENCIASURE 7.11 ') '
REACTOI:
C001. ANT SYSTEM UIDE RANCE PRESSURES PT-21050'- PT-21051 Ref: Drawing I-53 Sh. 9 . 1-1186 Ref: 1-1184 INPUT AS FOUND AS LEFT y POINT INPUT AS FOUND IDADS ' . p%S~ AS I. EFT j ,PT-21050 PolNT PT-21050 PT-2I050 18 4 (4) (4)
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g (2oT t201 ( 30% >
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IMI CTE- Test Equipment Dtti s
Recal Due Date Test Cauge CTE- .CTE-Test Cauge CTE-1- Digi tal Calits. CTE-Digital Calits. CTE-Performed By Date Performed By Date Reviewed By Date I&C Engineer ' Reviewed fly Date a
I&C Engineer I-038-33 gey, )
g .
a PT-53621 PT-53622, ,
ENCLDSURE 7.12 REACTOR BUILDING WIDE RANG'E PRESSURES ,
TRANSHITTER TRANSHITTER COMPUTER TRANSHITTER TRANSHITTER. COMPUTER -
INPITT AS FOUND AS LEFT POINTS INPUT AS FOUND AS LEFT POINTS
- IDADS SPDS '
PT-53621 PT-53621 PT-53621 P9051 Pr 1.Pt 24 ~'
PT-53622 PT-53622 PT-53622 IDADS P1052 -
(4) (4) (-5) 4 (4) (4) .(-5 )
_5 4 (8) (8) (41.25) tal tas (41 M 2-* 41.25 8 l 41.25 8
( 12T (121 ( 37.5) ,
tazi tazi ta7.si ;
87.5 12 l - 87.5 12 (16T (161 (133.75) (163 (161 (133 737 133.75 16 l 133.75 16 (20T (20) (1801 - (20i tzo unor-
.I80 20 l _
180 20 ,
(16) (161 (16) (16) 2-, % 138.75 16 ji I33.75 16 te '
NR
@ (12) (12) (12) (12) g C7.5 12 te 92.$ 12 NR g (8) (8) (8) (8)-
, 41.25 8 ta 46.25 8 . NR ___
(4) (4) (4) (4)
-5 4 ta -5 4 NR PSIC . HA -
HA MA PSic PSIC HA HA HA PSIG Tot.ERANCE 1 25%=.04HA 1 25%=.04HA ,
TOLERMCE t .25%=.04HA 1 25%=.04HA Test Equipment Used Recal Due Date Test, Equipment Used Recal Due Date DeH CTE- [8 91 CTE- .
Test Cauge CTE- Test Cauge CTE-IJigital Calibrator CTE- ,
Digital Calibraror CTE-Performed By Date Performed By Date Reviewed By Date Reviewed By Da'te IEC EnRineer I&C Engineer I-038-34 Rev. 2 1 e s
. - a
j I
D Q' .
g_ ,
ENCIDSURE 7.13 AUXILIARY FEElWATER TEST FIAW - FT-31850 Ref: I-053 Sh. 3 l INPUT ER AS FOUND AS LEFT - PolNT FT-31850 FT-31850 FT-31850 IDADS F1670 (4) (4) (o) 0 4 (8) (8) (550:
50 8 .
(12) (12) (777.7) 1 00 12 ,
(16) (16) (952.6)
K 150 16 -
g -
(20) (20)
(1100) g 200 20 w (16) (16) n .
- s 150 16
" NR (12) (12)
, 100 12 NR (8) (8) ,
50 8 .
NR (4) (4) 0 4 '
NR s "W.C. HA HA MA GPM Tolerance 1 25%=.04HA f.25%=.04MA Test Equipment Used Recal Due Date .
19 91 CTE-Test Cauge CTE- ~
t* ..
Digital Cal ib. CTE- .
Performed by
- Date -
Neviewed By Date I&C hugineer I-038- 35 1:ev . 1 ,
FT-31803 FT-31903 ENCLOSURE 7.14 AUXILIARY FEEDWATER, FLOWS FT-31803 and FT-31903 TRANSHITTER TRANSHITTER COMPUTER TRANSHITTER TRANSHITTER COMPUTEPS INPUT AS FOUND AS 1. EFT PolHT INPUT AS FOUND AS LEFT POIMT FT-31903 FT-31903 IT-31903 IDADS F1663 8 FT-31803 FT-31803 FT-31803 (4) (4) (0) 64f ( 9 T- (0) 0 0 0 0 (8) 08~) (6661 (8) (8) (650) 2+ 67.5 650 67.5. 625 g (12) (12) (919.21 (12) (12) (919.2) 135 919.2 135 919.2 g (16) (16) (1125.8) (16) (16) (1125.8) 202.5 1125.8 202.5 1125.8 l
(20) (20) -(1300) (20) (20) (1300)
- 270 1300 ~ 270 1300~
- l N (16) (16) *
(16) (16)
@ 202.5 1125.8 NR ~202.5 l'125.8 NR 8 (12) (12) (12) (12) *
$ 135 919.2 NR 135 919.2 NR w (8) (8) (8) (8)
+ (s7.5 650 NR 67.5 650 NR (4) (4) (4) (4) 0 0 NR 0 0 NR
'*U.C. CPM HA HA CP11 "W.C. CPM HA IIA CPM TOI.ERANCE 1 25%=.04HA 1 25%=.04HA TOLERANCE t.25%=.04HA 1 25%=.04HA AUX FW Flow OTSC B Ref: I-053, Sh. 7 AUX FW. Flow OTSC A Ref: 1-053, Sh. 6 TEST EOUIPMENT RECAL DUE DATE TEST EQUIPHENT RECAL DUE DATE DHH . CTE- Diet CTE-Test Cauge CTE- '
Test Gauge CTE-Digital Calib. CTE- Digital Cal ~1b. CTE- s
~
Performed By Date ' Performed By Date Pev ewed Fy Date Reviewed liy Date 16C Enginee, i C~ Engineer 1-03 Rev. 2 .
. o
l' 3
ENCLOSURE 7.15 _
am '
2-WIRE TRANSMITTER SIMULATOR, RONAN MODEL X85 CALIBRATOR Terminals are previded for 2-wire transaicter simulation. The calibrator is connected to the system to be calibrated as shown.
MODELX85 I I LOAO(S)MAY BE HERE oo I-~l
/ '
O.*CrO i l
~ ~ ~
0 TO + 40 VOC 2.WIR E POSTS SYSTEM LOA 0(S)
.- a..- .~ .. . . . , . . , . . .. .
O i -
2-WIRE TRANSMITTER SIML*LATION 1
- 1. Set the METER switch to the OLTIPUI position.
- 2. Set the OUTPUT RANCE switch to the 100MA position.
- 3. Set the SCALE-ZERO switch to the SCALE position.
4
- 4. Connect the external current loop to the 2-wire output posts observing polarity as shown.
- 5. Adjust the COARSE and FINE output controls for the required calibration current.
NOTE: If there is to be repeated calibration between two current levels, the lower current may be. adjusted on the ZERO ADJ -
control and the higher current level aey be set up as above.
The SCALE-ZERO switch then allows convenient and fast switch-ing between the two current levels.
l l
I-038-37 Rev. 1 Attachment 3 P . -._ u
l ENCLOSURE 7.16
~
1130-kTRE TRANSMI AitA SIMULATION - e
-d TRANSMATION MODEL 104C DIGITAL CALIBRATOR
+h VIN /0UT *
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= our O@-
= 4
. TWO VIRE+TRANSMITTIR SIMULATOM OUIPt/I -
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IMTA Siw l
(
TWO '=' IRE TRANSMITIER SIMLUTOR OUTPUT:
In 'this mode, the instrument will simulate the output from a two-wire trans-mitter when connected in a loop having a supply voltage of between 22 and 100 volts.
- 1. Put the function switch "A" in the XMTR SIM position.
- 2. Disconnect the ::vo-wire transmitter from the loop.
- 3. Connect the digital calibrator in the loop with the DfTR SIM binding posts.
- 4. Set the coarse and fine controls "B" and "C" to the desired current.
The coarse control has a sensitivity of 10 aA per position and the fine control has a sensitivity of 1 mA per turn. The output current is read directly off the display "L".
~
I-0'38-38 Rev. 1 Attachment 3 k
I ,
3 PURPOSE (Continued) ,
1.3 Sof tware changes which are not subject to this procedure include:
.1 Parameters or data entered by a user, under program control, whi~ch do not affect plant monitoring. .This includes personnel records on the ALARA/HP and Security / Training computer systems.
.2 Programs running on programmable calculators or personal computers which are used for unof ficial calculations, word processing, scheduling, or other similar administrative or computationsl tasks.
.3 Diagnostic programs used to troubleshoot hardware problems.
.4 Changes to programs controlled by NEP 4120.
2.0 REFERENCES
.1 Plant Computer Operating Manuals (A.75 and A.75A)
.2 Administrative Procedure, Records Management (AP.8)
.3 Ranch'o Seco Configuration Control Procedure (NEP 4109)
.4 10 CFR 50.59
.5 10 CFR 50.54, paragraphs P & Q ,
.6 NEP 4120, Standard Engineering Computer Programs ,Y 3.0 PROCEDURE
.1 Initiation, Routing and Review
.1 A software change is initiated-by submitting a Software Change Request (SCR) form or District memo to the Supervisor, Computer Engineering. A copy of Enclosure 4.1 may be used for the SCR if pre-printed forms are not available.. Memo requests should include all of the information requested in the "0RIGINATOR" section of the SCR form including:
.1 EQb1PMENT 10/ DESCRIPTION - Enter the equipment -ID number or a -
description of the system.
.2 SYSTEM / PROGRAM - Enter the software system or program affected by the change.
.3 REQUESTED COMPLETION DATE - Enter a realistic date that gives a reasonable amount of time to complete review, routing, implementation and testing.
Rev. 3 AP.52-2 Attachment 6
i EFFECTIVE DATE 07-11-86 Rev. 3 WP0566P D-0023P AP.52 SOFTWARE CHANGE PRDCEDURE l
1.0 PURPOSE
.1 The purpose of this procedure is to establish the method, responsibilities, and requirements for recommending, approving and implementing changes to Rancho Seco computer software. A software l
change is defined as any modification which alters the performance or capabilities of the software.
.2 Software changes which are subject to this procedure include:
- .1 Software changes to any of the folicwing computer systems
I
.1 The Bailey 855 Plant Computer
.2 Thc IDADS Plant Computer System -
.3 The Safety Parameter Display System (SPDS)
.4 The Plant Security and Training Computer System
(
.5 The ALARA/HP Records Management System .,'
.6 The General Atomics Radiation Monitoring System
.2 Any software used as a part of a Rancho Seco procedure or used to satisfy a regulatory requirement. This includes programs that run on programmable calculators, personal computers, or time share
( systems and includes software developed or modified by vendor, l contractor, or District personnel.
.3 Database changes where the change reflects a plant configuration change or'affects plant monitoring capabilities. This includes data base changes to the following computer systems:
.1 The Bailey 855 Plant Computer
.2 The IDADS Plant Computer System
.3 The Safety Parameter Display System (SPDS)
.4 The General Atomics Radiation Monitoring System Rev. 3 y, AP.52-1 Attachment 6 l
l
. ,d t
< 5
.h -
4 -
PROCEDURE (Continued) 3.1 .1 .4 FOLLOWUP - Check "Yes" if a followup action is required to close out an SCR; otherwise, check "No." "Yes" examples:
.1 A vendor software update notice has to be closed out.
.2 An NCR has to be closed out.
.3 A test has to be run at a later date.
.4 Suitability can't be determined until the change has been run for a specified amount of time.
.5 TIME-CRITICAL - Check "Yes" if the implementation of this change is urgent and must be accomplished before a specific date or event; otherwise, check "N6."
.6 REQUEST / JUSTIFICATION / FOLLOWUP / TIME CRITICAL REQUIREMENTS -
Give a brief explanation of the change. Include enough detail to review and, if necessary, explain any attachments. Explain any followup or time-critical requirements.
.7 ATTACHMENTS - Check "Yes" if any attachments are included and list them. Typical attachments would be copes of ECNs, NCRs,
- Work Requests, log sheets, computer listing, or trouble reports.
.8 REFERENCES - List any refer'ences such as ECN number, NCR f (f" . number, Work Request number, manual title and/or number, procedure number, or trouble report. _,'
.9 ORIGINATOR - Enter the originator's name.
10 OEPARTMENT - Enter the originator's department.
.11 MS - Enter the originator's mail stop.
(
.12 EXT - Enter the originator's extension.
.13 DATE - Enter the date that the SCR is submitted.
.2 On receipt of an SCR or memo, Computer Engineering will:
.1 Assign a number to the SCR and enter it into the SCR Log.
.2 Fill out an SCR (if necessary).
Rev. 3
.s AP.52-3 Attachment 6 l
l t
i, .
2 PROCEDURE (Continued) 3.1 .2 .3 Perform a feasibility review and make sure that the requirements are completely and accurately defined and that supporting documentation (including database change request forms, if appropriate) are complete. The reviewer shall fill out the " FEASIBILITY REVIEW" portion of the SCR as follows:
.1 COMMENTS - Enter a brief description of the results of the review. httach supporting documentation if necessary.
.2 REVIEWED BY - Enter name of reviewer.
.3 DATE - Enter current date.
.4 ATTACHMENTS - If any attachments have been added by the reviewer, mark "Yes" and list the attachments.
.4 If a followup is required, enter.the SCR number, due date, and required action into the followup log maintained by Computer Engineering.
.5 Indicata appropriate approval and review routing using the following general guidelines:
.1 All SCRs are routed to the Technical Support Superintendent.
.2 Changes to the Bailey or IDADS plant computers or Control 1:3 Room microcomputer system are routed to the Nuclear 1)
Operations Superintendent. '[,4
.3 Changes to the security computer are routed to the Supervising Special Agent.
.4 Changes to the training records system are routed to the Nuclear Training Superintendent and to the Supervising Special Agent.
.5 Changes to the ALARA/HP system are normally routed to the Nuclear Radiation Protection Superintendent.
.6 Send a copy of the SCR back to the originator.
.7 Route the SCR to those indicated in the " APPROVAL & REVIEW" section of the SCR.
.8 Track the routing status and ensure the timely completion of time-critical coordination.
Rev. 3 AP.52-4 ,
Attachment 6 2
~
r=
PROCEDURE (Continued) 3.1 .3 For each SCR received, the Technical Support Superintendent shall determine: -
.1 The requirement for a 10 CFR 50.59 review.
.2 The requirement for a 10 CFR 50.54Q review.
.3 The need for routing the SCR to the Supervising Special Agent for a 10 CFR 50.54P determination.
.4 Any person on the approval and review routing may add additional routing by adding the new name in one of the routing blanks, checking the box to the left of the name, and initialing next to the added name.
.5 Time-critical and emergency changes may require special handling such as:
.1 Hand carrying the SCR to reduce coordination time.
.2 Telecon approval with followup approvals and review signatures. This method of SCR approval shall be limited to .
emergency or time-critical SCRs.
.2 Implementation and Closecut r'~. .1 After a properly authorized SCR is received by Computer Engineering: #
(_- .
.1 If the software change is for a computer system or program -'
l maintained by Computer Engineerir]g, Computer Engineering shall l implement the change according to internal procedures for software development and configuration control.
.2 If the software is not mainiained by Computer Engineering, l (time share program, programmed calculator, personal computer
- program, etc.), the SCR originator shall be responsible for i ensuring that
.1 The change is implemented in accordance with industry standard software development techniques.
.2 A functional test is performed.
.3 Documentation and magnetic media are properly updated.
Rev. 3 i AP.52-5 Attachment 6
PROCEDURE (Continued) 3.2 .2 Computer Engineering shall complete the " DISPOSITION" section of the SCR prior to closecut. Closecut shall be performed by Computer Engineering according to internal procedures that ensure:
.1 Functional verification of the software change.
.2 Magnetic media and documentation are updated, including transmittal of new manuals or updates to the Vendor Manual Library for distribution and control.
.3 Notification of affected areas (e.g., training, operatnrs).
.4 Completion of post-release audit.
.5 Any followup requirements have been met.
.6 A copy of the completed SCR is sent to the originator.
.3 If the software change was not implemented by Computer Engineering, Computer Engineering will provide an analyst to ensure that the criteria of Section 3.2.2 have been met.
.4 If a new Work Request is issued to install the software change, -
Computer Engineering will enter the Work Request number in the
" DISPOSITION" section of the SCR.
N 4.0 ENCLOSURES . ./~
.1 Form,' Software Change Request (SCR) l l -
t Rev. 3 AP.52-6 l
l Attachment 6 l
l A
~
ENCIDSURE 4.1
_.. l
- SOFTWARE CHANGE REQUESTy. sn ,
'(,A) ORIGINATOR
=QU E F Rt 3E I IU/DL)LEIFilGR bThltR/PRQGRAR E=QVthitD (URFLtTIgm DAIL FULLgwuF TIME. CRITICAL kYES yt3 k gg NO (YES. DESCRI8E RTLOW)
NtQUt3I / JU354PIEAllGN / PULLUWWF / IIRt GRIILGAL RtQUIRtRtNI)
AII ALMntsia L J Yt3 lut30xtst) statutacts (t6m. aca. uUna atQuths. 5FR. Lic)
Ungr.imarca atramentaa R.>. tal. Gait I
FEASIBILITY REVIEW 6w mais um utvitwto av oAit O A,, Au t.., u ru t otsui. } .
. = -
n APPROVAL AND REVIEW mart hisNAIUR. UAlt M TECHNICAL SUPPORT SUPERINTENDENT E 10CFR50.540 REVIEW REQ'O $
10CFR50.59 REVIEW REQ'O [(])
YESYES
[] No() No g
[] $UPENVl5ING SPECIAL AGENT @
ygg 10CFR50.54P REVIEW REQ'O () YE5 [] NO
() NUCLEAR I&C SUPERINTENDENT g
[] CHEM. RAD PROTECTION SUPERINTENDENT E
O
() NUCLEAR OPERATIONS SUPERInituotNT g
() TRAINING SUPERINTEN0 TNT
[] M
() 2
.O DISPOSITION 3:6xArust UAlt wont stQutsi sc.
AUTHORilt0 FOR RELEASE RELEASE COMPLETED POST-RELEASE AUDIT COMPLEff0
~
FOLLOWUP /flME. CRITICAL REQUIREMENTS COMPLETED NOTE: Rouit THIS SCR SACK TO COMPUTER ENGINEERING AFTER EACM APPROVAL SIGNATURE Rev. 3 END AP.52-7 ATTACHMENT 6
m Os ii Nucicar Engin3Gring Proc dura
)CMUD NEP 4109 RANCHO SECO CONFIGURATION CONTROL PROCEDURE 1.0 PURPOSE !;;j ;g g, ,
The purpose of this procedure is to provide for configuration control for Rancho Seco through a set of instructions covering the initiation, review, issuing and revision of design disclosure documents. This set of instructions implements certain requirements in QAP-2, " Design Control,"
Rancho Seco Quality Assurance Manual. (See QAP-2 for the listing of covered documents.)
2.0 POLICY AND RESPONSIBILITIES 2.1 GENERAL POLICY (1) The approval documents utilized in the Configuration Control Program are: the Engineering Change Notice (ECN), Attachment 8.1; the Drawing)
Report (DBR Change Notice Attachment 8.3; the(DCN),
Design(See Verification NEP 4112);
Report the Design Basis (DVR), Attachment 8.4; the Safety Analysis (SA) (see QCI-5); and the Safety Review of~ Proposed Facility Change (SRPFC) form (see QCI-5). ..
(2) The Nuclear Project Engineer sfall determine if an ECN does or does not require Nuclear Engineering Staff review and approval.
ECN/DCN's not requiring Nuclear Engineering Staff approval will as a minimum be signed by a Nuclear Operations senior engineer.
(3) SDC shall retain a list of names and sample signatures of all persons authorized to sign on design disclosure documents as Managers, Supervising Engineers, Cognizant Engineers and Licensing Engineers. These levels of approval on ECN's and DCN's shall designate alternates to sign for them when they are not available. The Supervising Engineers shall submit to SDC the names and sample signatures of all designated alternates to Supervising, Cognizant and Licensing Engineers. The managers and supervisors shall be responsible for keeping the signature lists current.
(4) Anyone can prepare and submit an ECN or DCN to engineering personnel for review; however, entry into the system must be authorized by the originator's supervisor and engineering personnel in either Nuclear Operations, Nuclear Engineering, or Engineering Departments.
4109REV4 Page 1 of 24 Revision 4 Attachment 4
._ - - - . - ~.
CMUD NucIcar Engin:Gring Proccduro NEP 4109 (5) Nuclear Operations, Nuclear Engineering, and Engineering shall assign responsibility for administering their portion of the Configuration Control Program. These are defined as follows:
(a) Nuclear Operations - Site Document Control (SDC)
(b) Nuclear Engineering - Nuclear Engineering Document Control (NEDC)
(c) Engineering - Engineering Configuration Control (ECC)
It is the responsibility of the three department managers to i
ensure thase control points enforce the requirements of this procedure for all ennfiguration changes at Rancho Seco.
~
(6) The paperwork flow of ECN's and DCN's between Nuclear Operations and Nuclear Engineering will be through the SDC and NEDC control I points.
(7) SDC and NEDC have the authority to return ECN's and DCN's to the l
Cognizant Engineer for corrections to bring them up to acceptable administrative and document standards and to insure the
- - information presented is legible; however, SDC and NEDC do not l review for technical content.
(8) The responsibility for maintai ing specialized lists, schedules, logs, etc., will be as shown in Attachment 8.5 and AP.42.
(9) ANSI-45.2.11 1974, Section 8. " Design Control," requires establishment of procedures for control of design changes to approved documents, including " field changes." This procedure establishes a method for review and approval of changes to approved design documents, regardless of the source of the change. Changes to approved design documents which become necessary due to problems arising during construction or startup shall be reviewed and approved per this procedure.
2.2 ENGINEERING DEPARTMENT RESPONSIBILITIES The Engineering Department has overall responsibility for the Rancho Seco Switchyard.
2.3 NUCLEAR ENGINEERING DEPARTMENT RESPONSIBILITIES (1) Responsible for the plant configuration control of Rancho Seco.
(2) Responsible for approval of all design modifications when Nuclear Engineering staff approval is required.
4109REV4 Page 2 of 24 Revision 4 Attachment 4 E 9 erss oas- - . - . - - -.._- . . _ _ _ _ . _ _ __ _
0CMUD v
NucIcar Enginscring Proc: dure NEP 4109 (3) Responsible for providing testing criteria for modifications when applicable.
(4) Responsible for determining which ECN(s) require staff. approval, ,
when a DBR is required, and when Design Verification is required. ;
(5) Responsible for incorporating all " Work Complete" DCN's and l generating new drawings.
(6) Responsible for ensuring Environmental Qualification (EQ) review is performed as required by the EQ Program. An EQ Coordinator shall be established, reporting to the Electrical Discipline Supervisor.
(7) Responsible for ensuring that fire protectionL review of design modifications is performed per the Fire Protection Program Manual and associated Nuclear Engineering procedures. A Nuclear Engineering Fire Protection Coordinator (NEFPC) has been established, reporting to the Mechanical Discipline Supervisor.
2.4 NUCLEAR OPERATIONS DEPARTMENT RESPONSIBILITIES (1) Responsible for initiat'ing all physical work at Rancho Seco ~
throu AP.3)gh the use of the Work-Request (Nuclear Operation's Procedure (2) Responsible for making a determination whether a 10CFR50.59 safety review by the PRC is required. The Technical Support Superintendent may exempt an ECN from the safety review requirement detailed in QCI-5 in cases where it is clear that no nuclear safety significance exists. (Note: The PRC or the MSRC may reverse the determination.)
(3) Responsible for reviewing and approving all procedures used for testing plant modifications.
(4) Responsible for updating all plant procedures that are affected by plant modifications.
(5) Responsible for prov.iding any required training resulting from plant modifications.
(6) Responsible for determining if Verification and Validation (V & V) are required per AP.48, AP.49 and AP.53.
l (7) ECN, DCN, drawing transmittal control numbers and all new drawing numbers are issued by SDC. Line numbers for isometrics are issued 4109REV4 Page 3 of 24 Revision 4 Attachment 4
r NucI:ar Enginscring Proccduro
\v)CMUD NEP 4109 l l
by the MIMS Coordinator and the sheet numbers for isometrics are issued by SDC. Drawing numbers required at Rancho Seco shall be obtained from and recorded in SDC.
(8) Responsible for implementing EQ requirements as specified by the EQ program. An EQ Coordinator shall be established.
(9) Responsible for implementing the fire protection requirements specified in the Fire Protection Program Manual'and associated Nuclear Operations procedures. A Nuclear Operat' ions Fire Protection Coordinator (NOFPC) shall be established per AP.1, Responsibilities and Authorities.
3.0 GUIDELINES FOR APPLICATION OF ECN's, DBR's, DVR's, SA's-and DCN's 3.1 GENERAL ,
(1) The Design Engineer is responsible for perfonning a walkdown of plant areas which will interface with the intended change to ver.ify that drawings to be changed reflect the existing plant configuration.
(2) For ECN's marked "50.59 Yes," the Cognizant Engineer is responsible for scheduling a pfeliminary presentation of the planned change (s) to the PRC to provide early coordination with Nuclear Operations.
(3) Inter-discipline coordination of design documents shall be conducted, when applicable, by the use of the Interdiscipline Document Review Notice (IDRN) per NEP 4110 and/or coordination
- prints. Generally, specifications and other " text" type documents shall be coordinated through the use of the IDRN.
(4) System designators shall be as given in AP.42.
l 3.2 ENGINEERING CHANGE NOTICE (ECN)
(1) ECN's shall be issued for all configuration changes that require modifications to the permanent plant.
(2) Nuclear Engineering and Nuclear Operations Department manager-level approvals of an ECN are required for any of the
, following conditions:
(a) Changes to any Class 1 system or equipment or to any EQ item.
4109REV4 Page 4 of 24 Revision 4 Attachment 4
r~)CMUD i
V NucIsar Enginscring Proccdura NEP 4109 9 Class I systems and equipment and EQ items are identified in the Maintenance Information Management System (MIMS)
Master Equipment List (AP.42.)
(b) Changes to Security System or equipment.
(c) Changes to Fire Protection Systems or equipment.
(d) Changes to Class 2 systems or equipment which require ASME Code Inspection.
(e) Changes to Class 2 systems which will significantly affect the plant operation, performance, reliability or availability.
(f) Any plant change for which the estimated total cost of project
~
would exceed $10,000.
(g) Any changes to the plant which would alter the environment of any particular area (e.g. heat loads. HELB).
(3) ECNs are required for new computer system installations and hardware modifications to existing computer systems. ECNs are not required for " Software Change Only" work.
Software changes necessary to support an ECN require coordination with the computer engineering " discipline in accordance with AP.52.
(4) The minimum approvals required for an ECN requiring Nuclear Engineering staff approval are the Technical Support Superintendent and the lead Supervising Engineer from Nuclear ,
Engineering. These may be telecon approvals for emergency cases. i (5) ECN's are not required for " drawing change only" work which includes such things as correction of drawing errors, adding new 1 drawings or voiding old drawings where no actual field work is required. J (6) ECN's shall be issued for plant changes even though no drawings are available for DCN's. Examples of this are changes to vendor equipment for which the District has no drawings. The ECN shall !
state that no drawings are available for change.
(7) Open-ended, generic ECN's (e.g., ECN to remove unused, spare cables from cable trays) shall have an expiration date added by i the Nuclear Technical Support Superintendent. This expiration i date shall not exceed one year from the date of issue of the ECN.
4109REV4 Page 5 of 24 Revision 4 !
l Attachment 4 Emu 4ss c os
,a
\
V
)CMUD Nucicar Enginccring Proc dura NEP 4109 (8) Three types of ECN's are identified. These are (1) Singular-ECN, (2) Major-ECN, and (3) Sub-ECN.
9 Singular-ECN: The purpose is to provide a description of the overall project, is complete in itself, and contain no
. Sub-ECN's.
9 Major-ECN: The purpose is to provide a description of the overall concept for a major modification and is to be used in conjunction with detailed.Sub-ECN's. DCN's are not to be prepared against a Major-ECN.
9 Sub-ECN: The purpose is to describe a work package. The Sub-ECN will be scoped by the Cognizant Engineer in such a way that it is sufficiently complete so that all work encompassed by the Sub-ECN can be inspected, and if applicable, tested and put into operation as a unit. The appropriate DCN's will be identified with the Sub-ECN numbers. Sub-ECN's can also-be useful in scoping work packages such that construction of certain portions can begin early. Examples of Sub-ECN Work Packages are given in Attachment 8.6.
~
(9) If any Sub-ECN's are 10'CFR50.59 "Yes," then the Major-ECN must be ^
a 10CFR50.59 "Yes." Sub-ECN's may be 10CFR50.59 "No" even though the Major-ECN is a 10CFR50.59 "Yes."
(10) If a Sub-ECN is marked 10CFR50.59 "Yes," it may not be issued for work until the Major-ECN is issued for work.
(11) A Sub-ECN may be issued for work if one of the following conditions is met:
(a) The Major-ECN has been issued for work with all associated documentation approved; i.e., DBR, DVR, SA, 50.59 forms, etc.,
and the supporting documentation for the Sub-ECN is approved, or (b) The Major-ECN has been issued for document preparation, the Sub-ECN is marked 10CFR50.59 "No" and the associated DBR and DVR, if required, have been approved.
3.3 DESIGN BASIS REPORT (DBR)
(1) A DBR is a detailed design report which describes the proposed change (s),thedesigncriteriautilizedandtheimpactofthe change (s) on the plant. It includes or references supporting calculations.
4109REV4 Page 6 of 24 Revision 4 Attachment 4
CMUD Nuct ar EngineGring Proccdura ,,, 4,,,
(2) The DBR provides a unified and complete written design report for use by reviewers in " Design Review" activity required by QAP-2.
The DBR becomes part of the pennanent plant record.
(3) The DBR is prepared by the Cognizant Engineer with support from the various disciplines as required.
(4) If the DBR written for the Major-ECN is complete enough to provide sufficient detail for the Sub-ECN, a separate DBR is not required on both the Major-ECN and Sub-ECN,.but DBR applicability must be noted by the Cognizant Engineer by a memorandum to SDC.
(5) A DBR is required for all 50.59 "Yes" ECN's.
3.4 DESIGN VE'RIFICATION REPORT (DVR) .
(1) The DVR is a pre-printed form containing spaces for entering summary information on the type and scope of the verification performed, plus checklists for guiding the review. Signoff blocks are included for reviewers. Samples of the fonns are included as Attachment 8.4. A checklist to be used during the verification activity is included in Attachment 8.4 and is an integral part of the DY Report. ..
(2) The principal purpose for the E R is to provide design reviewers with a systematic approach to reviewing design changes, resulting in documented evidence of " Design Review" as required by QAP-2.
(3) A DVR is required for all singular ECN's identified as Quality f Class I, and/or 50.59 "Yes." A DVR is not required for a Major ECN identified as Q. C. Class I and/or 50.59 "Yes." As a minimum, however, a DVR is required for each sub-ECN which is so identified.
(4) The signed-off reports, including checklists, shall be part of'the permanent ECN file.
(5) Design verifications for work done by external A/E's and contractors may be furnished by them for part or all of a design package. These Design Verification Reports are furnished in conformance with SMUD QCI-11, and are filed in the corresponding ECN files. The DVR preparer shall indicate on the DVR Summary Fonn. Attachment 8.4, sheet 1, whether design verification has been accomplished by an external contractor, and whether it was total or partial coverage for the ECN in question.
4109REV4 Page 7 of 24 Revision 4 Attachment 4
_ _ _ _ _ _ _ -- _ . - - __ - - - - _ - - - - - -~ --
g Nuci:ar Enginccring Proccdura OCMUD ___
,,, ,,n, 3.5 DRAWING CHANGE NOTICE (DCN) (ALSO SEE NEP 4112)
(1) All physical changes to the permanent plant shall be documented on DCN's. DCN's shall be issued for all new drawings to be added to the system.
(2) For DCN's requiring I;uclear Engineering staff approval, the initial issues require, as a minimum, the approvals of the Design Engineer and the Discipline Supervising Engineer. For EQ review purposes, the Electrical Discipline Supervisor's signature on all electrical drawings constitutes evidence of EQ review. All piping isometrics labeled " ISOMETRIC" in the title block shall receive EQ review and such review shall be evidenced by the signature of the Electrical Discipline Supervisor and the lead discipline supervisor. All DCNs involving the systems.and/or_ components listed in Attachment 8.25 shall receive fire protection review by the NEFPC. The signature of the lead discipline supervisor shall constitute evidence that all DCN's in the package have been reviewed against Attachment 8.25, and appropriate fire protection review has been accomplished.
(3) DCN's shall not alter or expand the scope of the approved ECN.
(4) DCN Color Coding --
(a) Pink-Allsupportingdocuhntationhasbeenapprovedandthe drawing is issued for work.
(b) Yellow - Work is complete and the ECN has been closed out.
The DCN's have not been incorporated on the original drawings. The yellow prints reflect plant configuration.
(c) White - Originals of DCN's stored in SDC flat files are white. (Note also that preliminary prints are white. These shall be stamped "Information Only." Preliminary prints will
, be furnished by SDC only on request.)
(5) DCN's may be issued for work (pink) only if the related ECN is
" Issued for Work."
(6) If a system is to be put into service with a missing component (i.e., valve, instrument, relay, etc.), a revision to the DCN must be made to delete the component.
" Drawing Change Only" (DCO) DCN's do not require an ECN. However, (7) a transmittal number is required and is assigned by SDC. DCO's do not require a cognizant engineer's signature or a NEFPC review.
4109REV4 Page 8 of 24 Revision 4 Attachment 4
(m')CMUD Nuci:ar Engincaring Procsduro NEP 4109 3~.6 SAFETY ANALYSIS (SA)
(1) The SA provides documented evidence that a proposed change in the plant or procedures has been analyzed for its impact on the safety of the plant, as required by QAP-2.
(2) An SA is required for all ECN's classified as 10 CFR50.59 "Yes."
(3) The SA becomes part of the permanent plant record and is uniquely associated with an ECN or Sub-ECN.
(4) The SA shall be prepared by a licensing engineer utilizing the associated DBR as the basis for the analysis.
(5) The procedures for preparation and processing of an SA are detailed in QCI-5. The procedures include the preparation, review and signoff of the Safety Review of Proposed Facility Change (SRPFC) form. The SA and SRPFC for any ECN determined to be " Fire Protection-related" shall be reviewed by the NEFPC for fire protection concerns ottly (See Section 4.1[8][C]).
~
~
4.0 DETAILED PROCEDURES ,
4.1 ECN PREPARATION AND PROCESSING (See 45ttachment 8.7 for routing.)
(1) Originator / Cognizant Engineer (a) Develops concept and initiates the ECN. The standard ECN form, Attachment 3.1, shall be used. The Originator's name is
[
to be entered in the " Prepared By" space. The Originator l enters the name of the Cognizant Engineer if known. (Note:
l The Originator and the Cognizant Engineer may be the same person.)
(b) Provides a detailed written description of the proposal and other pertinent information to describe and illustrate how the proposal is to function, as well as illustrate interface (s) with existing equipment. Indicates what new compenents are required. See the example in Attachment 8.9. It is preferred (but not mandatory) that all paperwork attached to the ECN be no larger than 8-1/2" x 11".
(c) Lists the types of drawings affected by this change.
(d) Enters the work order number.
4109REV4 Page 9 of 24 Revision 4 Attachment 4
( CMUD Nuctaar Engincaring Proc; dura ,gg 4,n, (e) Detennines highest QA Class of system or component being modified.
(f) Provides the total estimated cost of the project, which should include:
0 Materials 9 Labor (Engineering, Construction, and Startup)
O Consultants (g) The Originator shall determine if the ECN is to be a Major-ECN with Sub-ECN's or a singular ECN.
(h)ItistheresponsibilityoftheassignedCognizantEngineerto review the Major-ECN when preparing Sub-ECN s for approval to verify that the Sub-ECN does not change and is included within the' scope of the Major-ECN. If a Sub-ECN does change the scope of cr is not included in the scope of the Major-ECN, then the Major-ECN must be revised and resubmitted for management approval. Sub-ECN's shall be listed on the Major ECN. .
(1) The Originator enters the J10D number, N/A if not related to a MOD, or OPS if originated in Nuclear Operations and not related to a MOD.
(j) Obtains supervisor's approval of the ECN content at this stage of development by the supervisor initialing in the Cognizant Engineer block.
(k) When an ECN is ready for approvals, submit to SDC.
(2) NEDC (a) Upon receipt of the ECN, assigns an ECN number and enters the number at the top of the form.
(b) Logs ECN.
(c) Returns ECN to originator.
NOTE: If a draft ECN is provided to NEDC, Engineering has 60 days to complete engineering reviews. After 60 days NEDC shall cancel the ECN number and notify Engineering.
4109REV4 Page 10 of 24 Revision 4 Attachment 4
n t
O 1OMUD Nuct:ar Enginacting Proccduro NEP 4109
.-,e==
(3) Lead Discipline Supervising Engineer (a) Confirms or assigns the Cognizant Engineer.
(b) Coordinates the ECN with supporting disciplines, including, EQ Review and Fire Protection Review.
(c) Signs and dates the ECN in the lead discipline box.
(4) Nuclear Project Engineer (a) Reviews ECN for staff approval requirements. Design changes to certain areas of Rancho Seco do not require Nuclear Engineering staff app'roval. Attachment 8.10 is a list of these areas. ._
0 If "No," check the appropriate box. ,
9 If "Yes," check the appropriate box and assign the lead discipline by checking the appropriate box.
(b) Determines if a DBR is required and checks the appropriate box. (A DBR will be required if the ECN is marked 10CFR50.59 "Yes." after Technical Support Review.) -
(c) Confirms that the Mod numb r assignment is consistent with the Living Schedule.
(d) Determines if Design Verification is required and checks appropriate box.
(e) Signs and dates the ECN.
(f) Forwards ECN to Manager of Nuclear Engineering.
l (5) The Manager, Nuclear Engineering, reviews for correct system designation, that the requirements for a DBR and design verification are appropriate. Approval of the ECN is indicated by signing and dating in the appropriate box. The ECN is then forwarded to NEDC for further processing. l l
t i
4109REV4 Page 11 of 24 Revision 4
( Attachment 4
m I
)OMUD Nuclear Enginaaring Proccdura NEP 4109 l (6) SDC (a) Logs ECN (b) Transmits ECN to Nuclear Operations Technical Support Superintendent.
(7) Technical Support Superintendent (a) Reviews for 10CFR50.59 applicability and checks appropriate box on form. If 50.59 "Yes," obtain a log number from QA and add log number to ECN form.
(b) Prepares a justification memorandum for the 50.59 determination. The memorandum shall be.addres. sed to the Manager, Nuclear Operations.
(c) Assigns Nuclear Operations Designated Engineer, (NODE). For -
ECN's originating in Nuclear Operations, there will be no N0DE assignment.
(d). Reviews for verification and validation (V & V) applicability and checks the appropriate box. This determination shall be in conformance with administrative procedures AP.48, AP.49, -
and AP.53. -
(e) Signs and dates the ECN and transmits ECN plus memorandum to Nuclear Operations Manager.
(8) Nuclear Operations Manager and Staff (a) Review Scoping.
(b) Review for Testability, Maintainability and Training.
(c) Review 50.59 and V & V applicability.
(d) If the ECN is approved, sign and date the ECN and return the ECN to SDC.
(b) Issue and distribute ECN.
4109REV4 Page 12 of 24 Revision 4 l
Attachment 4 1
OWN -- _ _ _ _
O Nuclear Engin:aring Proc dura GCMU= NEP 4109 (10) Disapproving, Voiding and Revising ECN's (a) Disapproving ECN's 9 An ECN should only be " Disapproved" by supervision if the concept or change is not desired and there is no intent to change the plant. " Disapproval" is indicated by checking the appropriate box, stating the reason for disapproval on the ECN, signing, and dating. Errors or other discrepancies in the ECN are corrected by revision to the ECN and do not require disapproval.
9 Disapproved ECN's will be returned to SDC. SDC will send a copy to the Originator and Cognizant Engineer and will void the ECN. Disapproved ECN's cannot be revised or reopened under the same ECN number.
(b) Void ECN's 9 ECN's should be voided when no work is to be done. The Cognizant Engineer will notify SDC by a memorandum which
- - is to include the reason (s) f6r voiding the ECN, and will void all related documents. _,
2:
(c) Revised ECN's 9 If revisions are required to an ECN before any approvals are obtained, the ECN will be returned to the Cognizant Engineer for correction and reprocessing. Corrections shall be made by submitting a new original or drawing a single line through the error and initialing the correction (no correction tape or fluid will be used).
9 If revisions are required after an approval signature is obtained, the ECN is returned to the Cognizant Engineer via SDC. The Cognizant Engineer then makes the revisions ,
I and reprocesses the ECN for approval as Rev. 1, 2, 3, etc.
9 ECN revisions require the same approval processes as the origina. ECN, and the distribution is to be the same as for the original ECN.
9 If an ECN change does not alter any accompanying DBR or SA, the Cognizant Engineer will issue a memo to SDC stating that the DBR is still applicable. The licensing engineer will issue a memorandum to SDC covering the fact that the existing SA is still applicable. :
l 4109REV4 Page 13 of 24 Revision 4 '
Attachment 4 !
1
_a
m GCMUD Nuclear Engincaring Proccdura 4.2 DBR AND DVR - PREPARATION AND PROCESSING (1) DBR preparation is the responsibility of the Cognizant Engineer.
The typical routing is shown in Attachment 8.8.
(2) The Design Basis Report, Attachment 8.3, may be used as-is if the text fits in the allotted spaces, or if "See Attached" is entered. It is also acceptable to provide a typed DBR without using the form. However, all information shown on the form shall be furnished in the typed DBR. The last sheet shall contain the nine signature blocks. All sheets including " Attached" sheets shall have as a heitding the information required at the top of the DBR form (i.e... Discipline, ECN No., etc.).
(3) The technical content of a DBR is of prime importance, as this is the only comprehensive document covering the details of a modification to the plant. The descriptive material will be thorough, complete and in detail. A writer's guide is given in Attachment 8.11. Calculations shall be in accordance with Nuclear Engineering Procedure 4106.
(4) The. Cognizant Engineer signs and dates the DBR and obtains approval of the appropr;iate interfacing discipline supervisors.
(5) When required by an ECN, desige verification shall be performed.
- This shall be documented using the DVR fom and checklist. A sample is shown in Attachment 8.4.
(6) The Review Engineer (s) performing design verification shall use the checkpoints given in Attachment 8.4 as part of the review process, and shall execute the form per the instructions in Attachment 8.4. The checklist shall be completed and signed.
(7) Upon satisfactory completion of the DBR review, the Review Engineer signs the DBR and forwards the DBR and DVR to SDC.
(8) SDC logs the DBR and DVR and transmits both to the NODE.
(9) After review, the NODE signs and dates the DBR. The NODE then returns the DBR and the DVR to SDC.
(10) SDC transmits the DBR to licensing for review and approval. An information copy of the ECN and the original DVR are also sent.
4109REV4 Page 14 of 24 Revision 4 Attachment 4 suuomsacas
o)CMUD Nuclear Engincaring Proccduro ,g, ,,,,
(11) After review, the Licensing Engineer signs and dates the DBR and returns the DBR and DVR to SDC.
(12) Revisions to DBR's shall be documented by change bars.in the margin opposite changed text and specifying the DBR revision number at the top of the page, as well as the ECN and ECN revision number. If changes are made prior to any approval signature, no change to the revision level is required.
4.3 DCN PREPARATION AND PROCESSING (ALSO SEE NEP 4112)
(1) The Cognizant Engineer prepares DCN's or has DCN's prepared by appropriate Design Engineers to implement modifications.
(2) DCN's shall be prepared for all drawings that will be affected by the change outlined on the ECN. See Attachment 8/12 for a list of drawing categories that are maintained by the Configuration Control system.
(3) If a design change requires new drawings to be created or vendor prints to be added, the drawing number shall be obtained from SDC. It is the Supervising Engineer's responsibility to assure the use of correct numbers. Document numbering is given in NEP 4103. .
(4) The Design Engineer or Cognizait Engineer sh'all determine whether or not field inspection is required for each DCN and mark the appropriate block on-the DCN.
(5) The Cognizant Engineer shall obtain new identification numbers for new components (i.e., valve and line numbers, instrument numbers, circuit numbers, pump and tank numbers, etc.) from the responsible custodian as shown in Attachment 8.5.
(6) The Cognizant Engineer shall approve new DCN's and obtain remaining approvals or route through SDC for approvals. DCN's shall be transmitted to SDC through the use of the Transmittal Sheet (Attachment 8.15). In the case of " Initial . Issue" DCN packages, a package cover sheet (Attachment 8.14a) with the upper part completed, will be submitted with the DCNs and transmittal sheet. If the drawing oackage is incomplete, the related information required on the cover sheet shall be furnished.
NOTE: An " Initial Issue" DCN package is defined as the first DCN package ever submitted against a specific ECN.
4109REV4 Page 15 of 24 Revision 4 Attachment 4
, mass ces j
A)CMUD V
Nuclear Engin:cring Proccdura NEP 4109 (7) DCN's for ECN's not requiring Nuclear Engineering Staff approval:
(a) The Cognizant Engineer shall obtain the approval of a Nuclear Operations Senior Engineer. Signature shall be in-the
" Supervising Engineer" Block.
(b) The Cognizant Engineer shall transmit the DCN's to SDC using the Transmittal Sheet and shall include the DCN Package Cover Sheet (Attachment 8.14a).
(8) Revisions to DCN's:
(a) Revisions to a DCN that do not alter the original intent of the change as authorized by the ECN or affect the safety analysis if a 50.59 review has been done, only need the
~ ~
approval of the Design Engineer and the S~upervising Engineer.
The Cognizant Engineer is to be informed of the change. If the revision changes the concept, the Cognizant Engineer shall -
sign the revision, and EQ review and approval are required.
. Revisions to DCNs that require initial fire protection review per Attachment 8.25 shall be reviewed and approved again if
.the concept has changed. Telecon approval of the DCN by the Cognizant Engineer is acceptable.
c (b) Revisions to DCN's arising from problems encountered during l construction or startup shall be processed in accordance with l this procedure. The reason (s) for the change shall be
- documented. Revisions to DCN's that will result in the ECN becoming a 10CFR50.59 "Yes" cannot be issued on pink until the revised ECN is issued for work. The Supervising Engineer is responsible for making the determination.
(c) Revisions to DCN's that alter the content of the Safety Analysis (SA) cannot be issued on pink until the SA is revised and approved and a safety review is completed. The
! Supervising Engineer is responsible for making the
- determination.
l (d) Revisions to DCN's that alter the contents of the Design Basis Report (DBR) cannot be issued on pink until the DBR is revised and approved. The Supervising Engineer is responsible for j
making the determination.
l l
l 4109REV4 Page 16 of 24 Revision 4 Attachment 4 i
i (m)CMU' v
Nuclear Enginscring Proccdura NEP 4109 (e) SDC will make a file copy of the DCN and return the original to the requester. SDC will issue a letter revision to the l original DCN number to signify that it replaces the original. !
When the alpha revisions on DCN's become unreadable, they may be incorporated and a new DCN produced showing the latest configuration and labeled "New Original Submitted." However, any new changes will continue the alpha designations sequentially.
(f) The Design Engineer shall obtain the Supervising Engineer's approval, which may be by phone. If phone approval is obtained, the Design Engineer should initial for the Supervising Engineer on the DCN and enter "Telecon with . the date of the telephone approval, and "By .
" "If the Supervisir.g Engineer det. ermines that the revision (s) affect conclusions reached during the initial Design Verification review, a new DVR shall be executed, and this fact rhall be stated in the space provided on the DCN transmittal form. Attachment 8.15. The Supervising Engineer.
.is responsible for the new DVR and for assuring the proper completion of the DCN transmittal form. SDC shall not issue
- new pinks until a fully executed DVR~is received. Phone
- approvals of the DCN are acceptable.
(g) The Cognizant Engineer will- return the revised DCN with a transmittal form (and DVR if applicable) to SDC.
(h) The Cognizant Engineer shall clearly indicate on the t Transmittal Sheet, Attachment 8.15, changes being made and the reason (s) for any change to the package. Reference should be made to any applicable Field Problem Reports.
(9) DCN approvals:
l All signatures on DCNs shall also be dated.
4.4 SA PREPARATION AND PROCESSING (1) An SA is required when an ECN is marked 50.59 "Yes."
(2) When a DBR for a 50.59 "Yes" ECN is submitted by SDC to the Licensing Engineer (with a copy of the ECN), the Licensing Engineer prepares an SA and a Safety Review of Proposed Facility Change (SRPFC) forin. This activity is covered in detail by QCI-5. The SA and SRPFC for ECNs determined to be " fire protection-related" shall be reviewed by the NEFPC for fire protection concerns only.
l i
4109REV4 Page 17 of 24 Revision 4
' Attachment 4 m.. ...
,rh
()CMUD Nuclear Engincaring Procedura ,g, ,,,,
(3) When the SA and the SRPFC are approved, the Licensing Engineer returns the documents to SDC. The Licensing Engineer is responsible for obtaining the signature of the Manager, Nuclear Engineering on the SRPFC.
(4) SDC notifies the Cognizant Engineer that the documentation is ready for (See Section 5.0, " Review, Approval, presentation to the PRC.and Issuing of DCN Packages" for succeedin 4.5 PREPARATION AND PROCESSING ECN'S AND DCN'S FOR RANCHO SECO. SWITCHYARD (1) ECN Requirements:
(a)'An approved ECN is required for all changes to Rancho Seco Switchyard. ,
(b) In addition to the ECN approvals required by Section 4.1, switchyard-related ECN's shall be approved by the Manager of the Engineering Department, the applicable Engineering Department Supervising Engineer and'the Manager of Transmission and Distribution Operations, as applicable under the guidelines of Section 4.1. For Switchyard ECN's, the
- standard Rancho Seco ECN form shall be used with signature blocks added to the form (by a stamp) for the signatures of the three additional approuls required. ~
(c) The ECN form shall be stamped " Rancho Seco Switchyard."
(d) Switchyard ECN's shall be initiated, routed for approval, and distributed in accordance with Section 4.1 except that the Engineering Department Manager, the Supervising Engineer over substation design and the Manager of Transmission and Operations Distribution Department shall be added to the routing and approval sequence, as required.
(e) The ECN shall designate the group that will perform the actual field work, i.e., Substations, Nuclear Operations, Meter Shop, Line Division, etc.
(f) A Rancho Seco Work Request shall be implementel prior to the start of ='; P.ancho Seco switchyard modification work to be ;
performed by Rancho Seco personnel. The Work Request shall l
reference the ECN.
(g) All other procecural requirements cf Section 4.1 are )
applicable to switchyard-related ECN's.
4109REV4 Page 18 of 24 Revision 4 l l
Attachment 4 l suuo.t4ss oss i
U CHUD
! Nuclear Enginscring Proccduro NEP 4109 (2) DCN Requiremer,ts ,
(a) DCN's shall be issued for all changes to switchyard drawings.
9 The " Rancho Seco Switchyard" DCN fonn shall be used for changes to switchyard drawings. See Attachment 8.18.
9 If a Rancho Seco plant system drawing requires changing as a result of a switchyard drawing change, the standard Rancho Seco DCN Decal shall be used to effect the change to the plant drawing.
(b) DCN's to Rancho Seco switchyard drawings require the approval of the applicable Engineering Department Group Supervisor, the Nuclear. Engineering Electrical Group Supervisor, and the Manager of Transmission and Distribution Operations.
(c) The DCN's shall be prepared using the standard Service Area DCN format.
(d) A Rancho Seco Switchyard Route Slip, Attachment 8.19, shall be
-used to package related.DCN's.
(3) Processing of DCN's for Switchyard Drawings (a) The originator prepares the DCN in accordance with standard ECC practice.
. (b) The DCN package is transmitted to the Engineering Department Substation Design Group Supervisor for approval and entry into I
the system through ECC.
(c) ECC numbers and logs the DCN package.
(d) The DCN package is routed to the Manager, Nuclear Engineering, who then routes the DCN package to the Electrical Group Supervisor, Nuclear Engineering, for review and approval.
(e) The DCN package is routed to the Manager of Transmission and Distribution Operations for review and approval.
(f) The approved DCN package shall be returned to ECC to be issued for work.
(g) If the work is to be perfonned by Nuclear Operations, then ECC shall forward the original DCN package to SDC for distribution to the Rancho Seco Plant Scheduler.
4109REV4 Page 19 of 24 Revision 4 Attachment 4
Nuclear Enginscring Proccdura O" CMU= NEP 4109 (h) If the work is to be perfomed by one of the Transmission and Distribution work groups, ECC shall forward the original of the DCN package to the Transmission and Distribution Department Coordinator who will arrange for getting the work accomplished by the appropriate work group.
(1) A copy of the DCN package will be sent to the Plant Scheduler with a notice that the work will be performed by a Transmission and Distribution work group.
(j) When the work is performed by Nuclear Operations, SDC shall mark the original " Work Complete" and transmit it to ECC for ~
updating of the original drawings.
(k) When the work is performed by a Transmission ~and Distribution group, it shall be the responsibility of the Transmission and Distribution Coordinator to mark the original " Work Complete" and transmit it to ECC for updating the original drawings.
(1) When a Switchyard DCN is taken out for revision, and a "new
. original" is turned in in it's place, it should be stamped
" Switchyard DCN" and the same signatures that were on the first submittal should be obtained again for' the second ..
original that is turned in_for replacement.
5.0 REVIEW, APPROVAL, AND ISSUING DCN PACKAGES 5.1 GENERAL (1) The review and approval steps for DCN's are separate from those for the ECN, DBR, and other " authorizing" documents. This section of the procedure covers the processing of the authorizing documents, DCN reviews and the issuing of " pink" construction DCN's. The complement of authorizing documents and review steps vary as a function of the nature of the change. Attachment 8.21 suunnarizes the requirements for all ECN's. ;
(2) After supervisory approval, DCN reviewers consist of the N0DE and/or Construction (according to work assignment). In the event l that a NODE is not assigned and physical work is to be done by Nuclear Operations, there are no further raviews of the DCN's.
1 (3) The Cognizant Engineer is responsible for preparing MEL input sheets and transmitting them to the MIMS coordinator. The input sheets shall be transmitted via a memorandum per Attachment 8.17.
Engineering detailed schedules shall include this step where 4109REV4 Page 20 of 24 Revision 4 Attachment 4
o
()CMU= NucIsar Enginacring Procaduro NEP 4109 a
applicable. Submittal shall be completed prior to construction turnover to startup.
5.2 DCN REVIEWS (1) For initial issue packages, SDC prepares a set of "Information Only" DCN Prints. Copies are transmitted to Planning and Scheduling and to the N0DE, using the cover sheets shown in Attachments 8.14a and 8.14b. SDC notifies the Cognizant Engineer that the DCN's have been sent, indicating the required response date.
(2) Planning and Scheduling will review the DCN package and designate on the Package Cover Sheet (Attachment 8.14a) whether or not SDC should forward the package to NE Construction based on work assignment. Also, the " pink" DCN distribution wil1 be specified.
Planning and Scheduling will notify SDC at any time this distribution changes using Attachment 8.14a. If NE Construction is specified for review, SDC will transmit the package to them using Attachment 8.14c.
(3) If changes to the initial issue DCN package are deemed necessary
- . by the Cognizant Engineer before review comments have been completed. SDC will notify the reviewers to discard all review '
copies. The package will be returned by SDC to the Cognizant l
Engineer and the initial issue.: process will start over.
(4) If comments are not received in SDC by the required date, SDC may issue the package if all other authorizing documents are in SDC with approvals. If comments have been received from only one of the two reviewers by the required date, the Cognizant Engineer is required to resolve only those comments. Upon resolution of the comments, the Cognizant Engineer returns the signed cover sheet (s) to SDC. The DCN package can now be issued for work (pink).
5.3 PROCESS FOR ECN'S CLASSIFIED AS 50.59 "Yes."
(1) SDC notifies the Cognizant Engineer that all necessary authorizing documents are ready for presentation to the PRC by sending a copy of the ECN and the originals of the DBR, DVR, SA, and SRPFC to the Cognizant Engineer. The Cognizant Engineer schedules and makes a PRC presentation, utilizing these documents. The succeeding steps are detailed in QCI-5.
l 4109REV4 Page 21 of 24 Revision 4 Attachment 4
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n (G')CMUD Nuclear Enginscring Proc 3duro NEP 4109 5.4 PROCESS FOR ECN'S CLASSIFIED AS 10CFR50.59 "NO."
(1) The ECN, (and the DBR if required) shall be prepared, approved, and sent to SDC in accordance with Section 4.
(2) The Cognizant Engineer prepares the DCN's and Package Cover Sheets in accordance with Section 4 and forwards the DCN's, the transmittal form and Package Cover Sheet (s) to SDC.
(3) DCN reviews are performed in accordance with Section 5.2.
6.0 INITIATION OF WORK 6.1 After receipt of a set of pink construction drawings from SDC, the Plant Scheduler authorizes the initiation of work by issuing Work Requests. This activity is in conformance with AP.3.
6.2 Nuclear Engineering shall participate in a pre-construction " Job" ~
walkdown, to be scheduled by Construction.
7.0 COMPLETED WORK-CLOSE0VT OF DOCUMENTS 7.1 As construction activities are completed for an ECN (or sub-ECN), the .
ECH is released from the construction group to the Nuclear Operations startup engineer, in conformance wi4h AP.4?;. Engineering is required to conduct a walkdown, per AP. 44, to check for gross deviations from design intent. An engineering walkdown is required for all ECN's, regardless of origin. Walkdowns shall be conducted by qualified persons familiar with the modification. The methods given in Attachment 8.16 shall be followed. Guidelines for performing walkdowns are as follows:
(1) The checking is not intended to cover weld details, tolerances, or l details of dimensions.
(2) Utilize appropriate DCN's for the checking process and " yellow line" them as checking is accomplished. The " yellow-lined" DCN's need not be retained.
-(3) Check to see that all equipment is properly installed and in the correct location.
(4) Check to see that all piping and tubing are routed per print.
(5) Check to see that all supports for piping and tubing are of the correct type and located per print.
4109REV4 Page 22 of 24 Revision 4 l
Attachment 4
CMUD Nuclear Engin:aring Proc:duro ,,, ,,,,
(6) Check to see that all piping and tubing are of the correct size.
(7) NOTE: A post-startup walkdown may be conducted to cover items such as cable teminations and wiring at equipment and panels.
7.2 When startup testing is completed, the equipment and/or system is l released to Nuclear Operations in confomance with AP.44.
7.3 The Operations Superintendent defines and performs a validation exercise, if required by the ECN, per AP.53.
7.4 The pit,nt scheduling t.ffice initiates closing of an ECN notifying SDC that all work requests against that ECN (or sub-ECN) are closed.
7.5 SDC routes the ECN (sub-ECN) original for signatures by Startup, the N0DE and the Cognizant Engineer per AP.44. These signatures and dates shall be in the " Work Complete" boxes on the ECN.
7.6 SDC stamps the DCN's " Work Complete" after receipt of Nuclear Operations release per AP. 44.
7.7 The Regulatory Compliance supervisor updates the process standards as required. .
. 7.8 SDC issues " yellow drawings" to the: Control Room and other stick files. Voided yellow drawings will only be issued to SDC.
7.9 The Nuclear Operations Training Coordinator completes required training necessary to familiarize personnel with changes made by the ECN. Also, a log is maintained by ECN number to verify for audit purposes that an ECN was reviewed and appropriate training was either conducted or not required.
7.10 For ECN's which are 50.59 "Yes," SDC sends originals of the DBR's, SA's, and SRPFC sheets to QA.
7.11 Drafting updates original drawings and SDC issues revised aperture cards.
7.12 SDC files all ECN's and DCN's which are " Work Complete" after drawing updates. DVR's and package cover sheets are retained a.long with the related ECN's.
8.0 ATTACHMENTS (see succeeding pages) 4109REV4 Page 23 of 24 Revision 4 Attachment 4 l
( CMUD Nuclear Enginscring Proc: dura , ,
APPROVED: s ta b * [6 i2_f Date Manager,Nc1agngineering
/hl (NYs -
Maha~ger ' Nucle 1tr Uperations
/W7/2b
/ / Date A yt ' &f fha L' 5
/ /
ff(I Date ager, Engin ering Department W
% Manager, Quality Assurance w /s/84 Date l
4109REV4 Page 24 of 24 Revision 4 Attachment 4 se-uss oss _ _ _ .
r NEP 4109 ATTACliMENT 3.1 EC"c- "
$ SMUD 5AcRaassNTO asusesCIPAL UNTY Dismcf Shost of o l
ENGINEENNG CHANGE NOTICE m m.mmen ., . - - , ;
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O THE PCLLOWING SYSTBm51 WILL M APptC11D BY TMS CMAseGE l i
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I I ll: MEASON POR CHANGE I I N 08 O , -
- smoutaa naamm I sus i i
w A We 6 asm frB N Om staaff NTW. 6 m m om M munOminatuse TO COesmLETWLY SWCmIEE AMS lbkHffUlaTg esow maasses is 70 pusseftom as wmL as ILLusTaste arTgim4Cassa wrre smstess acuspeserf neceCATT waa? wtw
_ _ _ . ang meDMueW. vomeg 08 Samousses asegCTW amo esTunats TOTak Cas? 08 mmOJW' .
- 1. Wir Triu QF ECN:
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NEP 4109
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ATTACHMENT 8.2
' OELETED
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Attachment 4 M
l ATTACHf1ENT 8.3 1 i
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" SidMD r DESIGN BASES REPORT
- mm
=M nasosa e anse on . sa:n a m samart m oscenas
- --e= 1 asan, g
- t. MAW'OR OF DESGN CHANGE.
- n. DESIGN CNTENA USED:
1
- m. CALCULATIONS & DEstGN INFORMATION:
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1 N. FAILufE MODES. l C Tle CHAME DM NOT AMECT CONTRG ROOM IISTIEmedTATION
, O 795 CHANE AMBCTs CONmtL ROOM IISmuseffATION. SE ANALM ,
,. - - s V. NNN .
. L vi. speCw.oPuRATING naoumeMsNTs. ,
V5. VWWRCATION CM i,
vu. CoMnests.
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l sessana aan at M PRovats:
i emmena enn onwnnensm, oma NABee SAM Z -_ sam emmenn sement man men esem aan smaana asemanos semanns emism enn uneens ese one Attachment 4 .
me nsses oss
_ . _ . _ . _ _ . _ W . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ , . _ _ _ _ . _ . . _ . _ _ _ _ _ - . - - . - _ - - _ - - -
NEP 4109 AllACHMEN1,8.4 INSTRUCT [0NS FOR USING -
THE DESIGN VERIFICATION FORM .
- 1. GENERAL A. The form is to be us&d for all singular ECN's and sub-ECN's marked "D.V. Requi red. "
B. The form shall be retain,ed.by SDC in the ECM file.',
2.. SPECIFIC INSTRUCTIONS A. Sheet 1, DVR
- 2. ECN NO: Enter the ECN or sub-ECN.No. for which this DVR is applicable. A DVR cannot be applicaole to more than one Mod. or ECN/sub-ECN. If a design verification is perfonned encompassing more than one ECN/sub-ECN, initiate a fonz .for each ECN/sub-ECN and in the "Related ECN's*' space, enter the numbers of the -
ECN's/sub-ECN's: reviewed. SOC will file originals for all DVR's in the raspective ECN/sub-ECM files.
- 3. METH00: Check the appropriate method (s) used for verification.
I 4. DOCUMENTS REVIEWED: List the specific documents selected for review. Identify the document numbers and titles plus revision number. Note that not all i documents necessarily need review. The extent or depth of review is determined by the reviewer (s) and is a function of the complexity and importance to safety.
It is the responsibility of the Cognizant Engineer to l
prepare copies of documents to be reviewed and distribute to the reviewer (s) prior to meetings.
- 5. If verification is by alternate calculations or qualification testing, documentation shall be in i appropriate files for review / audit purposes. If the verification is by qualification testing, the methodology described in ANSI 45.2.11-1974 shall be followed. .
- 6. SUhMARY OF REVIEW: A summary of the method (s) used to review the documentation. This would include the use of the basic check points, method (s) of presentation by the Cognizant / Design Engineer and any cross-checking of data inputs an(er_rP+g 4 This should also identify any
' discrepancies and acETon items.
NEP 4109 Attachment 8.4 (cont'd) _
- 7. CONCLUSIONS: A statement as to the acceptabilit.y of the design and any . stipulations regarding cl'ose cut of action items.
- 8. The balance of the entries are self-explanatory.
- 3. Sheets 2, 3, 4 (checklist)
.1 . The Review Engineer shall determine which, if any, of the checkp.oints are not applicable and enter an (X) in.
the N/A column.
- 2. The initials of the Review Engineer after each applicable checkpoint shall constitute evidence that the design satisfies that requirement.
- 3. Enter any additional items reviewed in Section C, "A001TIONAL ITEMS, REVIEWED."
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- 4. All reviewers sha$1 sign and date in the spaces provided. .
E .
I t
l Attachment 4
NEP 4109 Attachment 8.4 (cont'd) Sheet 1 se 1 y e S SadL.T a no - e ===se RANCMC SECC NUC'. EAR GENE'GG S A !CN
- DESIGN VS!MCATICN TER~
uca no.
nes u =ra =s_.n -
usTHCC: C :#Crvcau. *Evttw :::,;fg:mA::n Ig ,uc
- trescisc:Panaav steview : x,ERNAM "M **1*ON .
DOCUMENTIS*. REVIEWED:
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- ""W 08' Mview w asumme mussst / neegsa: ,
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I CONC'JJSiONS: !Anserr Jesurser 3tsertst / nessest ensues C. O r z- *== w
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NEP 4100 Attachment 8.4 (conL'd) Sheet 2 3
l s w 2 QF 4
. MOD NO. .
"8* -
DESIGN VERIFICATION REPORT BASIC CHECK POINTS Reviewer's
, .N/A inrtials A. 19 Basic checkpoints from ANSI 45.2.11-1974 Seedon 6.3
, 1. Design inouts were correctiv selected and incor-porated in the design. (Ref. ANSI 45.2.11, Sec- -
non 3.2)
- 2. Astumpoons necessary to perform tne coegn ac-tivity are adequately described and reasonable.
Also where necessary, deogn assumpoons are
__ idendsed for subsecuent revenficeoon e tne .
dessiled demon acave are completed. *
^
- 3. The acoroonate cuality and quality aneurance re-ouremems are specified. .:
4 The acolicable codes, stenderds and reguistory re-cuirements, including issue and addenda, are pro- .
perly idemified, and their reguremems for design '..
have been met.
4 4
i 5. Acolicable conesucson and opersong excenence . _ _ . . _-
have been canadered.
i 6. Desgn enerface recuremems have been senefied.
- 7. Apprognate deogn method has been used.
- 8. The deogn output is reasonable compared to the input.
- 9. The specified parts, eatsoment and processes are sumable for the required appliceoon.
- 10. The specifled meterials are comoedbie with each ,
other and with the deogn armronmemel condi-tions to wteen the mesonal we be exposed.
- 11. Adequete mentenance features and reguremems are specified.
Attachment 4 m
M
NEP 4109 Attachment 8.1 (cont'a; Sheet 3
- ' -swerr 3 c.= a '
- -- Reviewer's N/A Inrtials
- 12. A- = ":- y and emer previsions for mantenance g
.nd repair have 'ceen ine:uced. ;
l .
- 13. Accessbjltty for expected l$1 curing plant life has l been inrJuoec. .
- 14. The design has proceny conadered radianon ex-l cosure to me cualic and ciant oorsonnet. ALARA i program requirements have been met. -
- 15. Adecuate acceptance cntena nave oeen included ; .,
i in oomgn occuments to asiow venficanon tnac demon recuremems have been senofocurey ,
accompilohed.
- 16. AM- W and subseousnt genodic test recuremems have been specineI where ~
m ..
! 17.~ Adequate her,# 4, storage, M-a4 ar shipp-
. ing recuremems have been snecrned (Also see NE8 4205 "*urchase Recues:"). '
- 18. Adequate idermffcaten recuremems are soec:ffed.
--- ~ ~ ~
. 19. Recuremems fot record precaranon, review, ao-
- preval and rotonnon are adecumery specrfled.
l B. The fosowing checicpoims are Rancho Seco 9=
1
- 1. HELBA program recuremems have been met.
I '
! 2. The Nuclear Engineering Fire Protection Coordinator (NEFPC) review is complace.
- 3. The design has been reviewed for Human Facture l engineering.
A Pinoding poundel has been adeousisiy canadered.
l E. Irnoect on IDADS hee been canadered, including l software changes.
l
- 6. Seismic II.over-seismic I demon has been l considered.
Attachment 4
. , . . " " * * ."" -_ _ ._ _._ __ _____ . _____ _ . _ _.- . _ _ . _ _ _ _ _ _ _ _ _ _ __ w
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NEP 4109
' Attachment 8.4 (cont'd) g Sheet 4 ,
MOD NO.
E'CN NO.
-- Reviewer's N/A initi&ls
- t
- 7. RG t.97 impac: reviewed. _
l
- 8. NUREG 0737 commitment imosc: reviewec. !
- 9. SPOS data base impac: reviewed.
- 10. Impac: on Emergency Response Plan has been cons 4ered. i l
- 11. Impact on Emergency Rosconse Capabilities has 3 been conocerec. j .
-- 12.- E4%... Regwements have been sensfied.
C.-m iteme Reviewed * - -
. 8 e
q MY e
P e
D. Approveio I
mesumer ame Asseur .isse Ass ==. an. --tta- '-^^' ,;.s
NE!' 4109 AilACHMENI 8.5 .
. RESPONSIBLE GROUPS FOR _.
Specialized Lists, Logs, Schedules, Etc.
Drawing Title and Number Descrintion Custodian E-1008 Raceway Schedule Nuclear E-1010 circuit Scnedule Engineering Electrical E-1011 Load Design Data Sheets Group
- E-1012 Motor Operated Valve Data Sheets M-853 Line Designation List '5ee AP-42 M-870 Specifications for Piping Design See AP-42 ,
M-871 Master Valvec List See AP-42 ;
' M-872 Valve De'signat' Ion List See AP-42 ,
M-873 Motor Operated 4'a lve Data a
Master List See,AP-42 M-878 System Transients for Class I Pipes and Valves See AP-42 Hanger Orawings ,, See AP-42 l
l Equipment Identification Numbers See AP-42
- 10000-99999 Isometrics MIMS*
NOTE: The custodian shall have the system, the name of the requestor,
! and the ECN prior to issuing any identification numbers per this Attachment.
- Sheet numbers for isometrics are issued by SOC.
I I
Attachment 4
- e R m i0i SB 4 . 1 _ _ _,_ _
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' ~
NEP 4109 1
AIIACHMENT 8.6
~
. EXAMPLES OF BREAKOUT OF A MAJOR-ECN INTO SU8-ECN'S
- 1. If the Major-ECN requires complete fire protection in a compartment, 1.e., water, CO2 and Halon, then the Sub-ECN's could be as follows:
One Sub-ECN for the complete water system which can be installed, inspected, tested, and put into operation.
One Sub-ECN for the complete CO2 system which can be installed, inspected, tested, and put into operation. .
One Sub-ECN for the complete Halon' system which can be installed, inspected, tested, and put into operation. .,
- 2. If the Major-ECN requires the installation of two hundred (200) feet of piping and three hundred (300) feet of raceway and cable for the auxiliary feedwater system then the Sub-ECN(s) could oe:
a Sub-ECN for installation of the piping, but connection to the
, , operating system is not medg. Only inspection will be performed.
^
. a Sub-ECN for installation of the raceway and cable, but no.
! termination is made to the operating system. Only inspection will be performed. . .
i a Sub-ECN for final mechanical connection of the piping to the operating system and final inspection, testing, and operational verification will be performed.
- a Sub-ECN for final electrical terminations to the operating system and final inspection, testing, and operational i verification will be performed.
6 l
l l
i '
l i
Attachment 4 i - Page 35 m_
NEP 4109 ATTACHMENT 8.7 FLOW CHART ECN PROCESSING ORIGINATOR NEDC FOR ECN NUMBER 4
LEAD DISCIPLINE SUPERVISING ENGINEER
- NUCLEAR PROJECT ENGINEER NUGAGER NUCLEAR ElGINEERING E
SDC FORWARDS TO TECH SUPPORT 2
TECH SUPPORT SUPERVISOR 1
i NUCLEAR OPERATIONS MANAGER AND STAFF l
l SDC TO PROJECT ENGINEER l
i
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VOIDING ECNS MA092 3ee.c3,,ne 4 Page 36
NEP 4109 ATTACiMEtiT 3.8 4
FLOW CHART 08R's ,
J COGNZANT ENGINEER PREPARES OSR AND 08TAl'NS OlSCIPLINE APPROVALS l
T REVIEW ENGINEER SIGNS 08R ADOS DVR f
. . . ~ REE -
1 en .
4 .a y
NODE REVIEWS / SIGNS 1P 19S (ATTACHES COPY OF ECN) 1 I LICENSM , , _ , _ , ,
REVIEWS Ale SIGNS 08R ggg _ .
Attachment 4 Page 37 REvf01@n 4
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5 CMD sacnaasems wume:=. me one==
ECN NC.
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INGIMEIRING CHANGE NCTICE ,m.,em.s ., mc c ;
C_ - u, , W vos n I g n.is sep.aa sysrtwsi u c. 3ji/w et -w. . umu. m sa t a=e..u s ::4svsmsr-=s exauca CmW N- . -
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A single line. ciagram snowing tne interconnection of :na 4.16 C/ switengear, i me 480V loac canters, and :ne motor contici cantart wita :ne existtag gistri-button system and anocer snowing tne 120 Vac/125 Voc systems are at. acned.
. -Cool'..n, 'ans will te ansee to :ne nuclear service susoly transformer :n ungrada its rating to 10 MVA. All ecutament will be setssica11y and environ-mentally cualtfled and me systan will be assigned and installed to tne reautremanu of IEEE 279 and 308.
During normal ooeration busas' 54A -and Sahl will be connected to the nuclear servics sussly transformer and buses 548 and fast will be connecten to tne ~
> start-un No. I transformer. The only loadt on 54AZ and 5481 at tne end of tne 1981 outage will be 1 cad cantart 53A2'and 5382 resnecitvely. The only load cantar load other than tne MCs wi1Lbe the 600A cameuser tattary enarger.
Since tne new slant camouter will not be installed, tais enarger is needed l
- only
- = keen me batteries caarged. All etner loads to be acced suring tne i 158% outage wt11 ne :n tne MCs or :ne 120 Vac/125 Vdc systnas.
fun-(Qts as indicated-on :ne attacned single lines, will to used :n install 1
Drawing 1101 will be revisan anc new snests will j anc turn over :ne soutoment.
' as ascos to E104. E105. E107, and 1108. Adattionally, many new venace crints.
conneciton diagrams. etc. =111 to added. if am -ez.m
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_ ____ E m t _ _ _ _ _____ _ _ Page 38 _
Revision 4
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NEP 4109
, ATTACHMENT 8.3 ECN A-3660 Page 2 of 4 -
REASON FOR CHANGE A study to determine if the Class 1E Power Distribution System could support the new loads imposed by NUREG 0737, Clarification of TMI Action Plan Requirements, and NUREG 0696, Functional Criteria for Emergency Response Facilities, has been completed. The study concludes that they present diesel generators are fully loacea witnout any soare capacity to feed new loads. Furthermore, the Auxiliary Feecwater Pumps cannot be automatically 1caded on the existing diesel generators in the required time from with any assurance of meeting NRC Regulatory Guide 1.9. New diesel generators are needed to provide the additional on-site capacity that is required, which in turn requires new 4.16 kV switchgear and load centers to distribute it.
4 Existing motor control centers for lE service have a totai~ of only 13 spare positions and a review of the current requirements for new design indicate l
the 73 new loads have been identified which require service from MCCs. The need for new NCCs for IE service is to support v' ital bus systems and to feed the auxiliary loads in the Nuclear Service Electrical Building (NSEB) and i the Diesel Generator Building. In addition, new MCCs are required to supply
} pressurizer heaters that are presentlysfed temporarily from separate IE feeders in non-IE motor control centary. ,-
! The existing IE 125 Vdc and 120 Vac systems, including batteries, battery chargers, and inverters are adequately sized to carry 'exisitng loads, but do not have sufficient spare capacity to add loads required by NRC direction.
- A review of the existing 120~Vac vital buses shows that the addition of new -
- loads will result in exceeding available capacit.ies by 24 to 54 percent for the four-channel system. The 125 Vdc batteries and battery chargers which support the inverters (i.e., vital ac buses) as well as supplying de loads will similarly exceed available capacities by 26 to 72 percent when new l~ loads are added. A new four-channel scheme is required to supply these loads and to provide ample spare capacity for future loading.
Eauinannt Description Quantity Classification Location I o 4161V Switchgear and Bus 2 1E NSEB ,
o 480V Load Centers 2 1E NSEB o 480V MCC's 2 Non-1 E Aux. Bldg.
o 480V MCC's 2 1E NSEB
! o 480V MCC's 2 1E Diesel Bldg o 125V DC-120 Vac Vital Sus Systems 125V DC Batteries 4 1E NSEB 125V DC Panel Boards 4 1E NSEB 200 AMP Battery Chargers 6 1E NSEB 25 KVA Inverters 4 1E NSEB 120 Vac Panel Switch 4 1E NSEB Transfer Switch 4 1E NSEB i (bypass ekt.) Attachment 4 Regulating Transformer 4 1E. NSEB (bypass ekt.)
- _ _ m __
~ _ .
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NF.P 4109 ECN A-2660 Sage ? c' 1 Attachment 8.9 (cont'c) 4 ATTACHMENT 1 9 Table 1 _
. 120 Vac Vital Power Buses ana Inverters SUS A B C 0 Existine Load. XVA 14 15.5 22.7 24.8 1
Usable inverter Canacity . XVA 20.4 18.5 25 25 4ew Loads Recuired. KVA 12.8 ~ 12.8 8.1 8.4 Maw Loads in Excess of Existine Canacitv. cercent 31 54 24 33 -
New Inverter Ratine. KVA ' 25 25 25 25
~
- 1. ' Invertet ratings are 25 KVA. Usable' inverter capacity assumes all available
~ '
spare ca' s acity from the battery sysstas is serving invertar load.
- r _
l Table 2 ,
T23 Vdc IE Buses and Battery sizing 2 L
SUS A 8 C 0 Total Existine Canacity - AM 564 664 580 590
- (percent) (19) (9) (22) (6)
Existing Spars Capacity AH 128 59 277 277 New loads Recuired - AH 540 540 277 277 New Load in Excess of Existine Canacity. cercent 62 72 26 42 .
New Battery Ratine - minimum AH 710 71" 350 350 (percent) (24) (24) '
(21) (21)
Spare capacity New Batteries - min AH 170 1.70 73 73
- 2. Ampere-Hours at 8-hour discharge rate Attachment 4
- w ._ _ _ _ _ _ R0viei@@ 4
NEP 4109 l
i Attachment 8.9 (cont'd) ECN A- 3660 PAGE 4 0F 4 .
START-UP NO. I START-UP MO.2 wW wW *
~
Mmmm (Ym WA REACTOR CIRC. WATER PP '
CCCLANT PP WW NUC.ZAR '
mm SERVICE SUPPLY A-3GGCA .
, . 4.se nv fA-SGGCC
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D
? A-3640s s . . s >s .,
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lS4A2 l l 34 A.! SAS ! S452 l l l e
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@ @ iN ww ww ww ww tY m tY m tY m ' tY M A=366GO Saat ssA 48cv Sss 1 i su2 1
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328T
,gp SAT CMGR M40N -
A- GGGl 3254[
- 70$$_ --
- ?UTU $
SAT CMGR M484A . , BAT CMGR M4868 3669 A-3G43 >
Attachment.4 -
- r - - - - - -
t --c-e em-,-rce,w.,_ , - , - . - , . . . . - - _ _ _ _ . , _ _ , _ , _ _ , _ _ _ _ , , , _ _ _ _ _ _ , __ _ ,, _ ,_
r .
NEP 4109 ATTACliMENT 8.10 _
AREA 0F RANCHO SECO FOR WHICH NUCLEAR ENGINEERING STAFF APPROVAL ON DESidN CHANGE IS NOT REQUIRED
- 1. Leavell-Dravo (Training) Building
- 2. All Trailers .
- 3. C Warehouse
- 4. On-site Warehouse
- 5. Of f-site Warehouse ..
- 6. Tool Room
- 7. Electrical- and Welding Fabrication Shops
- 8. Quonset Hut
~ ~ '
- 9. Old Construction Office (BechtellF8uilding) _
- 10. Turbine Rotor Storage Building- Jr
- 11. Contractor Temporary Construction Offices -
l l
l l
l
- l I
Attachment 4 PA89 42 .
NEP 4109 (Sheet i of 2)
AIIACHMENI 8.11 ,
DESIGN BASIS REPORT WRITERS' GUIDE I. PURPOSE OF DESIGN CHANGE:
' A brief explanation of why this change is needed and what it will accomolish.
II. DESIGN CRITERIA:
A. Summary of Chance An explanation of the change to be implemented and the actual work to be performed.
B. Desian Basis A detailed . definition of the applicable design codes, regulatory requirements and/or any othgr plant specific design standards.
~C. Scne .I
- An explanation of the total scope of this change, defining its boundaries, limitations, ef'fect on other plant modifications, and the coordination of this chance with other chances. Include a discussion of impact on Plant Technical Specifications.
O. Eauioment Class and Power Recuirements A general summary of the classification of the new equipment being installed and the power requirements (i.e., power sources and classification, types of power, etc.l.
! E. Testine i A- brief explanation of any testing requirements needed prior to or during installation. Also, if acceptance testing is required.
- III. CALCULATIONS AND DESIGN INFORMATION:
A. Desien Features i
A detailed explanation of the design change elaborating design approach, equipment hardware descriptions, and/or implementation.
- 8. A detailed description of the function of the design change andi its relationship with existing plant systems / equipment. Setpo nt data shall be included inAttachment this section.
4 m
f NEP 4109 (Sheet 2 of 2)
Attachment 8.11 (conL'a)
C. Desian Calculations -
Inclusion of or reference to any design calculations required for (1) design or installation of new equipment, or (2) modifications to existing equipment. Calculations shall be in accordance with Nuclear Engineering Procedure 4106.
TV. FAII.URE MODE A detailed explanation of ally system failure mode and possible effects' . '
on plant safety or plant operation that could be caused by the design change. In addition, if the change does not affect or involve Control Room Instrumentation, check the appropriate box. If the change (211 affect or involve Control Room Instrumentation (including power supplies), check the box and provide an additional detailed analysis. -
V. SPECIAL MAINTENANCE REQUIREMENTS Imposed.by vendors or as system ilesign requires.
~. . .
VI. SPECIAL OPERATING REQUIREMENTS ' -
Imposed by vendors or from systed standpoint, imposed on operations.
VII. VERIFICATION CRITERIA Describe any special verification documentation and/or inspections required to meet V & V program commitments.
VIII.CONMENTS Any special remarks pertaining to the design or implementation of the design change.
Attachment 4 f4wn_/V1 -
. - NEP 4109 (Sheet 1 of 3)
ATTACHMENT 8.12 DRAWING AND OTHER DOCUMENTS MAINTENANCE (UP-DATING)
REQUIREMENTS I. ORAWINGS WHICH REQUIRE DCN's A. Civil
- 1. Civil / architectural ces ign drawings
- 2. Major suppliers type vendor drawings such as VSL, Harnischfeger, all hoist and elevator vendors, and Chicago Bridge .and Iron
- 8. Electrical ..
- 1. Drawina Series Title
~
i E 100 One Lines E 200 Schematics E 300 , Wiring Diagrans ,
E 400 . Panel Layouts
~ '
E 500 I Electrical Equipment Arrangement -
E 600 r Grounds .
E 700 Conduit and Cable Tray E 800 Lighting
- E 900 Communications E 1010 Elece.rical Circuit Schedule E 1008 Electrical Raceway Schedule 4 E 1011 Load Design Data Sheets E 1012 Motor Operated Valve Data Sheets
! 2. Current and potential transformer saturation and ratio j correction factor curves.
- 3. Structural type factory fabrication drawings for electrical panels, including layout and drilling details.
- 4. Structural type factory fabrication drawings of electrical penetrations. .
= Attachment 4 Page 45 . Revision 4 0009K
r i
NEP 4109 (3 heel 2 of 3)
Attachment 8.12. (cont'd) 4 _
C. Instrument and Control -
.1 . I Drawings
- 2. Vendor Instrument Drawings
- 3. Class I Instrument Tuoe Drawings
- 0. Mechanical
- 1. Design Drawings:
- a. Piping and Instrument 01agrams (P&ID's)
- b. Isometric Drawings
- c. Pipe Hangers / Pipe Supports .
- 2. Vendor Drawings ,
- 3. Line Designation List (M-583)
- 4. Valve Designation' List (M-872) -
- 5. Motor Operated. Valvi Data Master List (M-873)
- 6. Master Valve List (M-871)
- 7. Plant Equipment List (Equipment I.O. Numbers)
- 8. Specifications for Piping Design (M-870)
- 9. System Transients for Class I Pipes and Valves (M-878)
E. Nuclear
- 1. Vendor Drawings
- 2. USAR l
l l
Attachment 4
- Pm n 46 nwwtaalt
NEP 4109 (Sheel 3 of 3)
Attachment 8.12 (cont'd) .
II. THE FOLLOWING IS A LISTING OF ORAWINGS THAT 00 l40T NEid iU St MAINTAINED: .
A. Civil
~
- 1. Vendor Drawings on Reinforcing Steel
- 2. Vendor Drawings on Imbedded Stoci .
3.. Contractor Lift Drawings
- 4. Grating and Decking Drawings ..
- 5. Vendor and Contractor drawings on the various building structures, etc., at the site. This would incluce sucn -
structures as tiie auxiliary building, snop and warehouses, das and reservoir, grading and paving, and yard structures and foundations. Bear in mind that
- these are civii. structures and that all significant
' ~
vendor or contraqtor information is included in the '
engineerin~g design drawings. -
B. Electrical [ '
- l. Name Plate Engraving Lists
- 2. Factory Production Schedules and Charts
- 3. Seneral Information brochures that were gives drawing ,
numbers
- 4. Factory test data reports that were given drawing numbers i l
- 5. Factory Painting Instructions
- 6. Shop Assembly and Fabrication Procedures
- 7. Vendor Drawing Schedules
- 8. Vendor Cable Tray Detail Drawings (this includes all E26.04 drawings)
- 9. E25.05 drawings of AMP crimping tools and lugs C. Mechanical
- 1. Piping Layout Oggdage 4 Pase 47 ym
.NEP 4109 ATTACHMENT 8.13 MINIMUM DISTRIBUTION BY Spc FOR APPROVED ECN'S The original is retained in SDC files. Copies are sent to:
- 1. All Supervising Engineers.
-2. Selected drawing stations at Rancho Seco. (Include Nuclear
' Operations Training Department) !
- 3. CognizantIngineer.
- 4. Nuclear Operations Designated Engineer, i 5. Originator. -
- 6. Principal Project Engineer. --
7.. Startup Engineer
- 8. Nuclear Engineering Site Resident Engineer.
- 9. ALARA Coordinator.
- 10. Operations Superintendent when V & V are called for. .
- 11. Living Schedule Coordiditor.
^
- 12. EQ Coordinator.
- 13. Nuclear Engineering Fire Protection Coordinator. ,
- 14. Nuclear Operations Fire Protection Coordinator.
i 9
MA092 Page 48 Revision 4
. Attachment 4 i
w
. DCN PACKAGE COVER SHEET '
7 -(Attachment 8.14.a.)
ECN NO. ,
1 TO: SDC/ MAIL STOP 222 TRANSMITTAL DATE: -
)
s
+
)
C THIS PACKAGE IS COMPLETE. TRANSMIT FOR REVIEW. i
' ~
C THIS PACXAGE IS NOT COMPLETE. HOLD FOR:
l C THIS TRANSMITTAL COMPLETES PACKAGE ON HOLD, TRANSMIT FOR REVIEW.
FRG4: ~
Cognizant Engineer c - TO: SCHEDULING
% SDC PLEASE REVIEW THE ATTACHED OCN's[ CHECK; THE APPROPRIATE BOXES,
~
AND RETURN TO SDC BY -
s DATE (2 Woryng Days)
/ / TRANSMIT REVIEW PACKAGE TO CONSTRUCTION
. ' . j
// OISTRIBUTE PINXS TO NUCLEAR ENGINEERING
, // OISTRIBUTE PINKS TO NUCLEAR PLANT
/ / , CHANGE THE CURRENT DISTRIBUTION TO: -
TO: SDC/ MAIL STOP 222 FR(M: SCHEDULING __
_ Initials Date s s PLEASE. PJt0 CESS THEiDCN '.S . ALI#DJ.C4 TID _ABOVE.
^* 4
. PageYf ,
Revision 4
NODE PACKAGE REVIEW SHEET (Attachment 8.14.b) -
ECN # TRANSMITTAL DATE:
FR(Mr SOC -
e TO: Nuclear Operations Designated Engineer This DCN Package is submitte$ for your review and comments. Please review this package for the following:
Agrument with 10CFR50.59 Decision .
Testability .
Maintainability
- Operability Training Requirements .
If comments are not received on or before (15 working days) this package will be released by SDC for construction.
. All comments are to be attached to this transmittal sheet and returned to 50C.
6 TU BE COMPLETED BY NUCLEAR OPERATIONS 025IGNATED ENGINEER:
Comments Attached . ,- .: ..g No Comments i.
l Nuclear Operations Designatec Engineer Date _
NOTE: If "No Comments" is checkec and signed by the Nuclear Operations Designated Engineer, a signature by the Cognizant Engineer is NOT required.
Comm:nts have been reviewed by the Cognizant Enginar and the DCN Package will be re. leased for construction.
Cognizant Engineer Date Pagea60 ment 4 revision 4 i . .
. .. CONSTRUCTION PACKAGE REVIEW SHEET . '
(Attacnment 8.14.c)
ECN# TRANSMITTAL DATE:
FR(M: _ l 50C -
l TO: Construction This DCN Package is submitted 'for your review and ' comments. Please review this package for the followino:
Constructability ;
If' comments are not received on or before (15' working days) this package will be released by SDC for construction.
All comments are to be attached to this transmittal sheet and returned to SDC. ,
~.'
TO BE COMPLETED BY CONSTRUCTION: 1
. . Comments Attached.. 1. - .- '
. ~- ~
No Comments -
..=.
t Construction -
Date 1
NOTE: If "No Comments" is checked and signed by Construction, a signature by the Cognizant Engineer is NOT required.
Comments have been reviewea by the Cognizant Engineer and the DCN Package will ha released for construction.
l l
Cognizant Engineer Date l
Page 51 Revision 4 l
l Attachment 4
NEP 4109 AlIACH!iENT 8.15
-A w S MUD 5e' : ==
_ .r v ~~a:- uc.
DRAWING CHANGE TRANS.MITTAl. Sheet of
_, a m m a- a-
~
- -*-riousaaet w aeEn :AN 'rf cf * * *N (wtw ocx wuuagas E sc.ss t.mq s
- war?I w n Omawin.o ww" /
- ev soc
- 2.sca %
El DRamess saJansen ,, ,
h l ] WOax psypcRMc gy
- "W l i
. i l- 2 isu=:.Lui Dasassumes c l l 1 I l W C l l l 1 l ..
I i i ! I-
- !F OHANGE iS SEING i i i l 1 l l l l MADE IC !!3UED PINK QCN
I l I I i ovn mEcuinto: O yrs i I I I "'
I I .l... - . . . Q No I -4 1 I I L tr ves,ovn sHAi.L sg -
I I I l ATTACHE 2.
I I I l~
l i I I l l l l l EC3asadaNTS/Rt.ASON POR ANY OtANSEE M PACXACL i i I. l .,.
I I I I I I I I -
1 I I I I I I I I I I I I I I I
. I - 1 I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I l Attachment 4
[Pagql2 Revision 4
. NEP 4109 1
ATTACHMENT 3.15 (Sheet 1 of 2)
INSTRUCTIONS FOR 00C'JMENT ING ENGINEERING 'dALXOGUNS CF '
PLANT MODIFICATIONS
- 2. Enter the OCN Number, Orawing Number, Shec*. and Revision Number, as on a DCN Transmittal Form.
- 3. Enter the Drawing Title.
- 4. After walkdown has been satisfactorily completed (no nonconformances),
the person conducting the walkdown signs and dates for eggh DCN listed.
- 5. When walkdowns are completed, the Cognizant Engineer signs and dates, .
and forwards the form (s) to the Project Engineer.
- 6. When work is complete on NuclearsEncineerina .ECN's, the Project Engineer _ approves and dates the form (s) and sends originals to SDC.
.f. . . -
When work is complete on Nuclear Ooerations ECN's the appropriate -
superintendent approves and dates the form (s) and sends originals to SDC. -
l t
i l
Attachment 4 j Page 53 . Revision 4, l
m ammu . . _ . un _ _ . _
~ - - - ~ ~ - ~ ~ ~ - ' ~~
3 RECORO OF PLANT N00lFICATION WALKDOWN BY ENGINEERING ECN NO. Approved; _.._ __ ._ _ .._. .. .___ . __ .__ _ ..
PROJECI ENGINEER /SUPtktillENut NI/0ATL
. COGN17AN1 ENGINIiR/DAIL DRAWING DCN DRAWING NUN 8ER SHT REV .Ti1LE llALKDOWN NO. No. No. . . __
_. __ BY (SliiNAlllRE/0A1_t, )_?
. . ,3
, ,0.i *_ ,I 5 3*
) y
~. = m f!
" 8' rr W
- l Fg p e
33 r1 -
m . . . . . _ _ . _ _ .. .___ . ..
.N n g
O w _It c -'
H . _ . . _ . ... _ .
c
. *' M rrt a
_.a ca o
o Signature indicates acceptable walkdown.
i 8 .
0 .'A. _ .- __ _ _
I l
- NEP 4109 ATTAC;daisi 5.1; l
l N. E. HEL Coordinator HIMS Coordinator N. O. I&C Engineer Site Q. A. ,
Jerry 'di!!iams ,
TRANSMITTAL OF NEL FORMS MOD ECN(s)
Attached are MEL Entry / Revision request forms for the fo1T6 wing equipment:
6
- f. .-
^
o Please sign in the appropriate place and route to the next person.
If you have any questions, please feel free to contact the requester or myself.
Attachments cc: J. W111fong w/o attachments J. McColligan w/o attachments Typical Engineering Files / Plaza 50 Distribution Design City Files /208-0 JW/pm Attachment 4 Page 55 Revision a
NEP 4109 OSMUD v - - - ==.,c-DRAWING CHANGE NOTICE RANCHO SECO SWITCHYARD ATTACMME.N1 8.18 Sheet of 3:sc:PuNG. C 3L3CMCAL Q ClVik C MSCHAMCAL
.v:. vc :mawimo sc aev '4c m av :An mays eeneweg av ars :4rsmecavao :ars seuAsso :a m a g aeviss: sv : Art f
m eet saviasse av urs aresca an==cven, sec.nasame snour supesason :Ars
.os uncurion m s vamo we m m as sensomasso av RANWO SECO SWlTC.*EARD suumeny -, ewA~as
. =_^*S= 80s CwANGE IS NSW CRAWING =
(Octwomist EV EBC."JEC W81tTE W y neuAans i OCm i i ase misis I ga I onamisui ma i- SmnW j *Ev - use =c e
l
' I a g. ,,
! I i ! ! Ai ~
Jji i i i 1! -
4
. i -"
I i B s
! i. I I I i : I .
l l i i i l l-i i I .
i
+
i i i l l .
~
i i l- l l 1
. : i l i- !
i i i i I !
I I I I I i i I l 1 i i 1 i I i i i l .
I I I I i l' I
. GCN 015M84GVED EV QATE
- ME.2 -..wn Ccasm.s.au Ev omrt *
. l
- SheUD AP88tCVALS
___; c- _ > = r ---- - -
--- c . .- e spa. ----.N^--- :=c+6 l
[ ,_ _ _ _ :--f sww.
l NN IMTMSJTION N ,
i
. i sare sarn saru save say, .
samaams men Attachment 4 Page 56 Revision 4
NEP 4109 AffACHMENI 8.19 t
RANCMC SECC SWITCH YARD ROUTE SLIP OCN No.
issue Cate f
van
- Stoo Reec- ::mr ' ens ts Qischoon Engmeenng Grous Sumerwsor. 30 in 7enemiassen Eng .a...; Grous Suoerwser 30 te C*wil Engmeenng Grous Sumerwsor. 30 .
I Cagmaane Engneer. 30 3 Pngec: Engmeer. . . . ..... . . . . ...
30 4 Engmeenng Grous Susanneer. . .. .. ....1 201 E Me. neger. Numeer Engmeenng. . . . . . . . . . . . .. f. . _ .
_ 32 t Engmeanne Conneuruuon Canaa . . . . . . . . . . . . . . . . . . . . 3e '
7 Onyneser * . . . . . . . . . . . . . . . . . . . . . . . . . . .:
8 Denannemen & Ciamounen Coonsnaar. . .... 59 8- Engmeenng con 6gurocon Camrot . . . . . . . . . . . . 36
~
ic ongemor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ _
I 1T & Disarmusen Coorowistor. . . . . . . . 59 l
T1 Sucessmen Suoerweer . . . . . . . . . . . . . . . . . . . . . 63 i
13 Peromen............................... l
[ is - Cayusene won . . . . . . v. ~. . . . . . : . . . . . . . . f. . _
13 1enonummen & Dieseusen Caereinssor. . . . . . . . SS l
te Enyneenne Canaguremen Canow. . . . . . . . . . . . 3a l
1 17 Senior 0rettemen . . . . . . . . . . . . . . . . . . . . . . . . 30 l l
1 1$ F 6 @ ....................... 30 !
19 Enyneenng Grous Suoerweer. . . . . . . . . . . . . . . 30 l
30 PnMeet Engmeer . . . . . . . . . . . . . . . . . . . . . . . . . 30 ;
l \
21 Eppneenng Canaguranen Centrol. . . . . .'. . . . . . 36 ;
l 4 diessoremet. Attachment 4 Page 57 Revision 4
NEP 4109 ATTACHMENT 8.20 DELEiED ,
4 -
E '
~
_f .
- =
Attachment 4 Page 58 Revision 4
NEP 4109 Al'IACHMENf 8.21 ,
DOCUMENTATIONANDREVIEWREQUfRENENTSMATRIX FOR DCN PACKAGES INITIATED BY AN ECN Occument/- SAFETY CATEGORY OF ECN Review Steo 50.59 "NO" 50.59 YES" Staff Review As Required by ECN Reg:24 red 08R As Required by ECN Mcqui' red
. DVR As required by ECN Required V&V Not Required As Required by ECN SA Not Required Required PRC Approval Not Required Required -
MSRC Approval Not Required As Required by PRC NRC Approval . NotRequir5. .-
~
As R'equired by MSRC OCN's. As Requi M As Required ,
Package Cover As- Required As Required Sheet M.E.L. Input As Required As Required l N00E Review Required l Required cf DCN's l Construction Required 2 Required 2 Review of DCN's Safety Review Not Required Required
-cf Proposed Fac. Chg MIfJi:
- 1. Not required for ECN's which have a Nuclear Operations Cognizant Engineer.
- 2. Not required if physical work is-to be done by Nuclear Operations.
Attachment 4 Page 59 Revision 4
SANptE Of' C a. SA. SWR APPLICAT(gi Scen4rlo; Assume Major 1:CN is 50.59 "Yes" t7 or Hare.Suh-ECN's. One of Whish -
7- is a 50.59 'Yes"
- ~- - . - .
SA DVk
. ITEM 988 .
A SSR for the Major is Required. An SA for the Major is kequirgil. line Major is i .is t'.:d e.V a. 4uiriin.
MAJOR ECN but since pq elr.nsisit. is.e issia 1 It may or may not be appilfable it Jeay or may not be applicable . ,
to the Subs. If applicable to to the Sub marked 50.59 "Vps" a!)ainst the N jor.-n.. uti: .i.
the Sub(s), stat, this in a if applicable to Sub(4), st4te Required for the it.s i..r.
memorandum to Soc. tigjg in a memorandum to Soc.
ua
- A separate, unique SSR is Re- A sppfrat"9 l baique SA is Re- . Design Verific allosi irosslit ti
- SUS-A '
m.stked "RE(plINED" an.1 a DVR quired if the Major SSR does quired (Tethe ' Major SA sloes not 0{(ASSUMEIS not apply.
~
apply, would be Required. -
g 50.59 "Yes")
g s
If Sub is marked % R REQUIREp", Not H4 quired. Respaired only if 6.18 L . .:lici k .
8 508-8 a separate, unique DBR is Re- DV Required. the sie..is i.ni is (ASSUME IS . based on Safely Slunift..is.u iil 50.59 'No") quired if Major DBR does not Ilie Sub-ECH se ope.
apply.
i.;
F e
2 S. 9 8 5
. , A, ok
NEP 4109 ATTACliMENT 8.24 SLOCX OIAGRAM CF NEP 4109 ORGANIZATION PtJRPOSE I 8of v
POLICY AN(1 RESPCN5181LlTIES 2.0 v
l Gul0ELINES FOR APPLICATIONS OF .
ECM's , OOR' *,, SAR's , OCM' ,
ANO DVR*
. 3.0 f
,r p <p sp J -
BS)
- 1. Walls, Floors, Ceilings, doofs and Partitions ~
- 2. Fire Barriers i 3. Fire Doors - 4 -
- 4. Penetration Seals (a11 types)
- 5. Structural Seals and Hatches AnDendix R Safe Shutdown Systems and Eauicment
- 1. Containment Building Spray System (CBS) -
- 2. Core Flood System (CFS) i
- 3. Decay Heat System (DHS) _
- 4. Electrical Distribution System (EDS) j l S. Emergency Generator System (EGS) 1
- 6. Feedwater System-Main / Auxiliary Feedwater Pump Trains (FWS)
- 7. Heating Ventilation and Air Conditioning System (HVS)
- 8. Instrumentation - any of the following:
a) Pressurizer L'evel b) Reactor Coolant Pressure c) Reactor Coolant T hot d) Reactor Coolant T cold e) . Makeup Tank Level f)^ OTSG Levels j g) OTSG Pressure j h) RCP Seal Injection Flow 1 i) Source Range Neutron Flux j j) Decay Heat Return Temperature k) RCP Seal Injection Flow
- 1) SFS Analog Cabinets , ,, 4 Page 63. . Revision 4
NEP 4109 ATTACHMENT 8.25 (Sheet 2 of 2)
- 9. Nuclear Service Raw Water System (NRW) ,
- 10. Nuclear Service Cooling Water System (NSW)
- 11. Purification and Letdown System (PLS) -
- 12. Reactor Coolant System (RCS)
- 15. Safety Features System (SFS) .
- 16. Seal Injection and Makeup System (SIM)
NOTE: Pipe support DCNs for the above systems do not require NEFPC review Other DCNs ,
- 2. Communications / Plant Communications System (CSP)
- 3. Reactor Coolant Pump (RCP) Lube Oil Collection System .
- 4. All of the following Electrical drawing DCNs.:
- a. One Lines - E 100 serip' .
- b. Schematics - E 200 serles
. c. ' Electrical Equipment: Arrangement - E 500 series
- d. Conduit. and Cable Tray ,E 700 seri'es
. e. Electrical Circui-t Schedule.- E 1010 series
- f. Electrical Raceway Schedule - E 1008 series l
1 PAR 9a@dment4 Revision 4 NEP 4109 It!DE 7. Page 1.0 PURPOSE 1 I ~ 2.0 POLICY AND RESPONSIBILITIES 1 2.1 General Policy 1 2.2 Engineering Department itesponsibilities 2 ~ 2.3 Nuclear Engineering Department Responsibilities 2 2.4 Nuclear Operations Departmen't Responsibilities 3 3.0 . GUIDELINES FOR APPLICATION OF ECN's 08R's, DESIGN VER FICATION REPORTS, OCN's ANO SA's 4 3.1 General 4 3.2 Engineering Change Notice (EIN) 4 - I 3.3 Design Basis Report (08R) 6 3.4 Design Verification Report (OVRT 7 3.5 Orawing Change Notice (OCN) 8 3.6 Safety Analysis (SA) 9 4.0 DETAILEO PROCEDURES 1 4.1 ECN Preparation and Processing 9 i 4.2 08R and DVR - Preparation and Processing 14 l 4.3 OCN Preparation and Processing 15 4.4 SA Preparation and F.-ocessing 17 l l 4.5 Preparation and Processing ECN's and OCM's for Rancho Seco Switchyard. 18 i Pagd'V9chment 4 Revision 4 NEP 4109 . 'INDEX (Cont'd) f4.98 5.0 REVIEW, APPROVAL AND ISSUING OF OCN PACKAGES 5 .1 - General- 20 5.2 DCN Reviews 21 5.3 Process for ECN's Classified as 50.59 "Yes." 21 5.4 Process for ECN's Classified as 10CFR50.59 'NO." 21 ~ 6.0 INITIATION OF WORK 21 7.0 COMPLETED WORK - CLOSE0UT OF DOCUMENTS 22 8.0 ATTACHMENTS 6 23 W-e s . l . I l l t , p tghment4 Revision 4 l NEP 4109 i 1 L!SI 0F All ACMMENIS l 8.1 Engineering Change Notice 8.2 Deleted 8.3 Design Basis Report 8.4 Design Verification Report '8.5- Responsible Groups for Specialized Lists, Logs, Schedules, Etc. . 8.6 Examoles of Breakout of a Major ECN into Sub-ECN's 8.7 Flow Chart - ECN Processing 8.8 Flow Chart - 08R's 8.9 ECN Example 8.10 Areas of Rancho Seco for which Nuclear Engineering Staff Approval on Design Changes is not required 8.11 DBR Writers' Guide 8.12 Orawing and Other Documents-Maintenance (Updating) . Requirements 8.13 Minimum Distribution - Approved ECN's 8.14a Package Cover Sheet - NODE 8.l*b Package Cover Sheet - Construction
- 8.15 Drawing Change Transmittal 8.16 Sheet 1 of 2 - Instructions for. Documenting Engineering Walkdowns of Plant Modifications 6 8.16 Sheet 2.of 2 - Record of Plant Jodification Walkdown by Nuclear
~ Engineering I-8.17 IOM for Transmitting MEL input sheets - 8.18 Drawing Change Notice, Rancho Secd Switchyard , 8.19 Rancho Seco Switchyard Route Sjip ' 8.20 Deleted
- 8.21 Documentation and Review Requirements Matrix for Work Packages
8.24 Block Diagram of NEP 4109 Organization 8.25 DCN's Requiring Fire Protection Review , 4 h Pa#%"fment4 r Yb-02' v-' f** OCT-13 '86 10:53 T-BW-SPIS-NPD-NO-1 / l SPECIAL PRODUCTS AND INSPECTION SERVICES WORKING INSTRUCTION NO. 4 Sof tware__D,evelopment Mgr. , Contract Management _ 3// f/f2.- 5 -'W -
- p .
Mgr. , Equipment Design h 3//7!P'L 8 6 94 - Mgr., operations Mgr., ISI Technology Applications , IM_ _ .._ _ _ _ _ __-_ /b ' Mgr., Marketing _ M//['[' *** - 3/A A/J'V Mgr., Special Products and [ /[ . Inspection Services ( __ _ /_{ff '2.----_ _ _ _ s ( ).J , Rev k Date Yly f fh- > Page 1 of 7 c . - ccT-13 '86 10:50 T-BW-SPIS-NPD-NO-1 . #902-03 g SOFTWARE 1.0 PURPOSE . This working instruction shall be followed in the. design of all Special Products and Inspection Services computer products applicable to a specific contract or product development, and for a,ny changes to the design of those products. 2.0 PROCEDURE 2 .1 A function requirements document shall be prepared. The document shall address all of the requirements of the customer's requirement specification or all of the advertised features in B&W's proposal and shall address how these are to be fulfilled. It shall contain the following as a minimum: 2.1.1 Description of the function the computer system is to perform. 2.1.2 Diagram of hardware configuration. 2.1.3 List of all features to be included in the system. ' . This is to include as a minimum the following: 2.1.3.1 Summary of each individual task to be performed by the system. , 2.1.3.1 Description of input / output, including forma t and units. 2.1.3.3 Description of features to be incorporated to facilitate program load, start-up, initialization, etc. 2.1.3.4 Description of features to be . incorporated for handling of power failure, 2.1.3.5 Description of internal checks to assure proper operation, action taken by the system upon detection of an error, and signals provided to the outside world. 2.1.3.6 Interface requirements to equipment outside of the system. 2.1.3.7 Requirement for software verification '- and validation. Rev 2 Date CN/g. 1~ Attachment 5 Page 2 of 7 - i l I -- .. OCT-13 '86 10:51 T-BW-5PIS-NPD-NO-1 '#902-04 . l i, I' (Q1 2.2 . Detailed programming flowcharts shall be prepared based f' "' on the functional requirements documents. Flow charts i should be on a functional level, but should be detailed 4 enough to show all sections and subroutines. An outline 'l ' of a Test Plan for testing the sof tware shall be prepared based on the flowcharts. 2.3 A review shall be conducted of the documents produced 'l under 2.1 and 2.2 before proceeding further with the de sig n. The purpose of this review shall be to assure that the design .as re flected in the flowcharts and - 1 drawings meets the requirements of the Punctional l Requirements Document. The review shall be conducted by the engineer responsible for the work, his supervisor i and another independent engineer. Comme,nts from this review shall be incorporated by the responsible engineer, and this review shall be completed by signing of the flowcharts and hardware drawings by the three reviewers. On systems requiring verification and validation, this review shall also be conducted by a qualified individual other than the original designer (s) . Comments generat from this review shall be addressed'in writing to the ,d& responsible engineer, who shall make changes as y,y appropriate to the documents based on the comments, and
- d respond in writing to the ' comments. All correspondence relating to the verification shall be included in the QA file for the system, and reference to the approving document shall be included in the notes on the d rawings .
2.4 Sof tware coding shall be performed in a manner such that flowcharts and coding can be tied together. Comments specifying the operation being performed by each section of the software, definition of meaningful variables and subroutines must be a part of the documentation and, if possible, part of the. code. Entry requirements and The exit conditions of all subroutimes shall be documented. test plan outline shall be filled in during the coding, to assure that all. logic will be tested. 2.5 Detailed hardware drawings'and parts lists shall be s reviewed as required to assure hardware /sof tware compatibility. As much as possible, hardware drawings should include - important system related details, such as the address space occupied by a board, meaningful signal name s on pin /, etc. Notes on the drawing should specify any special considerations in the design that may not be obvious to other than the original designer. , 1 . i ') / , e 't OCT-13 '86 10:51 T-BW-SPIS-NPD-NO-1 #902-05 l 73 2.6 Detailed test procedures (s) shall be prepared from the gMJ test plans to test the final hardware and softwarp. All features defined in the functional requirements document shall be exercised. 2.7 on systems requiring verification and validation a review of the final sof tware and test plan shall be conducted by a qualified person other than the original de sig ne r( s ) . This review shall consist of review of the final sof tware against the flow charts and functional requirements specification, and the test plan. The purpose of the review is to assure that the final design meets design requirements, and that all requirements will be verified in the final system test. Again, all comments and their resolution shall be in writing, all correspondence shall be placed in the QA file, and reference to final documentation of the verification made via a comment in the software. 2.8 System testing shall be performed in accordance with an approved procedure. The testing shall be performed by personnel other than the original designer (s) . Items that do not meet acceptance criteria shall be corrected as follows: 2.8.1 Items deemed trivial or cosme tic may be corrected ! l.9 and the applicable portions of the test run again. This shall be limited to format and spelling type errors. 2.8.2 Errors that require change to the logic in the software, but no changes to the flowcharts or functional specification necessitate a return to step 2.7. 2.8.3 Errors that require flowchart and/or functional spec changes require a return to step 2.3 In addition, for type '2.8.1 and 2.8.3 er.rors in sys tems - that require systems vetification and validation, a l document shall be prepared by the designer specifying l the following: . l s 2.8.4 The nature and cause of the error l 2.8.5 The proposed fix 2.8.6 Additional re-testing required 2.8.7 Any expected effect on system performance i ;. ' ~ Rev h Da te 7 (h, Page 4 of 7 Attachment 5 , . -*~. ~ OCT-13 '86 10:52 T-BW-SPIS-NPD-NO-1 #902
- w 3.0 DOCUMENTATI_QN
(} 3.1 The following documentation shall be prepared by 'the. system designer (s) . All documents shall be entered in the B&W drawing system. 3.1.1 Functional Spec per section 2.1 3.1.2 Flowcharts per section 2.3 3.1.3 Hardware drawings per sections 2.2 and 2.5 3.1.4 Software listing 3.1.5 Comments, variable definitions, subroutine entry / exit constraints, etc. , if not part of software listing 3.1.6 Dump of Object code if sof tware is in ROM 3.1.7 Calculation files for look-up tables engineering unit conversion equations, etc. 3.2 All software as shipped with the system shall be uniquely identified. Sof tware in Read Only Memory shall e- be identified with a stick-on label which contains the lv i B&W drawing number and revision for the object dump of it's contents. The identification shall also include a short description of the contents, and the address space that the ROM occupies. Tapes, discs, etc. , shall also be labelled with the B&W drawing and revision that documents their contents. These media shall be write-protected. Where master ROM's are used, a copy of the ROM shall be put in the custody of the Special Products and Inspection Service document control clerk. A copy of tapes and discs suitable for generation of ROM's for unique systems shall also be placed in document control. These shall also be identified with the drawing number t. hat specifies their contents. 3.3 Look-up Tables - A calculation file shall be prepared specifying the contents of all look-up tables. The file - shall state the source of the data (e.g. ASME Steam , x Tables, 1967, pp 23-27) , any ma thema tical manipulation peformed on the data, and, if necesary, hand calculations of selected data for the table. If automatic equipment is used to generate the table and put it into ROM, dat'a for 10 random locations shall be hand calculated and verified by hand with actual ROM data. This verification shall be documented in the T Rev _ Date I -b i Attachment 5
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-~ c-- . - __T-BlJ-SPIS-tFD-NO-1 OCT-13 '86 10:52 #902-07 I e TS calculation file and the entire file included in the QA i (i ' file for the project. These ROM's shall be documented ' by a hex dump of their contents on a B&W drawing. The drawing number and revision, along with a short _i description and address space informa tion shall be included on the stick-on label on the ROM. 4.0 DESIGN. CHANGES 4.1 Design changes, whether as part of a design enhancement initiated by B&W, or a customer requested design change shall follow this working instruction starting with changes as required to the functional spec. For systems requiring verification and validation, documentation of precise details of any changes made is important to assure that previous work is not volded by the change. ('\ On these systems the specific changes to the requireme nts docume nts, flowcharts and software shall be documented such that it is clear exactly what was changed. This can be done as a part of the document by p delineating revision number along side of sections that L_ are changed, or by a separate document that delineates 'the changes. A test procedure for testing the new < sof tware shall be prepared to test the changes and to assure proper functioning of the entire package with the t cha nge s. All'of the documents required in'section 3 h .' shall be updated with new revision numbers to reflect the new design. 5.0 OPERATIONS MANUAL 5.1 An operations manual shall be prepared for the system. Prior to release of the manual to the . customer, it shall be used by personnel other than the original designers to operate the system. 6.0 DESIGN PACKAGE 6.1 A design package shali be prepared for inclusion in the - project QA file required by 56-0134. This shall include: 6.1.1 Custome r requireme nts, B&W requireme nt spec, s etc. , as appropriate, and any correspondence related to the de sig n. 6.1.2 Functional requirements Spec. 6.1.3 Flow Charts l ~"-~~ ~ ~~~'"~ " -
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6.1.4 Results-of, technical teviews (h Sof tware listings on B&W drawing paper, as well 6.1.5 as on appropriate magnetic media or ROM. 6.1.6 System Drawings 6.1.7 Master copy of test procedures 6 .1.8 Operations manual (.' s I IJ 9 Attachment 5 Page 7 of 7 Rev b Date f _7 'g/ '- - - _ - - _ _ _ _ - _ _ ._