ML20129J760
| ML20129J760 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/19/1985 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Butcher E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM LIC-85-319, NUDOCS 8507230324 | |
| Download: ML20129J760 (10) | |
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 July 19, 1985 LIC-85-319 Mr. Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing Office of Nuclear Reactor Regulation
'J. S. Nuclear Regulatory Conmission Washington, DC 20555
References:
(1) Docket No. 50-285 (2) Letter OPPD (R. L. Andrews) to NRC (J. R. Miller) dated September 28, 1984 (LIC-84-323)
(3) Letter OPPD (R. L. Andrews) to NRC (E. J. Butcher) dated June 27, 1985 (LIC-85-211)
Dear Mr. Butcher:
NUREG-0737, Item II.F.2 Inadequate Core Cooling Instrumentation (ICCI)
Reference (2) provided the Omaha Public Power District's milestone schedule for submittal of the final design description for the ICCI, including the documenta-tion requirements of NUREG-0737, Item II.F.2.
Reference (3) supplied the final design description and noted that this package was currently undergoing indepen-dent review. This letter provides clarifying information as a result of this review. The attachment to this letter contains the changed pages to the Ref-erence (3) submittal. The changes are denoted by vertical lines in the right hand margin.
Si R. L. Andrews Division Manager Nuclear Production p[3OOhk$kOOO05 RLA/DJM/dao PDR Attachment cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, DC 20036 Mr. E. G. Touringy, NRC Project Manager Mr. L. A. Yandell, NRC Senior Resident Inspector
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(E4)
The following infomation is displayed on the QSPDS displays:
A.
- Liquid inventory level above the fuel core.
B.
Unheated junction tenperature at the eight positions.
C.
Heated junction temperature at the eight positions.
D.
Temperature differential at the eight positions.
The following plant-specific information is hereby provided:
1)
Paragraph 3.1.1 of Reference 3.2 listed C-E's recommended instrument ranges for certain SMM inputs:
RECOMMENDED FC1 INPUT RANGE RANGE Pressurizer Pressure 0-3000 psia 0-2500 psia Cold Leg Temperature 60-710*F 465-615'F Hot Leg Temperature 60-710*F 515-665'F UHJTC Temperature 100-1800*F 32-2300*F Pressurizer pressure indication provided is adequate to monitor all anticipated pressure events analyzed in the USAR.
For those analyses the pressure will not exceed the 2500 psia end point.
A commitment has been made (Ref. 2.6) to upgrade the qualification and range of the hot and cold leg RTD's.
ii) Paragraph 3.2 of Ref. 3.2 stated that alams for the following ICC variables will be provided with setpoints to be predetermined on plant-speci fic bases.
For Fort Cal houn, these setpoints are as follows:
VARIABLE SETPOINT Temperature Subcooled Margin
< 10*F subcooled Core Exit Temperature T 670*F Reactor Yessel Level T 100%
iii) The primary displays for the ICCI infomation are the Emergency Re-sponse Facilities Computer System (ERFCS) CRT's located in the con-trol room.
The ERFCS is a Modcomp based digital computer systen.
Some details of the system are shown in Figure 1 and additional in-fomation is provided in the response to Item 4.2.
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(E4) 1.b.
detailed description of existing instrumentation systems.
OPPD currently utilizes a Combustion Engineering Subcooled Margin Monitor.
This device receives inputs of pressurizer pressure and RCS hot and cold leg temperatures and displays margin (both temperature and presssure) to subcooling.
Two independent channels are provided.
Additionally, RCS temper-ature and pressure indications are displayed on the main con-trol board.
Range upgrade and LOCA qualification of the pri-mary system hot and cold leg RTD's are addressed in reference 2.6.
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.~.-.. - _-
(E4) 1.c.
description of completed or planned modifications.
A description of, and schedule for changes to the SMM RTD's wa s provided in reference 2.6, Attachment 1,
Response
3.
I Additionally, as described in the District's Reg. Guide 1.97 submittal, (Reference 2.9), the range of the pressurizer pres-i sure transmitters will be modified if the resolution of the ATWS issue indicates the need for such an upgrade.
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(E4) 2.
A design analysis and evaluation of inventory trend instrumentation, and test data to support design in item 1.
The design analysis and evaluation of the ICC detection instrumenta-tion is addressed in reference 3.2.
Addi tional infonnation on the I design analysis and evaluation is provided in reference 3.8.
Refer-ence 3.1 provides answers to previous NRC questions regarding the HJTCS.
Test data to support the design of the HJTCS is provided in refer-ences 3.3, 3.4, and 3.6.
NRC analysis of these evaluations is provided in reference 1.2.
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(E4) 3.
Description of tests planned and results of tests completed for evaluation, qualification, and calibration of additional instrumen-tation.
Systen qualification and system verification testing is discussed in sections 5.0 and 6.0 of reference 3.2.
Additional details and test documentation is provided in references 3.3, 3.4, and 3.6.
A functional test procedure, designed to verify performance of the QSPDS, including sof tware routines and proper display functioning, has been prepared and pe rfo med.
Additionally, a hardware test procedure, designed to ensure proper function and calibration of the QSPDS microprocessors, has been performed.
Results of these tests indicate correct and satisfactory perfomance of the hardware, sof t-ware, and display equipment.
Portions of these tests will be incor-l po rated into a routine systen test procedure to demonstrate and assure continued system performance and calibration of the ICCI asso-ciated instrumentation.
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(E4) 4.4.
Describe the use of the primary and backup displays.
What training will the operators have in using the core exit thennoccuple instrumentation?
How will the operator know when to use the core exit thermocouples and when not to use them?
Reference appropriate emergency operating quideline where applicable.
The primary ICCI displays are the plant SPDS CRT's located in the control room.
The backup displays are the QSPDS Plasma Display Units (PDU's) mounted in the QSPDS panels in the con-trol room.
The backup displays are required for operator use only in the event the primary SPDS displays are not operable.
Emergency Operating Procedures (EOP's) consistent with the standard C-E EPG's are currently being developed.
Training in the use of the CET's will be covered when these plant-specific E0P's are finalized.
The District's submittal of April 15, 1983 (Reference 2.3, ) provides a general description and schedule for the upgraded E0P's.
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(E4) 4.7.
Confirm the environmental qualification of the core exit thermocouple instrumentation up to the isolation device.
The core exi t thermocouples their associated cabling, the QSPOS microprocessors and displays and the isolation device in the QSPDS (i.e., the fiber optic modem) are qualified for use in their respective enviroments.
See response to iten 1 of Appendix B to NUREG-0737, contained in this submittal on
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Page 40.
mm 34
8 (E4) 2.
Single failure analysis Two physically separate, electrically isolated trains of ICC instru-mentation are provided.
No single failure within either the instru-i mentation, its auxiliary supporting features, or their power sources concurrent with the failures that are a condition or result of a specific accident will prevent the operators fran being presented the ICC information.
In the renote possibility that one conplete channel of instrumenta-tion is lost, there is sufficient diversity of information (e.g.,
hot and cold leg tenperatures, pressurizer pressure, subcooled margin, reactor vessel l evel, e tc. )
presented by the surviving channel to prevent infonnation ambiguity.
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O"*.
(E4) 3.
Class 1E power source Each channel of the QSPDS, including HJTC heater control and HJTC, SMM and CET signal processing, the backup displays, and the class IE to non-1E isolation devices are powered fran the station's vital instrumentation buses.
These buses are energized from the station standby power sources and are backed up by batteries.
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