ML18051A388

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Submits Addl Response to Generic Ltr 82-28 Re Inadequate Core Cooling Instrumentation Sys.Core Exit Thermocouple Design Discussed
ML18051A388
Person / Time
Site: Palisades 
Issue date: 04/14/1983
From: Vandewalle D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
GL-82-28, OC0483-0005A-NL, OC483-5A-NL, NUDOCS 8304210403
Download: ML18051A388 (9)
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{{#Wiki_filter:*.i.,' e consumers Power company General Offices: 212 Wast Michigan Avenue, Jackson, Ml 49201 * (517) 788-0550 April 14, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - ADDITIONAL RESPONSE TO NRC GENERIC LETTER 82-28 (INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM) Consumers Power Company letter entitled "Response to NRC Generic Letter 82-28" and dated March 10, 1983 indicated that the core exit thermocouple evaluation would be provided by April 15, 1983. The Generic Letter contained a number of questions relating to core exit thermocouple design. These questions are answered below and provide a means of describing the core exit thermocouple design selected by Consumers Power Company. Question

1.

Provide diagram of core exit thermocouple locations or reference the generic description if appropriate.

Response

Figure 1 attached shows the 16 locations at which Core Exit Thermal Couples (CETC) will be upgraded to provide assurance that an adequate number of CETC will be available for post-accident core inventory analysis. Question

2.

Provide a description of the primary operator display including:

a.

A diagram of the display panel layout for the core map and description of how it is implemented, e.g., hardware or CRT display.

b.

Provide the range of the readouts.

c.

Describe the alarm system.

d.

Describe how the ICC instrumentation readouts are arranged with OC0483-0005A-NL02 830421.0403 830414. PDR ADOCK 05000255 p PDR

  • ~

-~ ' DMCrut~hfield, Chief Palisades Plant 2 Additional Response to Generic Letter 82-28 April 14, 1983 respect to each other.

Response

2.

(a) to (c): (d): Question The primary display and range of readouts of CETC will be provided by the generic Westinghouse microprocessor-based system as described in NUREG/CR-2628. Alarms will be provided within the existing control room alarm system. No core map presentation will be available. Reactor Vessel Level Instrumentation System (RVLIS) and CETC readouts will be located on panel Cll-A to the right rear side of the Control Room within 15 feet of the front control boards and control room operator desks (see Figure 2). This panel was added in 1981 to accommodate post-TMI additions, and is identical to of one section of the front board console existing main control panels.

3.

Describe the implementation of the backup display(s) (including the subcooling margin monitors), how the thermocouples are selected, how they are checked for operability, and the range of the display.

Response

3.

Backup display of the CETC will be provided via a data link from the primary Westinghouse system to the newly installed Critical Function Monitoring System (CFMS), which provides the Safety Parameter Display System (SPDS) function at Palisades. Although the display software has not been designed at this point, the capabilities of the CFMS will allow good flexibility for CETC selection, checking and display. In addition, the CFMS link will provide remote readout at Technical Support Center (TSC), Emergency Offsite Facility (EOF) and General Office Control Center (GOCC) facilities. Range of CETC readout will be consistent with the primary Westinghouse system as described in NUREG/CR-2628. Operability of CETC can be checked periodically during normal plant operation by; observing that the multiple readouts are all within a specific band and read the expected coolant temperature. Subcooled margin will be calculated and displayed by the generic Westing-house readout. Backup can be provided by the existing SMM display upgraded to NUREG-0737 requirements located on the front panel of the Control Room. Question

4.

Describe the use of the primary and backup displays. What training will the operators have in using the core exit thermocouple instrumentation? How will the operator know when to use the core OC0483-0005A-NL02

. I, DMCrutchfield, Chief Palisades Plant 3 Additional Response to Generic Letter 82-28 April 14, 1983

Response

exit thermocouples and when not to use them? Reference appropriate emergency operating guidelines where applicable. The Emergency Operating Procedures for use of this RVLIS and CETC system will be prepared in accordance with the schedule set forth in our response Generic Letter 82-33 (NUREG-0737 Supplement 1). A description of the procedures will be provided at that time. Operating Guidelines were submitted for the Westinghouse system by letter to D G Eisenhut entitled "Operating Guideiines - OG-64" and dated November 1981. Question

5.

Confirm completion of control room design task analysis applicable to ICC instrumentation. Confirm that the core exit thermocouples meet the criteria of NUREG-0737, Attachment 1 and Appendix B, or identify and justify deviations.

Response

Task analysis for ICCI has not been completed. This will be done during the design and prior to use of the ICCI. This activity is addressed in our response to NUREG-0737, Supplement 1. The criteria of NUREG-0737 are addressed in the response to question 8. Question

6.

Describe what parts of the systems are powered from the lE power sources used, and how isolation from non-lE equipment is provided. Describe the power supply for the primary display. Clearly delineate in two categories which hardware is included up to the isolation device and which is not.

Response

All components of the primary display system will be powered by a class lE source on a two-channel basis. To provide complete isolation, the CETC inputs to an existing computer based non-lE system will be removed. Thus, the signals will be isolated from other readout devices over the entire channel from the thermocouple in the reactor to the primary display class lE units. Isolation to the backup display will be provided via the data link. The power supply for the primary display will be provided by the preferred AC system. In the event of loss of offsite power the display will be powered by either the emergency diesel generators or the station emergency DC batteries. OC0483-0005A-NL02

PMCrutchfieid, Chief

  • Palisades Plant Additional Response to Generic Letter 82-28 April 14, 1983 Question
7.

Confirm the environmental qualification of the core exit thermocoup_le instrumentation up to the isolation device.

Response

7.

4 (a) The CETC is an integral part of the standard incore probe utilized in other CE reactors. The qualification of the thermocouple itself and probe leads/connector will meet the specifications common to this type of installation. (b) Cables and connectors used to carry the signal from the reactor head through the Containment Building (CB) penetration will be qualified by types to LOCA conditions. Cables will be routed or protected to assure no single High Energy Line Break (HELB) event leading to a LOCA will destroy all signals. Fire protection separation is not considered a criteria for CETC. (c) Outside the CB, cables will be routed or protected, as noted above, and will lead to a common reference cabinet inside the Control Room with no further interconnections. At this point, copper signal leads will be added to carry the signals to the Westinghouse generic readouts for processing. Thus, no isolation devices are required prior to the primary display units. Question

8.

Confirm explicitly the conformance to the Appendix B items listed below for the ICC instrumentation, i.e., the SMM, the reactor coolant inventory tracking system, the core exit thermocouples and the display systems.

Response

Consumers Power Company intends to explicitly address and comply with the items of NUREG-0737 Appendix B as part of the overall ICC! project. A summary of our plans for each ICC instrument is provided in the following table.

1. Environmental Qualification OC0483-000SA-NL02 SMM IEEE344-1975 IEEE323-1974 RVLIS Same as Generic Westinghouse System CETC IEEE344-1975 IEEE323-1974
  • DMCrutchfield, Chief Palisades Plant Additional Response to Generic Letter 82-28 April 14, 1983 Response (Continued)
2. Single Failure Analysis
3. Class lE Power Source
4. Availability Prior to an Accident
5. Quality Assurance
6. Continious Indication
7. Recording of Instrument Outputs SMM RVLIS CETC Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes*

Yes* Yes*

  • recording of instrument outputs will be provided on the backup display 5
8. Identification of Instruments As indicated in Westinghouse Generic System
9. Isolation IEEE384-1977 Nuclear Licensing Administrator CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0483-0005A-NL02 IEEE384-1977 IEEE384-1977

Consumers Power Company Palisades Plant Docket 50-255 - License DPR-20 ADDITIONAL RESPONSE TO GENERIC LETTER 82-28 (INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM) At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to Generic Letter 82-28 dated December 10, 1982, entitled "Inadequate Core Cooling Instrumentation System". Consumers Power Company's response is dated April 14, 1983. CONSTTMERS P. OWEbOMPANY {B f BY~~l3' ~~ R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 14th day of April 1983. \\~AMldJ)~ Sherry Lc.;furfey, Notary J~lic Jackson County, Michigan My commission expires November 5, 1986. SHERRY LYNN DURFEY Notary Pu~li~, Jackson County, .ll.~\\ My Comm1ss1on Expires Nov. 5, 1986 OC0483-0005B-NL02

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  • Consumers Power Company Palisades Plant ADDITIONAL RESPONSE TO GENERIC LETTER 82-28 (INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM)

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