ML20098G332
| ML20098G332 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/28/1984 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| LIC-84-323, NUDOCS 8410040385 | |
| Download: ML20098G332 (6) | |
Text
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O Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 September 28, 1984 LIC-84-323 Mr. James R. Miller, Chief U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285 8
Dear Mr. Miller:
Evaluation of Inadequate Core Cooling Instrumentation Systen for the Fort Calhoun Station Unit No.1 l
The Omaha Public Power District received your letter dated July 11, 1984.
By letter dated August 2,1984 (LIC-84-250, R. L. Andrews to J. R. Miller) the District infonned your of fice that the requested infonnation concerning the subject would be provided by September 30, 1984. Accordingly, please find attached the District's response.
Sincerely, n
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p d R.'L. Andrews
/
Division Manager Nuclear Production l
RLA/DJM/rh-C Attachments cc:
LeBoeuf, Lamb, Leiby & MacRae i
1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. E. G. Tourigny, NRC Project Manager Mr. L. A. Yandell, Senior Resident Inspector 8410040385 840928 a
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The July 11,.1984 letter (J. R. Miller to W. C. Jones) contained Enclosure 1,
" Request for Additional Infomation - Omaha Public Power District's Proposed Inadequate Core Cooling Instrumentation System for Fort Calhoun Station Unit No. 1."
The District's responses are as follows:
1)
Describe the status of the RVLMS installation including a schedule for completion.of installation and calibration and provide a sketch to show the locations of those thermocouple sensors relative tc the reactor size.
Response
The installation of the RVLMS is essentially complete. Reactor head modifications, heated junction thermocouple (HJTC) probes installation, in-containment mineral-insulated (MI) cable installation, and Qualifled Safety Parameter Display System (QSPDS) installation have been accomp-lished. The RVLMS is currently undergoing an Operational Availability Demonstration Test and will be left running throughout the renninder of this operating cycle. This is to prove reliability and to allow person-nel to gather experience with the system. Since plant startup from a refueling outage in July,1984, the system has shown excellent reliabil-
'ity.
Providing this performance continues, the system will officially be declared operable after the end of the n?xt refueling outage, cur-rently scheduled to begin in December,1985 (reference Attachment 2 for detailed schedule). A core map showing relative Core Exit Thermocou-ples (CET's) and HJTC locations is attached, (see Figure 1).
2)
Provide detailed plant for upgrading the core exit thermocouple systen with respect to conformance with the design requirements of NUREG-0737, Item II.F.2. and identify deviations, if any. Also, provide the follow-ing information:
a.
How many CET's will be upgraded? When will the upgraded systs.
be completed?
b.
What is the qualification status of CET caFles, connectors, pene-trations and compensation junction boxes?
Response
Twenty-eight (28) detectors were replaced in 1983 with ICI's which include a CET in each detector. A qualified thermocouple design is provided in this assembly. Thermocouple perforwance is guaranteed to 1650'F and calibration to this temperature features an accuracy of 14*F to 530*F and t3/4% to 1650*F. Thermocouple type testing has been conducted to 2300'F to verify integrity and function. These Class 1E qualified CET's are connected to the Class 1E QSPDS via LOCA-qualified MI cable in containment, and Class 1E qualified organic car,le outside containment. Primary CET display in the control room is the Emergency Response Facility Computer System (ERFCS) and backup is the seismically qualifled Class 1E QSPDS.
No known deviations fram thm requirements of NUREG-0737, Item II.F.2.
exist. The CET system is qualifted,' including CET's, cables, connect-
. ors and penetrations. No compensation junction boxes are provided as this function is performed-in the Class 1E QSPDS.
As stated in Item 1, above, installation of the system is complete; how-ever, the system will not be declared fully operable until after the end of the next refueling outage (Also see Attachment 2).
I c.
How many CET's will be used for the backup display and how many
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CET's will be used for the primary display? If the same CET sig-nal is used.for both backup and primary display, will there be a qualified isolation device for signals to the primary display?
Response
Twenty-eight (28) CET's will be used for both the primary'and the back-up displays.
Isolation between the two systems is accomplished by means of. a fiber-optic data link between the QSPDS and the ERFCS.
-3)
Provide an 'evaluatio.1 af the final SMM with respect to NUREG-0737, Appendix-B design requirenents and identify deviations, if any.
Response
The existing Subcooled Margin Monitor (SMM) incomorates a Class.1E de-
' sign and confoms with the design requirements of Appendix B to NUREG-0737 with the exception of the qualificatian status and range of the primary system RTDs.. Additionally, recording capability for the exist-ing SMM is not provided.
The District has investigated certain methods for upgrading the primary system RTDs including complete replacement, addition of new RTDs in the primary system piping, signal sharing, etc. This investigation is on-going and the District believes that an SMM that confoms fully with the requirements of NUREG-0737 will be installed and operable following the 1985 refueling outage.
The final SMM will be the QSPDS with primary display and recording capa-5flities provided by the ERFCS and backup display by the QSPDS.
4)
In addition to the primary display for ICCI (Critical Function Monitor-ing System), two backup displays will be installed.
Identify the type and function of these two backup displays, and provide the completion schedule.
Response
The backup displays are Class 1E, seismically qualified plasma display units (PDUs) supplied as part of the Combustion Engineering QSPDS. The units are neon gas discharge type. They are currently located in the control room, mounted in the QSPDS cabinets. Determination of the final display location will consider results of the Detailed Control Room Design Review (DCRDR) currently in progress. These displays util-ize human factors engineering principles to provide alphanumeric dis-ply of safety parameters including ICC parameters. These displays
. will serve as backup to the primary SPDS, each displaying one-half of the safety-related parameters. Completion date, as stated above, is the end of the 1985 refueling outage.
- to the July 11, 1984 letter (J. R. Miller to W. C. Jones), en-titled'" Milestones for Implementation of Inadequate Core Cooling Instrumenta-tion," provided a list of items which rust be completed in order to fully implement the ICCI system.- The Safety Evaluation (SE) requests that these milestones be incorporated into the Fort Calhoun Unit No.1 schedule and be provided for staff review.
Accordingly, the follewing represents the milestone dates for itens found in.
It should be noted that these are only milestones and do not represent finn regulatory commitment dates.
1.
Submit final design description (by licensee) (complete documentation requirements of NUREG-0737, Item II.F.2, including all plant-specific information items identified in applicable NRC evaluation reports for generic approved systens).
Milestone Date:
June 1985 i
2.
Approval of emergency operating procedure (EOP) technical guidelines (by NRC).
NOTE: This E0P technical guideline, which incorporates the selected system, must be based on the intended uses of that system as described in;3pprovcd generic E0P technical guidelines relevant to the selected system.
Milestone Date:
January 1985 3.
' Inventory Tracking Systen (ITS) installation complete (by licensee).
Milestone Date:
30 days after the end of the 1985 refueling outage.
4.
ITS functional testing und calibration complete (by licensee).
Milestone Date:
30 days after the end of the 1985 refueling outage.
5.
Prepare revisions to plant operating procedures and emergency proce-dures based on approved E0P guidelines (by licensee).
l Milestone Date:
30 days af ter the end of the 1985 refueling outage.
6.
Implementation letter report to NRC (by licensee).
[
Milestone Date:
6 months after 1985 refueling outage 7.
Perform procedure walk-through to complete task analysis portion of ICC l
system design -(by licensee).
Milestone Date:
Prior to 1985 refueling outaga 8.
Turn on systen for operator training and familiarization.
Milestone Date:
Currently the system is turned on for testing and fam-iliarization and will be used for some training pur-poses beginning the summer of 1985. Official train-ing will not begin until completion of #5 and #7.
f 9.
Approval of plant-specific installation (by NRC).
~
Milestone Date:
90 Days After #6 10.-
Implement modified operating procedures and emergency procedures (by
. licensee).
Milestone Date:
60 Days After #9 t
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