ML19312B251
| ML19312B251 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/23/1989 |
| From: | Cox J DUKE POWER CO. |
| To: | Jabbour K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19312B252 | List: |
| References | |
| NUDOCS 8906220014 | |
| Download: ML19312B251 (3) | |
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May 23, 1989 L.
L Docket Nos.. 50-413/414 Kahtan N.=Jabbour, project Manager.
project Directorate, II-3 Division of p.eactor-projects.- I/II Office of Nuclear Regulation
Subject:
. Duke power Response to NRC Letter on Simulator.
s Certification Documentation Inadequacies
Reference:
NRC Letter to James W. Cox, March 16, 1989
='
Dear Mr. Jabbour,
Enclosed is Duke power Company's response to the March 16 letter-referenced above. We have determined that the simplest method of providing the information' you have requested is to submit an appendix for each concern.. Below is the response to each of the comments in the enclosure of the March 16 letter with a description of changes made:
1.
Appendix Volumes A-K, for enclosure items la-Ig: All performance test A
abstracts in the appendix are the-actual " signed off" copies.of.~the working-V' docament; i.e., approval records are signed,..results forms.are completed and signed, remarks forms are completed (where applicable),-field change' notices are completed (where applicable), and' data-sheets'are. completed.
Also, the latest transient test results are included in the appendix.
Transient test result sheets are ccmplete,-and the graphs comparing 4 simulator data to the reference data are included. To reduce the volume of i
documentation, raw data'for each transient test was not included in the abstracts.
However, a sample of the raw data for a single test was included in the appendix for your reference.
The raw data for all i
transient tests is maintained on site in hard copy, and the latest run of each transient on magnetic tape. We will gladly furnish this data for any of the transient tests upon your request.
For enclosure $ tem 1-1: Each of the performance tests performed for initial certi.1 cation were completed satisfactorily, documented by the date and signature on the test approval' record.
'For enclosure item 1-2:
While many of the' Catawba performanceLtests were written to ensure plant operating procedures could be executed properly on-the Simulator, there was a tremendous volume of baseline data used to ensure l.
fidelity to the reference plant-(see Simulator Design Database Master Index, section III.C.2).
This type of data-may be ine:luded in a i
performance test or may be referenced directly or indirectly by the test, Baseline data for transient tests is described in. response to enclosure comment #2.
We will gladly respond to any specific questions you may have on baseline data used in Simulator construction or testing.
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s, Kahtan H. Jabbour, project Manager May 23 1989 page 2 For enclosure comment 1-3:
Any deficiencies found as a result of a Factory Ac:eptance Test were documented on " Trouble Report" fonne, or "TR's".
Any'TR's generated for a perfornance test have been referenced on 1
the test procedure remarks or results forms for that test. Note that all TR's generated as a result of a-performance test performed for Initial Certification have been cleared (i.e., problems corrected).
Sinue there are over 2500 cleared trouble reports, these were not included in the certification submittal. We will furnish any.of the. Trouble Reports upon request.
2.
Appendix Volume K, Transient Selection Justification: A report generated by Duke Power's Reactor Safety group has been prepared to justify the selection of the sixteen transients used in the annual testing program.
This report is included with the transient test abstracts and annual-transient test descriptions in the amended submittal (II.D.1.c & II.D.2.c).
We feel that the sixteen transients selected by the Reactor Safety Group are more comprehensive than the, example transients listed in ANSI /ANS-3.5-1985-and fully meet the intent of the Standard.
Note that the acceptance criteria for each of the transients includes:
6.2 Any critical parameters shall be withir. + or -2% of estimated values.
rs 6.3 Any non-critical parameters shall be within + or -10% of estimated'
(,)
values.
These acceptance criteria do not apply to transient tests, or any otheru annual performance tests, other than the Steady State operation Tests.
These criteria will be deleted from the annual performance tests, except for the Steady State Operations Tests.
l 3.
Appendix Volumo K, Unit 2 Simulation: The Catawba Unit 2 simulation is used specifically to train on the operation of the D5 steam generator below 30%
power. At low power, the response of the Unit 2 D5 S/G is significantly different than that of the Unit 1 D3 S/G.
Core life has little or no effect on the steam generator response.
Therefore, several initial conditions between 0 and 30% power at a single core life are sufficient to meet the desired Unit ? training objectives. Unit 1 serves as the reference plant for the Simulator. An updated List of IC sets is supplied in conjunction with item four below.
4.
Appendix Volume K, Initial Conditions: The value for the pressurizer temperature field on the " List of Initial Conditions" has been corrected per Simulator Work Request SYS-06. Additionally, the field for xenon worth that was previously blank has been changed to include xenon worth in pCM.
The corrected list of initial conditions has been included in the appendix.
71fferences between the original and corrected. list of initial conditions other than those mentioned are a result of normal simulator Initial Condition maintenance.
Oh h
Kahtan N. Jabbour,-Project Manager 7.s) ;
May 23 1989
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Page 3 5.
Appendix Volume K, Procedure Comparison: Apparently, an early revision of the " Operating Procedure Comparison" was assembled into the original i
submittal inadvertently.
Our master copy shows the same error as well as i
other typographical errors. The proper version has been included in the s
amended submittal.
Please forward any questions or comments to Games W. Cox, Manager of Catawba Nuclear Station Training, 803-831-3219.
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hosW.Cox,TrainingManager P
Catawba Nuclear Station SAB/GES/gbj Enclosure cc:
W. H. Barron S. R. Frye J. W. Cox H. B. Barron L. Hindman l
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