ML20151Q561
| ML20151Q561 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/14/1984 |
| From: | Rahe E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Berlinger C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151Q556 | List: |
| References | |
| NS-EPR-2895, ST-HL-AE-2695, NUDOCS 8808110209 | |
| Download: ML20151Q561 (11) | |
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ATTACHMENT 3 s
l 3T HL AGOF c49s PArJ 4-11 anze Westin'ghouse Water Reactor PmpW m Electric Corporation Divisions NS-EPR-2895 March 14,1984 Mr. C. H. Berlinger, Qsief Core Performance Branch Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Camission Washington, D.C.
20555
/
SUBJECT:
Special Dropped Rod Tests
Dear Mr. Berlinger:
In the NRC evalu:tien of WCAP-10207 (Proprietary), WCAP-10298 (Non-Proprietary),
"Dropped Rod Methodology fcr Segative Flu Rate Trip Plants", it was noted that two plants with Westinghouse reactors planned to perform a more definitive test In November of 1983 of the Negative Flux Rate Trip response to dropped rode.
Westinghouse oc,tified the NRC of the successful completion of those tests, E. P. Rahe, Jr., Westinghouse, to C. H.
(Refer to letter NS-EPR-2851, 11/16/83, At that time, a comitinent was made to provide the test data in a forthcoming topical report on a new Westinghouse Reference Test Program for Berlinger, NRC).
Initial Startup (since this test is part of the current initial startup However, Westinghouse has been informed (by Ms. M. Chatterton, of
.F-k' prograrn).your staff) of the need for an earlier sutraittal of the test data.
In respnse f { to this request, the attachments provide the test data available to Wes 1
and our interpretation of the results. Based on NRC acceptance of this data, a 8
reference in the forthcoming topical report to this letter vill be made instead of providing the attached as part of the contents of the report.
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.h.< As can be seen from the test results, both plants tripped (or w It should be noted that the worth of the rods in both cases was l
5 significantly less than that determined in WCAP-10297 to result in acceptable rods.
DNBR values in the event a reactor trip did not take place. Thus it can be i
@g stated that the analysis assumptions of WCAP-10297 are consenative with respcet co a.o.
Based on NRC acceptance of the attached plant data to actual plant behavior.
and the above Westinghouse conclusion, Westinghouse will reccernend the deletion
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f of the Dropped Rod Test at 505 RTP to all plants of current Westinghouse design
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which hav e not performed this test as part of their initial startup test programs.. Westinghouse will reco::nend the inclusion of this test on new reactor
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ATTACHMENT 5 NS-EPR 2895 ST HL AE Str9s PAGE 'iOF lt core designs where the worth of the rods are significantly different free i
current values. If you have any ge stions concerning the above or the attached, please contact either D. G. Bevard, Manager, Advanced Plant and Fuel Licensing (41.2/374-5597), or C. R. Tuley (412374-4172).
Very truly yours, N
lh E. P. Hahe, Jr., Manager
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Noelear Safety Department kRT/dr Attactnents e
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. ST.HL AE 0915 PAGE L0f it NS-E?R-Ze95
.t ATTACHENT 1 A four loop plant performed the test at approxinstely 505 RTP by defeating the negative flux rate trip on NIS channel N-42 and dropping rods K-10 and F-10.
Based on the two rod positions, either N-42 or N 44 could have been defeatec, see Figure 1.
To perform the test, rods K-10 and F-10 were held by the stationary grippers while the rest of the rods 1, the group were held by the stationary grippers and the movable grippers. The stationary gripper coil current was then disconnected allowing the two rods to fall into the core. As can be seen on Figure 2, N-42 and N-44 tripped at about the same -time.
N-41 and N43 also tripped at approximately the same tirse completin6 the make-up of the 2/4 logic (please note N 42 was defeated, thus the logie was not made-up tritil either N-41 or N 43 tripped).
It can also be seen on Figure 2 that the fourth channel (either N-41 or N-43) tripped barcre the Reactor Trip Breakers opened.
Tne worth of K-10 and F-10 tcgether was about half of that analyzed in WCAP-10297 (Q
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AITACHtENT 2 A three Icop plant performed the test at approximately 505 RTP by defeating the negative flux rate trip on all four NIS channels and dropping rods D U and D-12.
Based on Figure 3, it can be seen that L42 and M3 would be expected to trip 4
quickly since the rods were positioned directly-in front of the detectors.
Inspection of Figures 4 and 5 will confirm that this is just what happened. The third channel to trip was M1. Since all four channels' trip functions were defeated, no reactor trip signal was generated, however as can been seen on Figure 4, the time interval between the tripping of b42 and N-41 is ~0.6 seconds. N-44 did not trip on this test, but as can be seen on Figure 5, the output of the rate circuit was close to the trip setpoint. The worth of D-4 and D-12 is about 40% of the rod worth analyzed in WCAP-10297 Allowing for the icw rod worth and performance of the test at ~505 RTP, not 1005 RTP, it can be safely assumed that N-44 would have tripped on a rod worth closer to that
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f on Figures 4 and 5, three outputs for each channel are recorded, the Power N
Level, the Rate Circuit, and the Negative Rate Bistable. A signal comen to Q
both figures is the output of the Rods Have Moved Relay. This relay is triggered by the rod position indication systs when the two rods were detected to have begun to fall.
As can be seen on the two figures, the power level and rate output showed rod insertion before the RPI systern.
Figure 6 is a recording
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of the outputs of the four Rate Circuits on a 'sid:. by side basis. The degree of output change can be compared on a relative basis quite easily. Based on such a ccaparison, it can be seen that N-44 was close to the trip setpoint.
In conclusion, based on inspection of the results of Attac!vnents 1 and 2, it was verified that Westinghouse plants trip on the third Negative Flux Rate channel when a pair of rods of significantly less worth than that analyzed in WCAP-10297 are dropped in the core. Based on Westinghouse analysis, the need for continued perfor:r,ance of the negative. flux rate trip test is unnecessary. No additional relevant information is expected unless major core or control rod redesign t.akes place, resulting in significant changes in individual or rod pair worths.
Therefore, Westinghouse recocrnends the deletion of this test from the initial startup test program.
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Westinghouse, to C. H. Berlinger, NRC.
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