ML19289C363
| ML19289C363 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/04/1979 |
| From: | Speis T Office of Nuclear Reactor Regulation |
| To: | Justin Fuller PUBLIC SERVICE CO. OF COLORADO |
| Shared Package | |
| ML19289C364 | List: |
| References | |
| FOIA-81-127 NUDOCS 7901120095 | |
| Download: ML19289C363 (1) | |
Text
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- r UNITED STATES o
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, 'g NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 9 f*
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'%.'.'"... o' JAN 4 1979 Docket No. 50-267 A
Mr. J. K. Fuller, Vice President Public Service Company of Colorado P. O. Box 840 Denver, Coloradv 80201
Dear Mr. Fuller:
Enclosed are three letters: one from ORNL dealing with their calculation of postulated DBDA and LOFC accidents for FSV; one from LASL transmitting their comments on your report " Core Fluctuatien Investigation Status and Safety Evaluation Report" dated August 11, 1978; and one from ORNL transmitting minutes of a December 15, 1978 meeting of a Technical Review Committee for Review of Temperature Fluctuations in Fort St. Vrain.
In the minutes of the December 15, 1978 meeting several requests for additional information are presented on page 3.
Would you please provide us with the asked for information by January 31, 1979.
We would like to have your comments on these three letters. Should you have additional questions please let me know.
Sincerely, shemis P. Speis, Chief Advanced Reactors Bianch Division of Project Management
Enclosures:
As stated cc: Bryant O'Donnell, Esquire Kelly, Stansfield & 0'Donnell 990 Public Service Company Building THIS DOCUMENT CONTAINS Denver, Colorado 80201 POOR QUAU1Y PAGES James B. Graham Manager, Licensing and Regulation East Coast Office General Atomic Company 2021 K Street, N.W.
Suite 709 Washington, D. C.
20006
?S01120097
OAK RIDGE NATIONAL LABORATORY CPtmatto av union CARBIDE CORPORATION NUCLEAR Pyl$10N POST OFFICE S0X X OAK RIDGE, TENNESSEE 3700 December 19, 1978 Mr. R. E. Ireland Technical Advisor to Assistant Director For Reactor Safety Division of Systems Safety Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, DC 20555
Dear Dick:
Minutes of the December 15, 1978 Meeting of the Technical Review Committee for Review of Temperature Fluctuations in Fort Saint Vrain The subject meeting was held in Oak Ridge to discuss the problen if temperature fluctuations in FSV. The meeting agenda and a list of attendees is attached.
Summary of December 14 Meeting at NRC I summarized GAC's presentation of their analysis and conclusions of the November 4,1978 oscillation event. Discussion centered around the unexpectedly large outlet temperature fluctuations observed in regions 12 and 13 and GAC's theory that the fluctuations are caused by flow redistribution in the core.
previously the fluctuations in region outlet temperature were small enough to be explained by leakage flow of cooler gap helium into the region outlet thermocouple sleeves.
Based on data from the November 4th event, GAC is now postulating that core motion causes flow redistribution in the core by opening and closing bypass gaps near the top of the core. GAC's calculations show that a 200*F region exit temperature decrease would be possible with a 40% region flow increase (a 181 F decrease in region 13 was measured during the November 4th event). GAC postulates that vertical gaps (" jaws") are opening between fuel elements near the top of individual region columns and that the above ~40% flow increase could be cautad by ~20 gaps in one region of ~0.4-0.45 inches in height each.
PW g f;;G7o (D
R. E. Ireland 2
December 19, 1978 Sur. nary of LASL Review of GAC Mechanical Model J. G. Bennett and C. A. Anderson of LASL have reviewed the PSC document entitled " Core Fluctuation Investigation Status and Safety Evaluation Report" and submitted a draft report of th~eir review to NRC. The review included an evaluation of the model used by GAC to calculate loads on individual elements caused by core motion. Anderson stated that the calculated loads may be questionable because of various assumptions and omissions of the model. Based on their review, Bennett and Anderson recormend that in-core mechanical instrumentation be installed as soon as possible because although it is unlikely that structural damage is occurring, it can not be precluded without data from in-core instrumentation.
Comparison of Displacement Probe and Nuclear Detector Signals ORNL has perfomed a preliminary analysis of FM tape recordings of PCRV displacement probe signals during oscillation Runs 10 (April 23,1978) and 31 (November 4, 1978). The ORNL results seem to refute the observations made by GAC that the five presently installed displacement probes do not reliably indicate core component motion.
Figure 1 shows the location of neutron detectors and PCRV displacement probes. DP-1 and DP-2 were installed for the April 1978 tests but only DP-2 provided useful data.
DP-3, 4, and 5 probes were added and the probe design improved for the Novemoer 1978 test. Figures 2 and 3 show that during an oscillation test on April 23, 1978 the PCRV displacement probes showed a significant increase in PCRV motion when fluctuations were observed on the neutron detector. Therefere, GAC used information obtained from the displacement probe, DP-2, in the April tests to support their conclusion that the maximum velocity of core internals movement was 5 inches /second. They have not made velocity estimates from data obtained with the presently installed displacement probes because they have observed signals from the sensor when the plant is not fluctuating (or even shutdown).
We have analyzed the probe signals during a single fluctuaticn event taken from the data record obtained on November 4,1978.
Figures 4 and 5 show the offsets that occured on two of the neutron detectors at ~4:15-4:16 AM (This is approximately when large temperature fluctuations were observed at the exits of regions 12 and 13). Note that the fluctuations in power were only 2 or 3% whereas the power fluctuated by 6-10% in April (See Fig. 2). Even so, DP-1, 2, 4, and 5 probes indicate increased activity in the NW-SE direction at the time of the fluctuation on November 4th (Cee Figs. 6-10). DP-3 does not indicate any PCRV motion in the NE-SW direction.
Based on these observations the review committee concludes that it is premature to discount the information that is provided by the presently installed displacement probes. Furtnermore, we strongly recocmend that four additional probes be installed, tangential probes at NW, SE and NE locations and a radial direction probe at the NE location.
R. E. Ireland 3
December 19, 1978 Additional Technical Information tieeded by the Committee In addition to the information requested in my December 13, 1978 letter to you the committee needs the following information in order to proceed with their review of the problem:
1.
Displacement probes Drawings showing exact location (also requested in December 13 a.
letter) of probec and the dimensions of the probes b.
Logic behind selecticn of probe type and locations 2.
Core cross-section drawing showing nominal hot gap widths for all components 3.
Boron content and configuration of spacer blocks and basis for statement that these spacer blocks do not move 4.
Detailed dimensional drawings of region between upper part of top plenum and top of fuel especially dimensions and configuration of orificing system. We also need similar drawings of the core bottom, f.e., core blocks, pads, support posts, etc. down thrcagh the thermal barrier.
(Some of this information may be reaundant with request item 2 of December 13 letter).
5.
Information on core status for 4:10-4:40 AM on flovember 4,1978 a.
Feedwater flow vs time b.
Reheat steam temperatures and flow vs time Region orifice valve settings c.
d.
Region peaking factors Equations used to calculate individual steam generator inlet e.
helium temperatures from region outlet temperatures f.
Region outlet temperature mismatch 6.
Orifice settings, peaking factors and region outlet temperature mismatch maps imediately before and after every oscillation event since October 31, 1977.
7.
Detailed design and installation location of proposed scratch gauges that will be installed during refueling.
R. E. Ireland 4
December 19, 1978 In addition to the above requests for specific information, various committee members have raised questions that can best be answered by GAC or PSC.
1.
Will graphite samples from fuel cycle 1 be analyzed to determine potential for stored energy?
2.
Has the possibility of broken core support posts been considered?
Could broken core support posts result in the NW-SE core motion and large region-to-region gaps with corresponding core flow redistribution?
3.
If the " jaws" theory is assumed, can the tilt in f_al blocks cause potential restriction of shim rod movement?
4.
Has fuel temperature been calculated for the central element in a fuel region with an orifice valve setting that is less than 5% open?
Committee Review Goals Ti.e review goals listed in my letter to you on December 13 were accepted by the committee on the condition that item 2 be expanded to include suggestions for any new instrumentation that will provide additional infomation about the problem.
Soecific Review Tasks Initial review tasks established by the ccmmittee are:
1.
Review in-core instrument package design and recommend modifications if necessary.
2.
Make recommendations for the testing surveillance and monitoring for in-core mechanical instrumentation including mechanical motion measurements to verify the " jaws" theory.
3.
Attempt to infer direction of core motion by correlating displacement probe signals with neutron detector signals.
4.
Determine velocity of reflector block movement associated with offsets on PpS neutron detectors.
5.
Ccmpare orifice valve settings, peaking factors and region outlet temperature mismatch for all oscillation events where this data is available.
6.
Perform dynamic calculations to simulate regions 12 ccd 13 temperature fluctuations, 31-1 and B1-4 helium inlet temperatures and steam outlet temperatures from 4:10 to 4:40 AM on liovember 4,1978.
R. E. Ireland 5
December 19, 1978 Completion Dates for Review Tasks We can not establish specific dates to complete the above tasks until the requested technical information is received.
However, we strongly believe that our review should be completed as soon as possible (hopefully not later than January 31,1979) in order to provide our input before the refueling shutdown scheduled for March 1,1979.
Therefore, it is imperative that we obtain the requested information immediately.
Assignment of Review Tasks The following assignments have been agreed upon by committee members:
Task No.
Person in Charge 1
All Members 2
Joel Bennett and Chuck Anderson (LASL) 3 Dwayne Fry (0RNL) 4 Dwayne Fry (ORNL) 5 Walt Eatherly (ORNL) 6 Syd Ball (0RNL)
Future Committee Meetings Committee meetings will be scheduled when requested by any member or to review the results of the above task work.
Sincerely, C
_ x..,j ' s-Dwayne N. Fry Instrumentation and Controls Division CWI cc:
C. A. Anderson, LASL S. J. Ball J. G. Bennett, LASL R. S. Booth S. J. Ditto W. P. Eatherly R. K. Kibbe R. C. Kryter L. C. Oakes L. E. Phillips, NRC/ DSS F. R. Mynatt J. D. White
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December 15, 1973 feeting of Technical Review Committee for Review of Temperature Fluctuations in Fort Saint Vrain Agenda 1.
Surcary of Dece=ber 14 meeting at NRC by Fry.
2.
Surcary of LASL review of GAC mechanical model by Anderson.
3.
Report of ORNL comparison of displacement gauge and nuclear detector signals by Fry.
4.
Determination of additional technical information needed by the committee.
5.
Establish review goals for the committee.
6.
Discussion of what specific review tasks must be done to accomplish review goals.
7.
Establish completion dates for review tasks.
8.
Assign review tasks.
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REFERENCE:
LETTER REPORT TO NRC ON THE PSC DOCUMENT ENTITLED " CORE FLUCTUATION INVESTIGATION STATUS AND SAFETY EVALUATION REFORT"
Dear Mike:
We have completed our review of the subject report. Our document covering this review is enclosed for your consideration. Any questions regarding this document can be addressed to J. G. Bennett, FTS 843-7888 f
or C. A. Anderson FTS 843-5150.
Sincerely, m
'> c Joq}/G.Bennett
Enclosure:
a/s CC:
150-5, w/o enclosure C. R. Emigh, 0-00/et, M.S. 572 W. G. Davey, Q-DO, M.S. 576 An Affirmative Action /Equalopportunity Employer I