ML20062G228

Summary of 781215 Meeting of Tech Review Comm for Review of Temp Fluctuations in Subj Facil.Topics Discussed Incl Comparison of Displacement Probe & Nuc Detector Signals & Info on Core Status

ML20062G228
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/19/1978
From:	Fry D OAK RIDGE NATIONAL LABORATORY
To:	Ireland R Office of Nuclear Reactor Regulation
References
NUDOCS 7812270182
Download: ML20062G228 (17)

Text

s

'i OAK RIDGE NATIONAL LABORATORY  !

CPERATED BY union CARBIDE CORPORATION ,

NUCLEAR DIVISION O

POST OFFICE BOX X OAK RIDGE, TENNESSEE 37830 December 19, 1978 4

Mr. R. E. Ireland Technical Advisor to Assistant Director For Reactor Safety Division of Systems Safety Office of Nuclear Reactor Regulation Nuclear Regulatory Comission Washington, DC 20555

Dear Dick:

Minutes of the December 15, 1978 Meeting of the Technical Review Comittee for Review of Temperature Fluctuations in Fort Saint Vrain The subject meeting was held in Oak Ridge to discuss the problem of temperature fluctuations in FSV. The meeting agenda and a list of attendees is attached.

Sumary of December 14 Heeting 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 b, pass 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), uAC postulates that vertical

• gaps (" jaws") are opening between fuel elements near the top of individual region coluans and that the above ~40". flow increase could be caused by ~20 gaps in one region of ~0.4-0.45 inches in height each.

OV x% 1 1 7812270137_

4

-R. E. Ireland 2 December 19, 1978 f Summary 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 -

1 Report" and submitted a draft report of their review to NRC. The t review included an evaluation of the model used by GAC to calculate i 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 recomend that in-core mechanical instrumentation be

installed as soon as possibl.e because although it is unlikely that ,

i structural damage is occurring, it can not be precluded without data l from in-core instrumentation. 7 I

i t

Comparison of Displacement Probe and Nuclear Detector Signals I i

ORNL has performed a preliminary analysis of FM tape recordings of PCRV i,

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 j probes do not reliably indicate core component motion. -

i i 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 i

.only DP-2 provided useful data. DP-3, 4, and 5 probes were added and the probe design improved for the November 1978 test. Figures 2 and 3 I show that during an oscillation test on April 23, 1978 the PCRV displacement [

probes showed a significant increase in PCRV motion when fluctuations  ;

I were observed on the neutron detector. Therefore, GAC used information i

j obtained from the displacement probe, DP-2, in the April tests to support t their conclusion that the maximum velocity of core internals movement  !

was 5 inches /second. They have not made velocity estimates from data I  !

j obtained with the presently installed displacement probes because they

[

have observed signals from the sensor when the plant is not fluctuating i (or even shutdown). '

, t We have analyzed the probe signals during a single fluctuation event taken 'from the data record obtained on November .4,1978. Figures 4 and 5' i

- i show the offsets that occured on two of the neutron detectors 'at ~4:15-i

' 4:16 AM (This is approximately when large temperature fluctuations were ,  ;

f i

observed at the exits of regions 12 and 13). Note that the fluctuations '

4 in power were only 2 or 3% whereas the power fluctuated by 6-10% in Apr_il (See Fig. 2). Even so, DP-1, 2, 4, and 5 probes indicate increased j activity in the _NW-SE direction at the time of the fluctuation on -

l November 4th (See Figs. 6-10). DP-3 does not indicate any PCRV motion  !

in the NE-SW direction. i Based on these observations the review comittee concludes that it'is premature to discount the infomation that is provided by the presently i installed displacement probes. Furthermore, we strongly recomend that i four additional probes be installed, tangential probes at NW, SE and NE

! locations and a radial direction probe at the NE location.  !

1

! i I

1 L

R. E. Ireland 3 December 19, 1978 l

t Additional Technical Information Needed 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 '

a. Drawings showing exact location (also requested in December 13 letter) of probes and the dimensions of the probes

b. Logic behind selecti'on of probe type and locations

'2. Core cross-section draw.ng 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, i.e., core blocks, pads, support posts, etc. down through the thermal barrier. (Some of this information may be redundant with ,

request item 2 of December 13 letter).

t 1

5. Information on core status for 4:10-4:40 AM on November 4, 1978

a. Feedwater flow vs time r

b. Reheat steam temperatures and flow vs time

c. Region orifice valve settings

d. Region peaking factors

e. Equations used to calculate individual steam generator inlet helium temperatures from region outlet temperatures i

f. Region outlet temperature mismatch '

6. Orifice settings, peaking factors and region outlet temperature mismatch maps immediately 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 a I I

I e

. ~ .

[

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 fuel blocks cause potential restriction of shim rod movement?

t

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 The review goals listed in my letter to you on December 13 were accepted by the comittee on the condition that item 2 be expanded to include suggestions for any new instrumentation that will provide additional infonnation about the problem.

Specific Review Tasks Initial review tasks established by the committee are:

1. Review in-core instrument package design and recommend modificatfor.s 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. Compare orifice valve settings, peaking factors and region outlet temperature mismatch for all oscillation events where this data is l available.

( -

l 6. Perform dynamic calculations to simulate regions 12 and 13 temperature fluctuations, B1-1 and B1-4 helium inlet temperatures and steam outlet temperatures from 4:10 to 4:40 AM on November 4,1978.

t .

6 r .o

.* 3 R. E. Ireland 5 December 19, 1978 f

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 i 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. j 1

Assignment of Review Tasks '

The following assignments have been agreed upon by committee members: .

I Task No. Person in Charge

+

1 '

All Members 2

Joel Bennett and Chuck Anderson (LASL) 3 Dwayne Fry (0RNL) 4 Dwayne Fry (0RNL) 5 Walt Eatherly (ORNL) 6 Syd Ball (0RNL) l Future Committee Meetings i

Committee meetings will be scheduled when requested by any member or to ,

review the results of the above task work.

Sincerely, 1 Dwayne N. Fry >

Instrumentation and Controls Division cwl cc: C. A. Anderson, LASL S. J. Ball 1 J. G. Bennett, LASL '

R. S. Booth S. J. Ditto W. P. Eatherly R. K. Kibbe 1 R. C. Kryter 1 L. C. Oakes  ;

L. E. Phillips, HRC/ DSS i F. R. Mynatt J. D. White I

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4 Decerrlaer 15, 1978 Meeting of Technical Review Committee for Review of Temperature Fluctuations in Fort Saint Vrain Agenda

1. Summary of December 14 meeting at NRC by Fry.

2. Summary 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.

S. Establish review goals for the committee.

6.

Discussion review of what specific review tasks must be done to accomplish goals.

7. Establish completion dates for review tasks.

8. Assign review tasks.

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