ML20234D038
| ML20234D038 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Grand Gulf |
| Issue date: | 02/07/1975 |
| From: | Zudans Z FRANKLIN INSTITUTE |
| To: | Burnett P Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20234A777 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707070078 | |
| Download: ML20234D038 (4) | |
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J RESEARCH LABORATORIES THE B F. H J A M I N FRANKLIN PARKWAY *
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Ch, $,T GL/ 05 Fe3ruary 7, 1975 sewo 6'ut r Mr. Paul Burnett Advisory Committee on Reactor Safeguards
/1 g U.S. Nuclear Regulatory Commission Washington, D. C.
20545
Subject:
Meeting with Mississippi Power & Light Co.,
Bechtel Co., and Licensing Staff of NRC i
Dear Paul:
l Enclosed please finc my notes on the subject meeting.
Please distribute copies of these notes to Grand Gulf ACRS Subcommittee Members.
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Thank you.
t Very truly yours, I
LL0b s Zudans ZZ:ces Di ector enc 1.
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- z. zedeme February 7, 1975 MEETING REPORT To: ACRS, Grand Gulf Subcommittee Subject : Meeting with Mississippi Power & Light Co.,
Bechtel Co., and Licensing Staff of NRC Topic:
Dynamic Loads and Their Basis for Grand Gulf Nuclear Generating Station, February 5, 1975, Bethesda, Md.
1.
Bechtel Co. presented marked-up drawings showing static equivalent and dynamic loads on containment and drywell vessel walls and other structures in the annular space between the containment and drywell.
2.
Drywell wall and containment wall loads as shown by Bechtel consisted of pressures shown in Fig. 1.
These loads are supposed to represent the dynamic effects of the pool action only.
When questioned, Bechtel Co.
could not produce any information upon which these loads were based.
Staf f requested that such infvimation-be-supplied for this and other load-ings used for the design.
I raised the question about possible asymmetric effects, none had been included here or on any other parts.
I suggested that the sensitivity of the design to asymmetric components should be looked at.
3.
Other loads considered were those pertaining to platforms at various elevations.
Here Bechtel Co. is using loads as supplied by CE.
In general, it appears that Bechtel is leaning heavily on GE in the matter of dynamic pool loads, and has not developed an acceptable model for independent checking of GE's input.
4.
Loads due to relief valve discharge were also discussed.
Here, it appears that Bechtel Co. is in the process of designing a sparger type discharge and has attempted to use RELAP 3 computer code to compute the design param-eters.
However, that the application of RELAP,3 for this design is questionable and Bechtel Co. was asked to perform a simple sparger clearing analysis based on first principles.
Note that the first set of GE's relief valve discharge loads on drywell wall were in the order 0FFi K USE ON.Y --
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0FFICIAL JSE GU of 330 psi,. Bechtel Co. calculations (probably invalid 'due 'to the use of an' inapplicable computer code) came out to 26 psi and a later set of GE loads was given at 56 psi. The entire question of relief valve discharge design and loads remained unresolved.
Further communications between Bechtel Co., GE and Staf f will be required.
Conclusions Discussions at the meeting indicated that Bechtel Co. will have some problems with the construction schedule if an acceptable set of loads is not defined rather shortly.
It also appears that lack of ecntinued communications flow between CE and Bechtel Co. exists, which in part accounts for the lack of basic and definition of the level of conservatism for the loads currently used by Bechtel Co.
I do believe, however, that these matters can be resolved satisfactorily and without' harmful effect on safety related structures of the Grand Gulf Nuclear Power Generating Station.
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DIVISION BWR PROJECTShPARTMENT GENERAL ELEbIC COMPANY,175 CURTNER AVENUE, SAN JOSE, CAliFoRr Man Code.
Phone (408) 297 3000, TWX No. 910-3381-0116 B!'
January 27, 1975 b
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Assistant Director of iA,
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Directorate of Licensing N'N V Mf
.'p".d* 7 Office of Rerulation U.S. Atomic Energy Commission Washington, D. C.
20545
Subject:
mRK III VERIFICATION PROGR#f Recent discussions with you and your staff together with statements made in rc:M ACR3 letters for ark III projects, indicate th:t it m:r/ be beneficial to again briefly identify and summarize the objectives of the Mark III Verification Program.
The Mark III concept investigation began with small scale tests in 1971.
When the concept was determined to be viable, a standard containment was J
selected, a large scale test facility constructed, and testing began in November 1973 to verify the modeling for the Mark III with that configura-tion. The initial effort in the Pressure Suppression Test Facility (PSTF) was to verify the -vent;. clearing modeling which nas considered to be the most important aspect of the analytical prediction of drywell peak pressure and was due to the ch...:ge of vent configuration from previous pressure suppression containments.
be_om the initiation of this large scale testing program, infomation has Fr en made availaN e in the form of quarterly progress vcports.
Periodic meetings with you and your staff have also been held to discuss the pro-gram and PSTF resu1M.
In June 1974 a licensing topical report, NEDO-20533
" Mark III Analytical Model," was issued to present the model that GE would use for Mark III containment response analysis. As previously indicated, this report will be supplemented by April 1, 1975 to address expressed concerns and unexplained anomalies in the data presented to support the models. The remainder of the test program has been discussed in an attach-nent to the transmittal letter for the Seventh Quarterly Progress Report dated December 31, 1974. Data frcm the remaining testing will contribute to that already availnbie to support the analytical edels presented in NEDO-20533 as well as investinction cf cther LO M related phenc:.ena.
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b BE SURE To INCLUDC Mall CODE oN RETURN CoRRE'SpoNDENCE 3_.
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GEllERAL h ELECTRIC i
R. L. Tedesce i
Page 2 l
January 27, 1975 l
Attached to this letter is a matrix which presents a concise picture of l
what has been accomplished to date together with what we hope to accom-i plish during the remainder of the Mark III Verification Program.
This matrix str::marizes the effort that GE has established as necessary to verify the containment configuration which is being recommended to applicants that have selected the Mark III concept with their BhR. The l
left-hand column of the matrix is a list of the phenomena that are either known to occur during the response of a Mark III system to a loss-of-coolant accident or could potentially occur. The remaining columns answer the following questions.
1 1.
Is there or will there be experimental data which can be either directly applied to the Mark III system, or can be used for analytical model verification?
2.
For each phenomenon, what is the source of the information being used for Mark III design purposes?
3.
hhere is the information in item 2 documented?
4.
Does the documentation include any comparisons between model predictions and data?
In addition, there is a comments column which has been used for ampli-ification and clarification purposes.
These discussions with you and your staff Icad us to believe that there is particular interest in the GE position on items 18, 20, and 22.
The first item is the phenomenon of the drywell pressure undershoot that was observed at vent clearing during some of the earlier large-scale PSTF steam tests.
Based on comparison of test results, the phenomenon is believed to be peculiar to the scaling of the large-scale facility and therefore is not expected to occur in the full-scale thrk III.
This position is based on a consideration of the scaling factors associated with the configuration of the PSTF during the large-scale steam tests and is supported by data from the 1/3 scale tests, which were more appropriately scaled for this phenomena. These 1/3 scale tests did not experience the oscillations. Additional data supporting our position is obtained from the single vent full-scale tests in which proper scaling of vent area to drywell volume was present. This test also showed no pressure undershoot.
There is no real technical concern for the inpact of this phenomenon on Mark III because even if the phenomenon occurred in Mark III as observed in some of the large-scale PSTF tests, there would be no impact on design requirements. Therefore, there is no need to develop an analytical model capabic of simulating the pressure undershoot.
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GEHERAL h ELECTRIC R.'L. Tedesco Page 3 l'
January 27, 1975 The second' item is the phenomenon of pressure oscillations during the quasi-steady steam' condensation that.follows vent clearing. Oscillations have been observed in the PSTF but are small and not a controlling load-ing condition (+ 2 psi at 3Hz).
GE feels that analytical model development
.in this area is not required because currently available test data is directly applicable and confirms.the GE position that.over a wide range of blowdown conditions this phenomenon does not represent a significant Mark III design condition. The work involved to develop and verify a model in this area would be significant.
In comparison to the expected payoff; i.e., a better understanding of a relatively unimportant phenomena, i
l we cannot currently justify doing anything additional in these areas.
The third item is the " chugging" phenomenon associated with low, end-of-bloktlown steam mass fluxes. Again, the GE position is that representative i
data is available which show that the phenomenon does not lead to a sig-l-
nificant Mark III containment loading condition. Consequently, we have concluded that analytical models are not required.
If you still consider these to be areas of disagreement, a joint staff-GE generic containment meeting could be scheduled for further discussion.
i Such a meeting would permit us to discuss the matrix in general and to present our positions on items 18, 20, and 22.
We do plan to discuss pressure oscillations in the 8th PSTF quarterly report sto be published April 1,1975.
Further, a large body of data will be generated by the remaining PSTF test programs that are planned for 1975 and 1976. While not specifically directed at investigating pressure oscil-lation, these tests would provide feedback on the phenomenon if it were significant.
In the event of any unexpected developments, GE will reassess its position.
Please do not hesitate to call me or Mr. Sobon (Ext. 3495) if you have any questions regarding this information.
Sincerely, Geza L. Gyorey, Fhnager BWR Licensing Mail Code 632, Ext. 2245 GLG:s'mk Attachment
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