ML17320A973
| ML17320A973 | |
| Person / Time | |
|---|---|
| Site: | Cook, 05000000 |
| Issue date: | 11/22/1983 |
| From: | Abramson P, Wei T ARGONNE NATIONAL LABORATORY |
| To: | Guttmann J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17320A970 | List: |
| References | |
| CON-FIN-A-2311 NUDOCS 8404040323 | |
| Download: ML17320A973 (9) | |
Text
ARCONNE NATIONAL%4BQRATORY K6Sour's Avc~Aaq~ lllimis60439 tEI~~3l2/972 4868 November 22, 1983 Mr. Jack Guttmann Reactor Systems Branch Division of Systems Integr ation Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Review of ?TSPWR2 Under Task I.A of FIN A2311
/
Dear Mr. Guttmann:
Enclosed are first round questions on the Exxon plant transient code PTSPWR2 based on our review of the following Exxon reports:
1.
XN-74-5 (P)
Rev.
2 Supp.
1 draft, "PTSPWR2 Modifications for St.
Lucie Unit 1,"
W. T. Nutt, et al. (received September 1983).
2.
XN-NF-74-5 (P)
Rev. 2, "Description of the Exxon Plant Transient Simulation Model for Pressurized Water Reactors (PTS-PWR),"
D. M.
- Turner, et al. (received October 1983).
Exxon has informed us that document
( 1) describes the generic modifications to the code models necessary for the analysis of Combustion Engineering plants.
Document (2) was previously revi ewed in draft form and a
list of first round questions on that draft was sent to NRC on September 30, 1983.
The enclosed list of questions focus only on modifications to the draft contained in the final version of the report.
If further clarification is requi red please contact us.
Yours trul T. Y. Z.
Wei Light Water~actor Systems Analysis Reactor Analysis and Safety Division 8404040323 840316 PDR ADOCK 05000316 P
PDR P.
B.
- ramson, Manager Light Water Reactor Systems Analysis Reactor Analysis and Safety Division
V 1g
Mr. Jack Guttmann
&2&
November-22, 1983 PBA:TYCW:kr Enclosure Distribution:
R. Mattson, Director, Division of Sys ems integration, NRC/NRR B. Sheron, Chief, Reactor Systems Br anch, NRC/NRR S.
M. Boyd, NRC/NRR J. Carter, NRC/NRR B. L. Grenier, NRC/NRR W. Jensen, NRC/NRR N. Lauben, NRC/NRR L.
W. Deitrich, RAS R. Avery, RAS LWR Systems Analysis Sec.ion RAS Files:
- BM627, A15
PTSPWR2 XN-NF-74-5(P) Rev.
2:
First Round l}uestions on Modifications to the Draft 3e ort The applicant is requested to verify that the errors identified as typographical errors are indeed typographical errors and were not carried further into the program statements.
Section 2.3;4 1)
If the boron transport model uses the equations of the thermal
- model, eqs.
(2-31) - (2-37), (2-32) and (2-35),
what variable is used in place of temperature?
2)
.Since boron injection is assumed by the model to take place in the I
reactor. vessel lower plenum, what is done about injection in the legs?
Section 2.4 3)
Is wall heat not modelled in the pressurizer?
PTSPWR2 XN-74-5 (P)
Rev. 2, Sup l. 1:
Fi rst Round Questions on Code Modifications for CE Plants The applicant is requested to verify that the errors identified as
,ypographi cal errors are indeed typographical errors and were not carried further into the program statements.
Section 2.0 1)
How is the pump energy included in the hydraulic flow model?
2)
Provide details of the model for the (a) motor torque (b) friction torque (c) windage torque.
3)
(a)
List the parameters adjusted in the modelling of a pump coastdown.
(b)
List the data used to adjust the above parameters.
(c)
Justify the use of SEMISCALE pump data for CE pumps.
4)
(a)
What torque is adjusted to stop shaft rotation'?
(b)
Justify the above approach.
Section 3.0 5)
Present the derivation for eq.
(3.5) and show how it is consistent with eq.
(2-26e) in the main report.
6)
Oefine Ysg j.
7)
Justify the functional form used in eq. (3.8).
8)
Provide a figure showing the elevation differences used.
9)
Give a reference for the pump head curve shown in Fig. 3.2.
~
~
~
~
10)
Define 6> and X
used in eq. (3.14).
Section 4.0 11)
How is the hot leg to cold leg delta-T redefined?
Section 5.0 12)
Provide the modified MacBeth correlation used for pressures below 1'450 psia and the database for the modification.
Section 7.0 13)
Provide references for eq.
(7.2)
-. (7.4) and Fig. 7.3 which describe various trips.
Section 8.0 14)
Explain how eq.
(8.2) used in the initialization of the pressurizer is consistent with eqs.
(2-45) - (2-46) of the new pressurizer model described in the main report.
Section 9.0 15)
There is an implication that the original code model does not conserve energy in the steam dome during depressurization.
Clarify.
16)
(a)
Reconcile eq.
(5.2) of the main report with eq. (9.1) for the break flow.
(b)
What are the units used in eq.
(9.2) for the break flow?
(c)
Provide the value-of the quality used for the Hoody flow factor of Fi g. 9.1 and justi fy the choi ce.
(d)
Why is dome pressure and not steam line pressure used to calculate steam line break flow?
17)
(a)
(b)
(c)
(d)
~
~
Reconci 1 e eq.
(9.4) with eq.
(3.30) for the steam dome in the main report.
Provide a figure, which should correspond to Fig. 3.2 in the main report, to illustrate eq. (9.5).
Correct the typographical error for the left side of eq. (9.8) (last line of page).
Explain why the steam generator model of the main report requires the modifications of the supplement to calculate the mass in the dome.
18)
Provide equations for the boron transport model.