ML20031A049
| ML20031A049 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Arkansas Nuclear, Waterford, 05000383  |
| Issue date: | 09/11/1981 |
| From: | Schnatz T MIDDLE SOUTH SERVICES, INC. |
| To: | Berggren J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8109180330 | |
| Download: ML20031A049 (5) | |
Text
W
-+ e MIDDLE SOUTH SERVICES,1NC/ BOX GIDOO/NEW ORLEANS.LA.70151/(504) 529-5252 TH O M AS W. S CH N ATZ. th D.,P. E.
ASSISTANT DIR ECTO R NUCLEAR ACTi%tTIES September 11, 1981 D
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.h e Mr. John S. Berggren, Project Manager j
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Standardization & Special Projects
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NY Di Division of Licensing Office of Nuclear Reactor Regulation Q #s8t.asmaamame U. S. Nuclear Regulatory Commission g
, s' j Washington, D. C.
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SUBJECT:
Intended Applicatione, for RETRAN by the Members of the Utility Group for Regulatory Action (UG?.A)
REFERENCES:
(1) Memo, John S. Berggren of NRC, " Review of EP'.I Licensing Topical Report CCM-5-RETRAN", Apr.1 9, 1981 (066-31).
(2) CCM-5 RETRAN Computer Code Manual, Volume 4:
Applications, EPRI, December, 197P.
(3) Conference Proceedings:
First International RETRAN Confer <.nce, September 22-24, 1980.
EPRI. April, 1981.
Dear Mr. Berggren:
As agreed to during the UGRA/NRC meeting of April 2, 1981 in Bethesda, I am forwarding to you the attached tables identifying the types of plants and transients to which the UGRA members intend to apply RETRAN. Table 1 presents a list of plant types as a function of NSSS vendor, nominal full power level and other dominant design character 1; tics. Table 2 provides a list of the types of transients intended to be analyzed with RETRAN.
The information presented in the two tables is intended to be of a repre-sentative naturr and should not be taken as definitive.
l As Table 1 indicates, RETRAN will be applied to a wide range of plant types from the early, one-of-a-hind plants, to the latest standardized design plants. The diversity in the p' ant designs is because of the wide-l spread interest among utilities in using RETRAN. The twenty UGRA members, for example, represent over 507 of the domestic units currently in operation
(
or under construction.
It should also be noted that not all RETRAN users are members of UCRA.
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Mr. John S. Btrggren September 11, 1981 Page 2 Several of the UGRA member utilities have begun to use RETRAN on a regular basis to support plant operations and/or training. At least one has prepared and submitted a user application report to the NRC to sup-port using RETRAN for licensint applications. While the members have their own individual schedules, a typical schedule is to have a working RETRAN model in 1982, submit a user application report to the NRC in 1982 or 1983, and begin using RETRAN for reload licensing applications by 1984.
However, as indicated above, some utilities are a year or two ahead of the typical schedule.
We, therefore, realistically expect that a number of utilities will submit RETRAN user application reports to the NRC for review during 1982 and more in 1983.
To efficiently process the review of these user application reports, we believe a generic review of the RETRAN code would be very beneficial to both the NRC and the individual utilities. We request that this review project be given a high priority within the NRC, commensurate with the expressed near-term, widespread usage of RETRAN.
There are two versions of RETRAN currently in use: RETRAN-01 and the recently released RETRaN-02. RETRAN-02 represents an expansion of the mod-el options available in the original version. The two versions however, are basically the same code. Appropriate selection of model options in RETRAN-02 will produce analysis results comparable to these obtained from RETRAN-01.
Therefore, it is appropriate to treat the review of RETRAN as one entity. Vc suggest that you initiate your review with the documentation that has been provided on RETRAN-01. As soon as the documentation on RETRAN-02 is complete, a submittal will be made to supplement (not replace) the RETRAN-01 material. Differences that exist between the two versions do not warrant separate review.
Special features that exist in RETRAN-02 should stand on their own merit. To aid in your reviev we would be happy to meet with you to explicitly identify the special features of RETRAN-02 and the differences between the two versions.
UGRA would look for in the end,' a Safety Evaluation Report that would be inclusive of both versions of the code. We are, therefore, requesting that you review the RETRAN methodology rather than any specific version of the code. The application of RETRAN, detailing modeling options selected, would be treated by each utility in their user application reports and licensing submittals.
Finally, as.ve agreed in Reference 1, please acknowledge your accep-tance of RETRAN for review and provide us a review schedule.
1 1
l
Mr. John S. Berggren September 11, 1981 Page 3 Should you have any questions please feel free to contact me at (504) 569 +503, n-Mr. Tom Temple at (504) 569-4568.
Sincerely, M
T. W. Schnatz Chairman Utility Group for Regulatory Action WS/TLT/tib Attachments cc:
Mr. John Long (NRC)
File:
041-01 066-31
l TABLE 1 REPRESENTATIVE REACTOR TYPES Pressurized Water Reactors Vendor Thermal Power Coolant Gteam Generator (Mwt)
Loops Typel B&W 2535 2/42 OTSG 2568 2/4 OTSG 3760 2/4 OTSG C-E 2530 ti UTSG 2630 3
UTSG 2560 2/4 UTSG 2700 2/4 UTSG-2815 2/4 UTSG 3411 2/4 UTSG 3835 2/4 UTSG W
600 4
UTSG 2200 3
UTSG 2441 3
UTSG 2652 3
UTSG 2758 4
UTSG 2775 3
UTSG 3250 4
UTSG 3411 4
UTSG Boiling Water Reactors Thermal Power BWR Jet Pump Containment (Mwt)
Type (Yes/No)
Type 240 BWR-1 No Dry 700 BWR-1 No Dry 1593 BWR-3 Yes Mark 1 1930 BWR-2 No Mark 1 2011 BWR-3 Yes Mark 1 2436 BWR-4 Yes Mark 1 2511 BWR-4 Yes Ibrk 1 2527 BWR-4 Yes Mark 1 3293 BWR-4 Yes Mark 1 3293 BWR-4 Yes Mark ?
3323 BWR-5 Yes Pfark 2 3835 BWR-6 Yes Mark 3 10TSG - Once through/superheating Steam Generator UTSG - U-Tube Steam Generator 2/4 - Two Hot Legs /Four Cold Legs
TABLE 2 REPRESENTATIVE TRANSIENTS 1.
Feedwater Line Breaks 2.
Feedwater Control System Miseparation/ Malfunction 3.
Steam Line Breaks 4.
Steam Flow Increase / Decrease 5.
Reactor Coolant Pump (s) Trip 6.
Reactor Coolc.nt Pump Shaft Seizure / Break 7.
Recirculation Loop Controller (BWR) Malfunction 8.
Control Rod Misoperation/ Malfunction 9.
Control Rod Ejection / Drop 10.
Inadvertent Start-up of Inactive Loop 11.
Chemical and Volume Contro! System Misoperation/ Malfunction 12.
Inadvertent ECCS Operation 13.
Anticipated Transients Without Scram (ATWS) 14.
Small Loss of Primary Coolant (a) Sample / Instrument Line Breaks (b) Letdown / Makeup Line P.reaks (c)
Inadverten Opening >f a Pressurizer Relief Valve NOTE:
It is not presently intended to employ RETRAN for analyzing Loss of Coolant Accidents (LOCAs) for compliance to 10CFR50.46 criteria nor qr slify RETRAN for 10CFR50, Appenddix K applications.
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