ML20039D989
| ML20039D989 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 12/30/1981 |
| From: | Sherwood G GENERAL ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20039D990 | List: |
| References | |
| DKD-81, MFN-216-81, NUDOCS 8201060408 | |
| Download: ML20039D989 (2) | |
Text
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e GENER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFN-216 MC 682, (408) 925-5040 DKD-81 to December 30, 1981 4
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U.S. Nuclear Regulatory Commission C
4 Office of Nuclear Reactor Regulation 2-8 J
Washington, DC 20555 Attention:
H. R. Denton, Director Office of Nuclear Reactor Regulation g
b Gentlemen:
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISLAND, GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II):
DOCKET N0. STN 50-447
References:
1)
Letter from G. G. Sherwood (GE) to H. R. Denton and R. B. Minogue (NRC), " Boiling Water Reactor Loss-of-Coolant Accident Proposal," dated September 4, 1981 2)
Letter from G. G. Sherwood (GE) to Dr. M. Plessett (ACRS), " General Electric Proposal on ECCS Decay Heat," dated October 6, 1981 Enclosed please find three original copies (15 conformed copies are beine transmitted under separate cover) of Amendment No. 3 to the 238 General Electric Standard Safety Analysis Report (GESSAR II) for the above numbered applications.
In the referenced letters, General Electric outlined a proposal for using the ANSI /ANS 5.1-1979 revised decay heat standard for BWR loss-of-coolant accident (LOCA) analyses.
In the letters, GE committed to provide a detailed technical basis describing an improved correlation based on the 1979 standard for determining BWR LOCA decay heat genera-tion. This technical basis was to be submitted as an amendment to GESSAR II. Accordingly, Appendix 6A has been added to GESSAR II and po3 fully responds to the committed requirements, j
The details of this submittal were discussed with the ACRS Subcommittee j
on Emergency Core Cooling Systems (ECCS) on August 28, 1981, in Mont-erey, California. At that time, GE committed to not use any increased peak clad temperature (PCT) margin obtained with this improved analysis to extend current BWR operating limits beyond 14.4 kW/ft, 54 kW/1, crd 28 kW/kgU.
However,.in order to be able to include the BWR/6 reactor design and allow application of this correlation to several operating foreign plants, this submittal commits to a core average power density 8201060408 8112304 DR ADOCK 05000447?
PDR9
G EN ER AL hELECTRIC U.S.. Nuclear Regulatory Comission LPage 2 of 57 kW/l rather than' the. 54. kW/l stated previously. This value is well beiow the values tested-in full scale fuel bundle tests for General Electric supplied fuel. The other two operating limits discussed et the-Monterey meeting remain unchanged.
1 Amendment No. 3 consists of two parts :- a nonproprietary portion and a portion considered by the, General Electric Company to be proprietary.
The pages considered to be proprietary are so marked and are transmitted underJseparate cover.
We request that this proprietary information be withheld from public disclosure and be considered proprietary pursuant to Section 2.790 of -
10 CFR Part 2 for the reasons presented in the separate cover.
Very truly -yours, G nn.
he o n
r Nuclear Safety and Licensing Operation GGS:sem/6E 1221 Attachments cc:
L. S. Rubenstein (w/o att)
R. L. Tedesco (w/o att)
J. R. Miller (w/o att)
H. J. Faulkner
'R.--B. Minogue (w/o att)
R. J. Mattson (w/o att)
B. Sheron L. S. Gifford (GE, Bethesda).
l M. S. Plesset (ACRS) l l_
i f'
.