ML17138B561
| ML17138B561 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/23/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8011100408 | |
| Download: ML17138B561 (5) | |
Text
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TRIBUTIDN:-q PkiOIILIA Docket Files iRHartfield,"MFA LBk'1 Rdg OELD OCT 2 3 1980 NRR Rdg OIF (3)
Docket Nos.:
', 50=387-'~
and 50-388 Mr. Norman M. Curtis Vice President. - Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsyl vania 13101
Dear Mr. Curtis:
DEisenhut RPurple JYoungblood RStark MRushbrook PCheck LRubenstein ASchwencer JMiller FMiraglia
- RVol'lmer DRoss
'- FSchroeder JKnight RTedesco VNoonan MTokap
'cc:
TERA NRC/PDR L/PDR NSIC TIC ACRS (16)
Subject:
Susquehanna Steam Electric Station, Units Nos, 1 and 2 - Request for Additfonal Information As a result of our review of your application.for operating licenses, for the Susquehanna Steam Electric Plant, we find that we need additional information fn the area of Core Performance.
The specfffc,information required fs listed fn the Enclosure.
If you desire any discussion or clarification of the information requested, please contact R. tl. Stark, Licensing Project Manager, (301-492-7238).
Sincerely, ODglIl21 slgII cg by Robert L. Tcdesco Robert L. Tedesco, Assistant Director for Licensing Division of Licensing Enclosure'.
As stated cc:
See next page got/foe pg 5'FFICE
-SURNAME DATE$
DL:LBg RMStark/ls i0/20/80 DL BJ lood 10/
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/80 NRC FORM 318 {9.76) NRCM 0240 4U.S. GOVERNMENT PRINTING OFFICE: 1979 289 369
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Mr. Norman W. Curtis Vice President - Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown,, Pennsyl vani a 18101 CC:
Mr. Earl.e M.'Mead Project Engineering Manager Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Jay Silberg, Esq.
Shaw, Pittman, Potts 5
Trowbridge-1800 M Street, N.
W.
Washington, D.
C.
20036 Mr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsyl vania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Bryan Snapp, Esq.
Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsyl vani a 18101 Robert M. Gallo Resident Inspector P. 0.
Box 52 Shickshinny, Pennsylvania 18655 John L.; Anderson Oak Ridge National Laboratory Union Carbide Corporation Bldg. 3500, P. 0.
Box X
Oak Ridge, Tennessee 37830 Mr. E.B. Poser Project Engineer Bechtel Power Corporation P.
0.
Box 3965 San Francisco, California 94119 Matias F. Travieso-Diaz, Esq.
Shaw, Pittman, Potts 5
Trowbridge 1800 M Street, N.
W, Washington, D. C.'0036 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pa 16801 Mr. Thomas M. Gerusky, Director
'ureau of Radiation Protection Department of Environmental Resources Cormonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pa 17120 Ms. Colleen Marsh Box 538A, RD//4 Mountain Top, PA 18707 Mrs. Irene Lemanowicz, Chairperson The Citizens Agains t Nucl ear Danagers P. 0.
Box 377 RD371 Berwi ck, PA 18503 Mr. J.W. Millard Project MAnager Mail Code 394 General Electric Company 175 Curtner Avenue San Jose, California 95125
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J C
ENCLOSURE 231.5 The NRC staff has been generically evaluating three materials models that are used in ECCS evaluations.
Those models predict cladding rupture temperature, cladding burst strain, and fuel assembly flow blockage.
We have (a) discussed our evaluation with vendors and other industry repre-sentatives (Reference 1), (b) published NUREG-0630, "Cladding Swelling and Rupture Models for LOCA Analysis" (Reference 2), and (c) required licensees to confirm that their operating reactors would continue to be in conformance with 10 CFR 50.46 if the NUREG-0630 models were substituted for the present materials models in their ECCS evaluations and certain other compensatory model changes weve allowed (References 3 and 4).
j Until we have completed our generic review and implemented new acceptance criteria for cladding models, we will require that the ECCS analyses in your FSAR be accompanied by supplemental calculations to be oerformed with the materials models of NUREG-0630, For these supplemental calculations only, we will accept other compensatory model changes that may not yet be approved by the NRC, but are consistent with the changes allowed for the confirmatory operating reactor calculations mentioned above.
REFERENCES 1,
Memorandum from R, P, Denise, NRC, to R. J, Mattson, "Summary Minutes of Meeting on Cladding Rupture Temperature, Cladding Strain, and Assembly Flow Blockage,"
November 20, 1979.
2.
D. A. Powers and R. 0. Meyer, "Cladding Swelling and Rupture Models for LOCA Analysis,"
NRC Report NUREG0630, April 1980.
3.
Letter from D.
G. Eisenhut, NRC, to all Operating Light Water Reactors, dated November 9, 1979.
4.
Memorandum from H.
R. Denton, NRC, to Commissioners, "Potential Deficiencies in ECCS Evaluation Models," November 26, 1979.