ML20137N009
| ML20137N009 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/19/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8512040050 | |
| Download: ML20137N009 (3) | |
Text
IkkJ
/;ke November 19, 1985
-Docket Nos. 50-413 and 50-414 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
Subject:
Request for Additional Information Regarding Main Steam Line Break in the Doghouse, Catawba Nuclear Station, Unit 1 & 2 The NRC staff has reviewed your evaluation of a main steam line break (MSLB) in the Catawba Doghouse forwarded by your coverletter dated March 15, 1985.
We find that additional information, identified in the enclosure, is needed for completion of our review.
Your response to the enclosure is requested within 30 days of this letter.
Contact the Project Manager, Kahtan Jabbour, at (301) 492-9789 if you have questions regarding the enclosure or are unable to meet the requested response date.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original Signed by Carl R. Stable for Elin'or G. Adensam, Chief 4
Licensing Branch #4 Division of Licensing
Enclosure:
As stated cc w/ enc 1:
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Mr. H. B. Tucker Duke Power Company Catawba Nuclear Station cc:
William L. Porter, Esq.
North Carolina Electric Membership Duke Power Company Corp.
P.O. Box 33189 3333 North Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.
Bishop Liberman, Cook, Purcell Saluda Riter Electric Cooperative, and Reynolds Inc.
1200 Seventeenth Street, N.W.
P.O. Box 929 Washington, D. C.
20036 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N 3100 Smoketree Ct.
York, South Carolina 29745 P.O. Box 29513 Raleigh, North-Carolina 27626-0513 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, Mr. C. D. Markham 101 Marietta Street, NW, Suite 2900 Power Systems Division Atlanta, Georgia 30323 Westinghouse Electric Corp.
P.O. Box 355 Pittsburgh, Pennsylvania 15230 Robert Guild, Esq.
P.O. Box 12097 NUS Corporation Charleston, South Carolina 29412 2536 Countryside Boulevard Clearwater, Florida 33515 Palmetto Alliance 2135 i Devine Street Mr. Jesse L. Riley, President Columbia, South Carolina 29205 Carolina Environmental Study Group 854 Henley Placc Karen E. Long Charlotte, North Carolina 28208 Assistant Attorney General N.C. Department of Justice Richard P. Wilson, Esq.
P.O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 S.C. Attorney General's Office P.O. Box 11549 Spence Perry, Esquire Columbia, South Carolina 29211 Associate General Counsel Federal Emergency Management Agency Piedmont Municipal Power Agency Room 840 100 Memorial Drive 500 C Street Greer, South Carolina 29651 Washington, D. C.
20472 Mark S. Calvert, Esq.
Mr. Michael Hirsch Bishop, Liberman, Cook, Federal Emergency Management Agency Purcell & Reynolds Office of the General Counsel 1200 17th Street, N.W.
Room 840 Washington, D. C.
20036 500 C Street, S.W.
Washington, D. C.
20472 Brian P. Cauidy, Regional Counsel Federal Emergency Management Agency, Region I J. W. McCormach POCH l
Boston, Massachusetts 02109 U
,.,i Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA UNITS 1 & 2 STEAM LINE BREAK Provide the following additional infomation in regard to your analyses of a main steam line break (MSLB) in the Catawba Doghouse as forwarded by cover-letter dated March 15, 1985.
1.
The steam line break analyses in support of Doghouse equipment qualification were perfonned with an updated but unapproved version of LOFTRAN. Provide a detailed description of the modifications made to LOFTRAN and its validation. Also, confinn the appropriateness of the break flow model for superheated conditions.
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2.
Superheated break flow conditions could lead to higher heat loss rates from the reactor coolant system when compared to saturated break flow conditions. This could imply that previous versions of the LOFTRAN computer program are non-conservative and that the results submitted in WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases," (as referenced in the FSAR) may not be valid for all conditions. Address, in detail, the consequences of modeling superheat and its effect on core response. Provide detailed comparative analyses of the results calculated with the two models (saturated versus superheated steam models).
3.
As a consequence of equipment failures from adverse environmental conditions, the main steam isolation valves in the affected Doghouse were assumed to reopen. This led to blowdown of the two steam generators:
(a) Provide details and justification of the reactivity methodology used in the analyses as well as the nodalization and the primary coolant mixing coefficients applied in the reactor vessel.
(b) Provide the data and justification to support the mixing coefficients applied to the reactor coolant as well as the reactivity feedback models.
(This information was requested by the NRC in 1983 on the WCAP-9226 submittal but Westinghouse has not responded to the request.)
(c) Describe how the analyses were performed when assuming the stuck rod cluster control assembly to be positioned in loop 1 core sector versus loop 2 core sector.
4.
Provide your evaluation of offsite dose, including in particular the case with two steam generator blowdown.
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