ML20215E057
| ML20215E057 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe, Maine Yankee, 05000000 |
| Issue date: | 10/03/1986 |
| From: | Mckenna E Office of Nuclear Reactor Regulation |
| To: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-2.K.3.30, TASK-TM NUDOCS 8610150011 | |
| Download: ML20215E057 (5) | |
Text
,
OCT 0 31986 Docket No.50-029 and 50-309 Mr. George Papanic, Jr.
Senior Project Engineer-Licensing Yankee Atomic Electric Company 1671 Worcester Road I
Framingham, Massachusetts 01701
Dear Mr. Papanic:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - TMI ACTION PLAN ITEM II.K.3.30 SMALL BREAK LOCA OUTLINE Re: Yankee Nuclear Power Station Maine Yankee Atomic Power Plant i
As part of our review of responses to TMI Item II.K.3.30 for the Yankee and Maine Yankee plants, the staff has reviewed Topical Report YAEC-1300P on the RELAP5YA code, and the additional information provided by your letters dated March 1 April 30, July 1, August 15, November 1 and 5,1985.
In order to complete our review, responses are needed to the questions in the enclosure to this letter, your response is requested within 90 days of receipt of this letter.
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.
r Sincerely, Eileen M.
cKenna, Project Manager Project Directorate #1 Division of PWR Licensing-A
Enclosures:
As Stated cc's:
See Next Page Q
[
Office:
P P #
P #
PM/ PAD #8 PM/ PAD #8 Surname:
E c enna/tg ea PSears AThadani Date:
09Mf/86 09/gf86 M/g//86 f/J/86 to 8610150011 861003 PDR ADOCK 00000029 P
1 v.
Mr. George Papanic, Jr.
Yankee Atomic Electric Company Yankee Nuclear Power Station CC:
Mr. James E. Tribble, President Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 Thomas Dignan, Esquire Ropes and Gray 225 Franklin Street Boston, Massachusetts 02110 Mr. N. N. St. Laurent Plant Superintendent Yankee Atomic Electric Company Star Route Rowe, Massachusetts 01367 Chairman Board of Selectmen Town of Rowe l
Rowe, Massachusetts 01367 Resident Inspector Yankee Nuclear Power Station c/o U.S. NRC l
Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 1
150 Tremont Street, 7th Floor Boston, Massachusetts 02111
Mr. J. B. Randazza Maine Yankee Atomic Power Company Maine Yankee Atomic Power Station cc:
Charles E. Monty, President Mr. P. L. Anderson, Project Manager Maine Yankee Atomic Power Company Yankee Atomic Electric Company 83 Edison Drive 1671 Worchester Road
- Augusta, Maine 04336 Framingham, Massachusetts 07101 Mr. Charles B. Brinkman Mr. G. D. Whittier Manager - Washington Nuclear Licensing Section Head Operations Maine Yankee Atomic Power Campany Combustion Engineering, Inc.
83 Edison Drive 7910 Woodmont Avenue Augusta, Maine 04336 Bethesda, Maryland 20814 John A. Ritsher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Mr. John H. Garrity, Plant Manager Maine Yankee Atomic Power Company P. O. Box 408 Wiscasset, Maine 04578 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset Municipal Building U.S. Route 1 Wiscasset, Maine 04578 Mr. Cornelius F. Holden Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578
n s,..
ENCLOSURE 1 REQUEST FCR ADDITIONAL INFORMATION In response to Q.II.12 YAEC stated that the PWR SBLOCA calculat' ions 1.
Because all the will be. completed with a two node pressurizer model.
assessment calculations were completed with more than two nodes, explain how this nodalization has been assessed. Clarify why YAEC believes a two node pressurizer model is adequate.
J 2.
In response to Q.IX.2 to 4, YAEC stated that the PORY passes steam because the pressurizer spray is terminated by decreasing system pressure.
During PORY break calculations, does the pressurizer level ever increase so that the PORV would pass a two-phase mixture? If so, what pressurizer nodalization is needed to accurately track the pressurizer level? Would more than two pressurizer nodes as discussed in Q/A.II.12, be used in this type of calculation? Has'YAEC reviewed the PORY flow data generated by the EPRI Safety and Relief Valve Test Program to assess the PORV flow calculated with RELAP5YA and the modeling techniques discussed in the answer to Q.IX.2 to 47 Discuss what impact the difference between the i
calculated and actual PORY flow would have on licensing calculations.
Will a break area spectrum study be perfonned for pressurizer breaks?
If not, will YAEC complete a discharge coefficient sensitivity study to 1
assess the effect of uncertainties in the break flow on the calculated l
system response?
3.
YAEC provided infonnation on the steam generator (SG) nodalizations for Maine Yankee (MY) and Yankee Rowe(YR) in the response to Q.II.2. Based on this information the two plant models will use a different number of nodes to represent the primary side of tl.e U-tubes. Clarify' why different nodalizations are used in the two plants. Also, the peak clad temperature (FCT) in RELAPS/ MOD 2 SBLOCA calculations has shown some sensitivity to SG nodalization and initial conditions (see NUREG/CR-4384, March 1986).
Justify convergence of the PCT with the proposed SG noda11 ration and initial conditions.
F i
Distribution Copies:
'Geeket-Iles:150-029 & 50-309 NRC PDR Local PDR PAD #1 r/f PAD #1 p/f TNovak, Actg. DD NThompson, DHFT OGC-Bethesda EJordan BGrimes JPartlow GLear PShuttleworth EMcKenna PSears AThadani DCrutchfield SSun ACRS(10)
LFMB