ML19296C325
| ML19296C325 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/08/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 8002250582 | |
| Download: ML19296C325 (1) | |
Text
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%, * *%#* * *,o KING oF PRUSSIA, PENNSYLVANIA 19406 February 8,1980 Docket No. 50-333 Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr. J. D. Leonard, Jr.
Resident Manager P. O. Box 41 Lycoming, New York 13093 Gentlemen:
The enclosed IE Bulletin No. 80-04 is forwarded to you for information. No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, a
n Boyce H. Grier Director
Enclosures:
1.
List of Recently Issued IE Bulletins CONTACT:
D. L. Caphton (215-337-5253) cc w/encls:
George T. Berry, Executive Director P. W. Lyon, Manager - Nuclear Operations A. Klausmann, Director, Quality Assurance M. C. Cosgrove, Quality Assurance Supervisor J. F. Davis, Chairman, Safety Review Committee C. M. Pratt, Assistant General Counsel G. M. Wilverding, Licensing Supervi..or 8002250 F#L
ENCLOSURE 1 UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSPECTION AND ENFORCEMENT 7910250504 WASHINGTON, D.C.
20555 IE Bulletin No. 80-04 Date: February 8, 1980 Page 1 of 3 ANALYSIS OF A PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION Description of Circumstances:
Virginia Electric and Power Co. submitted a report to the Nuclear Regulatory Commission dated September 7, 1979 that identified a deficiency in the original analysis of containment pressurization as a result of reanalysis of steam line break for North Anna Power Station, Units 3 and 4.
Stone and Webster Engineering Corporation performed a reanalysis of containment pressure following a main steam line break and determined that, if the auxiliary feedwater system continued to supply feedwater at runout conditions to the steam generator that had experienced the steam line break, containment design pressure would be exceeded in approximately 10 minutes.
The long term blowdown of the water supplied under runout conditions by the auxiliary feedwas.er system had not been considered in the earlier analysis.
On October 1, 1979, the foregoing information was provided to all holders of operating licenses and construct Qn mits in IE Information Notice No.
r 79-24. The Palisades facility did an accia at analysis review pursuant to the information in the notice and (iscovered that with offsite power available, the condensate pumps would feet the affected generator at an excessive rate.
This excessfue feed was not considered in the analysis for the steam line break acciot.at.
On January 30, 1980, Maine Yankee Atomic Power Company informed the NRC of an error is the main steam line treak analysis for the Maine Yankee plant.
During a review of the main steam line break analysis, for zero or low power at the end of core life, the Ticensee identified an incorrect postulation that the startup feedwater control valves would remain positioned "as is" during the transient.
In reality, the startup f?cdwater control valves will ramp to 80% full open due to an overr'de signal resulting from the low steam generator pressure reactor trip signal.
Reanalysis of the event shows the opening of the startup valve and associa;ed high feedwater addition to the affected steam generator would cause a rapio reactor cooldown and resultant return-to power, a condition outside the plan + design basis.
Actions to be Taken by the L'censee:
For all pressurized water power rea DUPLICATE DOCUMENT reactors listed in Attachment 1:
Entire document previ ausly entered into system under.
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