Information Notice No. 79-24, Overpressurization of Containment of a PWR Plant after a Main Steam Line Break
IN79024
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
September 23, 1979
MEMORANDUM FOR: B. H. Grier, Director, RI
J. P. O'Reilly, Director, RII
J. G. Keppler, Director, RIII
K. V. Seyfrit, Director, Region IV
R. H. Engelken, Director, RV
FROM: Norman C. Moseley, Director, Division of Reactor
Operations Inspection, IE
SUBJECT: Information Notice No. 79-24, OVERPRESSURIZATION OF
CONTAINMENT OF A PWR PLANT AFTER A MAIN STEAM LINE BREAK
The enclosed information notice should be dispatched October 1, 1979 to all
power reactor facilities holding operating licenses and to facilities with a
construction permit.
Norman C. Moseley, Director
Division of Reactor Operations
Inspection
Office of Inspection and Enforcement
Enclosures:
1. Information Notice No. 79-24
2. Draft Transmittal Letter
CONTACT: H. A. Wilber, TP
49-28180
.
(Draft letter to all power reactors facilities with operating licenses and
construction permits.)
Information Notice No. 79-24
Gentlemen:
The enclosed Information Notice provides information with regard to an
analysis that identifies an event that could result in overpressurization of
containment at a pressurized water reactor.
Sincerely,
Signature
(Regional Director)
Enclosures:
1. Information Notice 79-24
2. List of IE Information
Notices Issued in the
Last Six Months
.
SSINS: 6870
Accession No:
7908220123
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D. C. 20555
October 1, 1979
Information Notice No. 79-24
OVERPRESSURIZATION OF CONTAINMENT OF A PWR PLANT AFTER A MAIN STEAM LINE
BREAK
Virginia Electric and Power Co. submitted a report dated September 7, 1979
that identified a deficiency in the original analyses of containment
pressurization as a result of a steam line break for North Anna Power
Station, Units 3 and 4.
Stone and Webster Engineering Corporation performed a reanalyses 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 feedwater system had not been considered in the earlier analyses.
The corrective action is now under review by the owner, architect engineer,
and NSSS supplier.
This Information Notice is provided as an early notification of a possibly
significant matter that is still under review by the NRC staff. It is
expected that recipients will review the information for possible
applicability to their facilities. No specific action or response is
requested at this time. If NRC evaluations so indicate, further licensee
actions may be requested or required.
No written response to this Information Notice is required. If you have any
questions regarding this matter please contact the Director of the
appropriate NRC Regional Office.
Enclosure:
List of Information Notices
Issued in the Last Six Months
.
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