Bulletin 84-01: Cracks in Boiling Water Reactor Mark I Containment Vent Headers
SSINS No.: 5820
OMB No.: 3150-00011
Expiration Date: 4/30/85
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
February 3, 1984
IE BULLETIN NO. 84-01: CRACKS IN BOILING WATER REACTOR MARK I CONTAINMENT
For Action - All Boiling Water Reactor nuclear power reactor facilities
having a Mark I containment and currently in cold shutdown and holding an
For Information - All other Boiling Water Reactor nuclear power reactors
having an operating license or construction permit.
The purpose of this bulletin is to determine whether cracks exist in the
Mark I containment vent header (located inside the torus) in any boiling
water reactor currently in cold shutdown.
Description of Circumstances:
On February 3, 1984, the Hatch Unit 2 licensee reported a through wall crack
which appears to be 3600 around the vent header within the containment
Actions to be taken by all BWRs having Mark I Containments and Currently
1. Plants that are currently in cold shutdown should visually inspect for
cracks in the entire vent header and in the main vents in the region
near the intersection with the vent header. To the extent practicable,
the inspection should include the entire surfaces of the
aforementioned components. The inspection should be completed within
36 hours of receipt of this bulletin.
2. If cracks are found, the containment should be declared inoperable.
3. The results of the inspection are to be reported by telephone to the
NRC Operations Center within 8 hours after the inspection has been
completed. A written report describing the areas inspected and the
results should be submitted within seven days of receipt of this
February 3, 1984
Page 2 of 2
The written report required shall be submitted to the appropriate Regional
Administrator under oath or affirmation under provisions of Section 182a,
Atomic Energy Act of 1954, as amended. Also, the original copy of the cover
letter and a copy of the report shall be transmitted to the U.S. Nuclear
Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for
reproduction and distribution.
Although not a requirement of this bulletin, Boiling Water Reactor plants
that are currently operating which have Mark I type containments should
review their plant data on differential pressure between the wetwell and
drywell for anomalies that could be indicative of cracks. Any such anomalies
should be reported to the NRC in accordance with 10 CFR 50.72 and 10 CFR
50.73. This request for information was approved by the Office of Management
and Budget under a blanket clearance number 3150-00011 which expires April
30, 1985. Comments on burden and duplication may be directed to the Office
of Management and Budget, Reports Management, Room 3208, New Executive
Office Building, Washington, D.C. 20503.
If you have any questions regarding this matter, please contact the Regional
Administrator of the appropriate NRC Regional Office or the technical
contacts listed below.
Richard C. DeYoung, Director
Office of Inspection and Enforcement
Technical Contact: R. Baer, IE
C. E. Rossi, IE
Attachment: List of Recently Issued IE Bulletins
Page Last Reviewed/Updated Friday, May 22, 2015