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 IEB 84-01 UNITED STATES 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 VENT HEADERS Addressees: For Action - All Boiling Water Reactor nuclear power reactor facilities having a Mark I containment and currently in cold shutdown and holding an operating license. For Information - All other Boiling Water Reactor nuclear power reactors having an operating license or construction permit. Purpose: 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 torus. Actions to be taken by all BWRs having Mark I Containments and Currently Shutdown: 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 bulletin. 8401190017 . IEB 84-01 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 301-492-4780 C. E. Rossi, IE 301-492-4944 Attachment: List of Recently Issued IE Bulletins
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Page Last Reviewed/Updated Tuesday, March 09, 2021