ML19326D513
| ML19326D513 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee, Midland File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/28/1973 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8006170923 | |
| Download: ML19326D513 (1) | |
Text
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g UNITED STATES p,
ATOMIC ENERGY COMMISSION e
y )g DIRECTOR ATE OF REGULATORY OPERATIONS
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REGION lli
%rts o' "y 799 ROOSEVELT ROAD TELEPHONE GLEN ELLYN, ILLINOIS 60137 (312) 858-2660 November 28, 1973 Consumers Power Company Docket No. 50-329 ATTN:
Mr. Stephen H. Howell Docket No. 50-330 Vice President 1945 Parnall Road Jackson, Michigan 49201 Gentlemen:
The enclosed Directorate of Regulatory Operations Bulletin No. 73-6,
" Inadvertent Criticality in a Boiling Water Reactor" has been sent for com-plation of the requested action to utilities that are presently licensed (or that will be licensed in the near future) to operate boiling water reactors. This bulletin is being sent to you to provide you with information that was reported
- to the AEC by the Vermont Yankee Nuclear Power Corporation, concerning an inadvertent criticality incident that was experienced at their Vermont Yankee facility. This bulletin is provided only for your general.
information.
Very truly yours, James G. Keppler Regional Director
Enclosure:
RO Bulletin No. 73-6 bec: RO Files DR Central Files THIS DOCUMENT CONTAINS
~PDR POOR QUALITY PAGES Local PDR OCC, Beth, P-506A
- Ltr dtd 11-8-73 to Directorate of Regulatory Operations, Region I, King of Prussia, Pa.
- Ltr dtd 11-14-73 to Directorate of Licensing, USAEC, Washington, D.C.
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November 27, 1973 Directorate of Regulatory 4
Operations Bulletin No. 73-6
'l INADVERTENT CRITICALITY IN A BOILING WATER REACTOR We recently received an abnormal occurrence report from the Vermont Yankee Nuclear Power Corporation relating to an inadvertent criticality incident that waa experienced at their Vermont Yankee facility. A copy of this report is being sent to you under separate cover to provide you with pertinent details of this event.
At the time of the inadvertent criticality incident, the reactor vessel and primary containment heads were removed, the refueling cavity above the reactor vessel was flooded, control rod friction tests were in progress, the rod worth minimizer was bypassed, and core verification had been in progress. As a result of the incident, no measurable radioactivity was released, no fuel damage resulted and no personnel exposures were experienced. The incident is currently under review -
and evaluation by the Regulatory Staff.
l Action requested by this bulletin is contained in Section A.
A.
Action Requested by Licensees s
In light of this occurrence you are requested to take the following actions. Upon completion of these actions you are requested to inform this office in writing, within 45 days of the date of this letter, of the status of each item identified in each paragraph and subparagraph listed below:
1.
Procedural Review a.
Control Rod Drive Operating and Testing Procedures (1) Conduct a review of your control rod drive operating and testing procedures to determine that approved proced6res exist for all operations and tests.
(2) Verify that appropriate prerequisites are included in the procedures to require testing of associated inter-locking and protection features before control rod testing is permitted.
(3) Assure that prerequisites and detailed instructions are l
provided that demonstrate compliance with technical i
specification requirements and design bases.
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b.
Bypass Installation Procedures (Jumpers or Lifting of Leads)
Assure that existing bypsss installation procedures have been conservatively reviewed for technical adequacy and for adminis-strative controls.
c.
Radiation Protection Procedures Assure that procedures for access control and personnel accountability in areas subject to accidents are current.
d.
Shift Transition Procedure (Turnover)
Assure that complete and detailed procedures are in effect that provide instructions for a proper and conservative turnover of shift responsibilities. Such procedures must include requirements for communicating the status of all safety related equipment and conditions.
l 2.
Management controls Assure that your management controls that are in effect provide for qualified technical and administrative reviews and approvals of temporary circuitry changes and temporary off-normal plant conditions.
This review should assure that the responsibilities and requirements I
associ~ated with the review and approval, installation, verification, removal, and subsequent testing of temporary circuitry changes and temporary off-normal plant conditions are clearly delineated in station procedures, are understood by the station staff, and are being properly implemented.
3.
Licensed Operator Performance Assure that management provides the necessary opportunities and time so that operators are adequately trained to carry out their assigned responsibilities.
In particular, confirm that shift crew members are provided srecial training for safety related activities that are infrequent, complex, or have unusual safety significance.
If you have any questions concerning this request, please contact this office.
Enclosure:
A0 No. 7331 - Ltr dtd 11/14/73 (separate cover) 9 y
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