ML20127H398
| ML20127H398 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Vermont Yankee  |
| Issue date: | 11/27/1973 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wachter L NORTHERN STATES POWER CO. |
| References | |
| IEB-73-06, IEB-73-6, NUDOCS 9211180504 | |
| Download: ML20127H398 (3) | |
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p6,07 e UNITED OTATES h.
ATOMIC ENERGY COMMICOlON O
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\\ 'T DIRECTOR ATE OF REGULATORY OPER ATIONS Mo REGION lli D4rts o' 799 ROOSEVELT ROAD 3mg GLEN ELLYN, ILLINOIS 60137 (3123854-2860 November 27, 1973 Northern Statee Power company Docket No. 50-263 ATTN Mr. Leo Wachter, Vice President Power Production and System Oparation 414 Ricollet Hall Minneapolis, Minnesota 55401 Gentleman:
The enclosed Directorate of Regulatory Operations Bulletin No. 73-6,
" inadvertent Criticality in a Boiling Water Reactor," is sent to you to provida you with information that was reported
- to the AEC by the Vermont Yankee Nuclear Power Corporation concerning an inadvertent criticality incident that was experienced in the Vermont Yankee facility. This information may have direct applicability to your facility. Action requested on your part is identified in Section A of the enclosed bulletin.
Very truly yours, James G. Kappler Regional Director Enclosure to Bulletin No. 73-6 bect RO Files DR Central Files PDR Local PDR OGC, 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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L 9211180504 731127 PDR ADOCK 05000263 G
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i November 27, 1973 Directorate of Regulatory Operations Bulletin No. 73-6 INADVERTENT CRITICALITY IN A BOILING WATER REACTOR i
We recently received an abnormal occurrence report from the Vermont Yankee Nuclear Power Corporation relating to an inadvertent criticality incident that was experienced at their Vermont Yankee facility.- A copy of this report is being sent to you under separate cover to provide you l
with pertinent details of this event.
At the time of the inadvertent criticality incident, the reactor vessel l
and primary containment heads were removed, the refueling cavity above the reactor vessel was flooded, control rod friction tests were in-j progress, the rod worth minimizer was bypasced, 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 l
and evaluation by the Regulatory Staff, t
l Action requested by this bulletin is' contained in Section A.
t A.
Action Requested by Licensees j
i In light of this occurrence you are requested to take the following I
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 i
a.
Control Rod Drive Operating and Testing Procedures (1) Conduct a review of your control rod drive operating l
'and testing procedures to determine that approved
. procedures exist for all_ operations and tests.
i (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.
i (3) Assure that prerequisites and detailed instructions are provided that demonstrate compliance with technical specification requirements and design bases.
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2-b.
Bypass Installation Procedures (Jumpers or Lifting of Leads)
Assure that existing bypass installation procedures have been conservatively reviewed for technical adequacy and for adminis-strative controls.
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c.
Radiation Protection Procedures Assure that procedures for access control and personnel accountability in areas subject to accidents are current.
d.
Shif t Transition Procedure (Turnover)
Assure that complete and detailed procedures are in effect 3
that provide instructions for a proper and conservative j
turnover of shif t responsibilities.
Such procedures must i
include requirements for communicating the status of all 1
i safety related equipment and conditions.
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2.
Management Controls 1
i Assure that your management contr'ols that are in effect provide for qualified technical and administrative reviews and approvals of i
temporary circuitry changes and temporary off-normal plant conditions.
I This review should assure that the responsibilities and requirements i
i associated 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 special 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)-
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