ML17333A405
| ML17333A405 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/02/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17333A404 | List: |
| References | |
| 50-315-96-02, 50-315-96-2, 50-316-96-02, 50-316-96-2, NUDOCS 9604090046 | |
| Download: ML17333A405 (3) | |
Text
NOTICE OF VIOLATION Indiana Michigan Power Company Oonald C.
Cook Nuclear Power Plant Docket No. 50-315; 5-316 License No.
ORP-58; OPR-74 Ouring an NRC inspection conducted from January 16 through February 26,
- 1996, two violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
NUREG-1600, the violations are listed below:
A.
10 CFR Part 70.24, "Criticality Accident Requirements",
- requires, in part, that "Each licensee authorized to possess special nuclear material in a quantity exceeding 700 grams of contained uranium-235...shall maintain...a monitoring system....which will energize clearly audible alarm signals if accidental criticality occurs."
License number OPR-74 authorizes the licensee to posses special nuclear material (SNN) for Unit 2 in excess of 700 grams of contained uranium-235.
Contrary to the above, on February 16,
- 1996, the NRC determined that the licensee did not have a monitoring system that complied with the requirements of 70.24.
This is a Severity Level IV violation (Supplement I). (50-316/96002-01)
B.
10 CFR 50.59 requires, in part, that changes made to the facility as described in the safety analysis report be evaluated in accordance with 50.59 to determine, in part, if an unreviewed safety question exists.
Section 6.2 of the O.
C.
Cook Nu'clear Plant Updated Safety Analysis Report (USAR) states that the "spilled coolant and injection water which is collected in the containment recirculation sump following the
,injection phase is recirculated back to the reactor coolant system by the residual heat, removal pumps."
Contrary to the
- above, on February 26, 1996, the NRC identified a 8 ft by 8 ft tarp temporarily installed over the Unit 2 reactor cavity.
The unit was at full power and the tarp had the potential to prevent reactor coolant from reaching the containment recirculation sump during a Loss
'of Coolant Accident (LOCA).
The tarp was installed without the required evaluation to ensure it did not represent an unreviewed safety question.
This is a Severity Level IV violation (Supplement I). '(50-316/96002-02) 9604090046 960402 PDR ADQCK 05000315 8
Notice of Violation Pursuant to the provisions of 10 CFR 2.201, Indiana Nichigan Power Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region III, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, or
- revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (POR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the POR without reduction.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the
- PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at Lisle, Illinois, this 2nd day of April 1996