ML17333A575
| ML17333A575 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/19/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17333A574 | List: |
| References | |
| 50-315-96-06, 50-315-96-6, 50-316-96-06, 50-316-96-6, NUDOCS 9609270033 | |
| Download: ML17333A575 (4) | |
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Indiana Hichigan Power Company Donald C. Cook Nuclear Power Plant Docket No. 50-315; 5-316 License No. DPR-58; DPR-74 During an NRC inspection conducted from Hay 26 through July 13,
- 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:
D. C. Cook Plant Technical Specification 6.8. 1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
The following were examples of failure to follow procedures:
Regulatory Guide 1.33, Appendix A, paragraph 1.b requires that a
procedure be written delineating the authorities and responsibilities for safe operation and shutdown.
Plant Hanagers Instruction (PHI) 7030, "Corrective Action", was written in accordance with RG 1.33.
Step 5.31 requires in part, that a prompt operability determination "...must be made expeditiously following identification of a potentially degraded condition that has the potential to impact SSC operability."
Step 6.9.a, requires an originator to initiate a condition report for known or suspected adverse conditions/events.
Contrary to the above:
a ~
On April 13, 1996, the licensee failed to properly perform and document a prompt operability determination for both of the Unit 1
emergency diesel generators (D/G) and the other Unit 2 D/G (2 AB) following the identification of a potentially generic condition of failed Cam follower springs on the 2
CD D/G.
b.
On Hay 3, 1996, the Unit 2 West Essential Service Water (ESW) strainer discharge check valve leaked-by sufficient to cause the pump to rotate backwards, however a prompt operability evaluation was not petformed until prompted by the inspectors on July 9, 1996.
C.
On December 27, 1995, the Unit 1
CD emergency-diesel generator (D/G) neutral grounding resistor was identified by licensee personnel to be incorrectly configured (nominally 6 ohms but it was wired such that it was actually 2.3 ohms).
The prompt operability evaluation was not performed until January 5,
1996.
This is a severity level IV violation (Supplement I). (50-315/316-96006-01).
9609270033 960919 PDR ADQCK 050003l5 8
Notice of Violati on 2
2.
10 CFR 50, Appendix B, Criterion XVI, "Corrective Action" required, in part, that conditions adverse to quality be promptly identified and corrected.
Contrary to the above:
On February 5, 1996 NRC inspectors identified to licensee management that instruments used to verify Technical Specifications required temperatures were not in a calibration program.
This deficiency had been communicated from the operations staff to engineering prior to January
- 1996, but no action via the corrective action process had been initiated.
- Further, a condition report (CR) was not issued for 2 days after the identification by the NRC.
b.
On February 7, 1996 the inspectors identified possible auxiliary feedwater system piping support deficiencies and a
CR was not initiated until four days later.
C.
On February 6,
- 1996, a
CR for the boric acid system heat trace high temperature conditions had not been written until two days after NRC inspectors questioned the system status.
Previously, local high temperature indications had been illuminated and known to equipment operators and engineering, but corrective action was not initiated.
d.
In February 1996, following installation, but prior to placing a
temporary modification which installed a
"COSMOS" analytic panel on the component cooling water system in operation, the completed package was required by temporary modification procedure PMP 5040 MOD.001 to be returned to the control room and placed in the TM log.
The unit had been in service for about 30 days, how'ever, the package had not been returned to the control
- room, and operators were not aware that the unit was in service.
This did not meet the requirements of the procedure and a condition report was not written to address this issue.
This is a Severity Level IV violation (Supplement I). (50-315/316-96006-02)
Pursuant to the provisions of 10 CFR 2.201, Indiana Michigan 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
Notice of Violation 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 (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR 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 19th day of September 1996