ML20217A675
| ML20217A675 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/18/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20217A673 | List: |
| References | |
| 50-263-98-02, 50-263-98-2, NUDOCS 9803250162 | |
| Download: ML20217A675 (3) | |
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' Northem States Power Company Docket No.: 50-263 Monticello Station License No.: DPR-22 During an NRC inspection conducted from January 13,1998, thro Jgh February 23,1998, 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.
Criterion V of 10 CFR Part 50, Appendix B " Instructions, Procedures, and Drawings," requires that activities affecting quality shall be prescribed by documented instructions, procedures, and drawings of a type appropriate to the circumstances and shall be accomplished in accordance with those instructions, procedures, and drawings. Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
1.
Contrary to the above, on January 21,1998, the equipment isolation sheet associated with Work Order (WO) 9800108, " Install surge suppression diode at MO-2080 trip coil,"
did not contain adequate instructions for the restoration of Valve MO-2078. Specifically, the instructions did not require the operators to manually open and reposition the manual declutch after the motor-operated valve had been manually closed. As a result, these actions were not completed and operators were unable to electrically stroke the valve following the restoration activity.
This is a Severity Level IV violation (Supplement 1).
2.
Step 4.4.2 of Administrative Work Instruction 4AWi-04,05.05, Revision 8, "WO Closeout and Disposition," states, in part, that the shift supervisor shall coordinate the permanent clearing of an isolation to facilitate required testing and the retum-to-service of components or systems.
i Contrary to the above, on January 29,1998, the inspectors identified that the shift j
supervisor failed to remove a hold-and-secure card attached to the control room hand-switch for the #13 residual heat removal service water pump prior to declaring the system operable. The hold-and secure tag instructed the operators not to operate the pump.
This is a Severity Level IV violation (Supplement 1).
3.
Step 4.1.1 of 4AWi-06.06.01, Revision 6, " Material Handling and Control of Heavy j
i Loads," defines a heavy load as any load weighing greater than 1500 pounds. Step 4.2.1 requires the licensee to determine if the use of the heavy load procedures is necessary using Figure 5.1, " Heavy Load Decision Flow Chart."
Procedure 8151, Revision 4, " Heavy Load Movement Procedure," provides instructions for the movement o. heavy loads.
Contrary to the above, WO 980042, " Move New Channels / Blades to RB1027 [ reactor building,1027-foot elevation) and Remove Empty Boxes," was not appropriate to the circumstances in that it did not specify the number of crates to be lifted simultaneously.
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As a result, on January 21,1998, maintenance personnel lifted two crates, weighing
- about 1400 pounds each, from the ground level to the refueling floor area using the l
reactor building crane. The inspectors identified that lifting the two crates simultaneously L
' constituted a heavy load and an evaluation should have been performed in accordance with 4AWi-06.06.01 and Procedure 8151; l
This is a Severity Level IV violation (Supplement 1).'
4.
Technical Specification (TS) 3.7.B.2.a(3) states that the laboratory carbon sample u
analysis for stanaby gas treatment charcoal absorber cartridges shall show :t94 percent b
methyl iodine (iodide) removal efficiency when tested at 30* Celsius and at 95 percent l~i humidity.
Surveillance Test 0149, Revision 5, " Standby Gas Treatment Charcoal Absorber l
Cartridge Test," was developed by the licensee to meet the requirements of.
TS 3.7.B.2.a(3).
Contrary to the above, Surveillance Test O149 was not appropriate to the circumstances in that it did not contain the appropriate acceptance criteria. Specifically, the inspectors -
L identified that since October 2,1995, the requirements of TS 3.7.B.2.a(3) were not contained in Surveillance Test 0149. The test acceptance criteria provided in the test l
was 290 percent methyl iodine (iodide) removal efficiency when tested at 130* Celsius and at 95 percent relative humidity.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Northem States Power Company is hereby required
~ to submit a written statement or explanaticn to the U.S. Nuclear Regulatory Commission, ATTN:
l Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, p
Region lil, and a copy to the NRC Resident inspector at the Monticello Nuclear Generating Plant,'
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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 or i
i severity level; (2) the corrective steps that havo been taken and the results achieved; (3) the i
corrective steps that will be taken to avoid fur'her violations; and (4) the date when full j
compliance will be achieved.. Your response may reference or include previous docketed l
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 as to 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.
If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United Stated Nuclear Regulatory Commission, Washington, DC 20555-0001.
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l l-Notice of Violation l Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, N should not include any personal privacy, proprietary, or safeguards information so that N can be placed in the PDR without redaction. If personal privacy or proprietary information is _
i necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you mW11 l
specifically identify the portions of your response that you seek to have withheld and provide in l
detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial i
information). If safeguards information is necessary to provide an acceptable response, please l
provide the level of protection described in 10 CFR 73.21.
Dated at Lisle, Illinois l
this 18th day of March 1998 l
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