ML17059B566
| ML17059B566 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/16/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17059B565 | List: |
| References | |
| 50-410-97-02, 50-410-97-2, NUDOCS 9705280154 | |
| Download: ML17059B566 (4) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Niagara Mohawk Power Corporation (NMPC)
Nine Mile Point Unit 2 Docket No. 50-410 License No. NPF-69 During an NRC inspection conducted from February 23 through April 5, 1997, violations of NRC requirements were identified.
In accordance with the NRC "General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG 1600, the violations are listed below:
A.
Unit 2 Technical Specifications, Section 4.3.3.3, requires the response-time of each emergency core cooling system (ECCS) to be demonstrated at least once per 18 months.
Each test is to include at least one channel per trip system, so that all channels are tested at least once per "N times 18 Inonths," where "N" is the total number of redundant channels in a specific ECCS trip system, Unit 2 Technical Specifications, Section 1.12, defines ECCS response time as that time interval from when the monitored parameter exceeds its actuation setpoint at the sensor, until the ECCS equipment is capable of performing its safety function (i.e., the valve achieves the required position, pump discharge pressure reaches the required value, etc.).
Where applicable, times are to include delays associated with the diesel generator starting and sequence loading.
The response time may be measured by a series of sequential, overlapping, or total steps, such that the entire response time is measured.
Contrary to the above, on or before March 26, 1997, the response time of the high pressure core spray (HPCS) system (a required ECCS system), was not demonstrated at least once per 18,months.
Specifically, response-time-testing for HPCS actuation instrumentation was last performed:
e Channel 1 drywell pressure
- high Channel 1 reactor water level - low/low Channel 2 drywell pressure
- high Channel 2 reactor water level - low/low November 16, 1990 September 28, 1990 April 19, 1992 April 17, 1992 Additionally, one relay (E22A-k11) downstream of the trip units for reactor water level - low/low had not been response-time-tested for an unknown period of time prior to June 21, 1993.
This is a Severity Level IV violation (Supplement I) ~
Unit 2 Technical Specifications, Section 6.8.1, which references NRC Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation), Revision 2, requires written procedures to be established and implemented, Unit 2 Operations Administrative Procedure N2-ODP-OPS-0001, "Conduct of Operations,"
Revision 4, Step 3.3.7, requires:
(1) that when a work order (WO) is generated for repair of a control room deficiency, an action code of "X" is to be 9705280'f54 970516 PDR ADOCK 05000220 G
'I
Enclosure 1
used to denote a control room deficiency; (2) a transparent green dot be placed on or near the affected component or indication; (3) the Station Shift Supervisor (SSS) ensure that the green dot is removed when the deficiency is repaired and the WO is closed; and (4) a quarterly review of control room deficiencies.
Contrary to the above, on March 20, 1997, (1) WO 96-13381, associated with the drywell radiation monitor chart recorder in the control room, was not coded "X"to reflect the control room deficiency; (2) transparent green dots were not placed on or near the control room deficiencies for the control rod and detector display module cooling fan (2CEC" PNL603), or for the turbine controls chart recorder (2TMI-ZR136); (3) the SSS did not remove the green dots for the drywell area temperature chart recorders (2CMS "TRY130 and 2CMS "TRX130) after the WO. was closed; and (4) there was no indication that quarterly reviews were performed.
This is a Severity Level IV violation (Supplement I) ~
Pursuant to the provisions of 10 CFR 2.201, Niagara Mohawk Power Corporation 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 I, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice of Violation (Notice), within 30 days of the date of the letter transmitting this 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 stqps that will be taken to avoid further violations; and (4) the date when full compliance will be aci<<eved.
If an adequate reply is not received within the time specified in this Notice, an order of 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.
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 redaction.
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 King of Prussia, Pennsylvania this 16th day of May, 1997
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