ML15118A307
| ML15118A307 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/13/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15118A306 | List: |
| References | |
| 50-269-98-06, 50-269-98-6, 50-270-98-06, 50-270-98-6, 50-287-98-06, 50-287-98-6, NUDOCS 9807200396 | |
| Download: ML15118A307 (4) | |
Text
NOTICE OF VIOLATION Duke Energy Corporation Docket No. 50-269,270,287 Oconee 1. 2, and 3 License No. DPR-38.47,55 During an NRC inspection conducted from May 3 to June 13. 1998, violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions." NUREG 1600, the violations are listed below:
A.
Technical Specification 6.4.1.e requires the station be maintained in accordance with approved procedures and that written procedures with appropriate checkoff lists and instructions be provided for preventive or corrective maintenance which could affect nuclear safety or radiation exposure to personnel.
Contrary to the above on May 18, 1998. a self disclosing event revealed that a procedure did not exist for the adjustment of loss of coolant restraints on the reactor coolant pumps. Without proper adjustment, the 2A1 reactor coolant pump shaft rubbed on a non-critical cover of the pump requiring the pump to be shutdown and repairs to-be performed.
This is a Severity Level IV violation (Supplement I).
B.
Technical Specification 6.4.1.j requires the station be operated in accordance with approved procedures and that written procedures with appropriate checkoff lists and instructions be provided for nuclear safety-related periodic test procedures.
Procedure IP/0/A/0310/012B, Engineered Safeguards Logic subsystem 1 LPI Channel 3 On-line Test, Revision 28. Step 10.9.7 states to start the 1A low pressure service water pump by depressing the manual push-button for LPSW-P1A.
Contrary to the above, on May 18, 1998. the station (Unit 1) was not operated in accordance with approved procedures in that an operator in the control room started low pressure injection pump 1A instead of low pressure service water pump 1A. This resulted in an inadvertent start and run of an emergency core cooling system component, the 1A low pressure injection pump.
This is a Severity Level IV violation (Supplement I).
C.
Technical Specification 6.4.1.e requires the station be maintained in accordance with approved procedures and that written procedures with appropriate checkoff lists and instructions be provided for preventive or corrective maintenance which could affect.nuclear safety or radiation exposure to personnel.
Nuclear System Directive 301, Nuclear Station Modifications, Revision
- 13. requires that prior to a modified system, structure, or component 9807200396 980713 PDR ADOCK 05000269 G
being ready for acceptance by the operational controlling group.
procedure revisions, including new procedures, shall be completed.
Contrary to the above, on May 1, 1998. the licensee placed the Unit 2 siphon seal water system (Nuclear Station Modification ON-52932) in service without developing a new procedure for maintaining a portion of the system. Specifically. Procedure MP/0/A/1600/028. Strainer - Mueller
- Removal, Cleaning And Installation, Revision 0.
was not issued to provide for cleaning the system strainers. This resulted in a delay in cleaning the strainers when indicated strainer differential pressure exceeded the maximum scale reading.
This is a Severity Level IV violation (Supplement I).
D.
10 CFR 50 Appendix B. Criterion V. Instructions, Drawings, and Procedures, states that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, and drawings.
Nuclear System Directive 209, 10 CFR 50.59 Evaluations. Revision 7, requires that changes to anything described in the safety analysis report describing controls over plant configuration be evaluated for an unreviewed safety question.
Contrary to the above. May 27. 1998, the licensee changed the controls for limiting quadrant power tilt without evaluating the change for an unreviewed safety question. Specifically, the licensee changed the quadrant power tilt limits listed in the Unit 2 Cycle 17 core operating limits report without doing the unreviewed safety question determination.
This is a Severity Level IV violation (Supplement I).
E.
10 CFR 20.1101(a), states that each licensee shall develop, document, and implement a radiation protection program commensurate with the scope and extent of licensed activities and sufficient to ensure compliance with the provisions of this part.
System Radiation Protection Manual, which implements 10 Code of Federal Regulations Part 20.1101(a), Procedure.I-13 Use of Protective Clothing and Related Equipment. Revision 2, requires personnel removing protective clothing to. "Remove booties as you transfer to the step-off pad which is clean."
Nuclear System Directive 507. Radiation Protection, Revision 1.
also requires, in Section 507.8.5. that booties be removed while transferring to the step-off which is clean.
-Contrary to the above, on May 7, 1998. a worker exiting a contaminated SII
(III3 area transferred to the step-off pad without removing booties.
This is a Severity Level IV violation (Supplement IV).
F.
Paragraph 3.E of the Oconee operating license states that the licensee shal! implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the safety evaluation reports (i.e., NRC's Fire Protection Safety Evaluation Reports).
Section 9.5.1.3 of the Oconee Updated Final Safety Evaluation Report states, in part. "Procedures have been developed to control transient storage of materials and state the parameters of allowable storage of combustible materials for Oconee. If wood is required, (inside buildings containing safety-related systems) only fire retardant treated wood is used."
Section C.6.4 of the Oconee Fire Protection Safety Evaluation Report dated August 11, 1978. states, "The licensee has identified the facility procedures which implement the controls to minimize the amount of combustibles that a safety-related area may be exposed to...
We find that the control of combustibles conforms to the provisions of Appendix A to Branch Technical Position (BTP) 9.5-1 and is, therefore, acceptable."
Plant Design Basis Specification for Fire Protection, OSS-0254.00-00-00 4008, Revision 2, outlines the program for control of combustibles and housekeeping at the Oconee facility. Administrative Nuclear System Directives (NSDs), NSD 313, NSD 116. and NSD 104 are the fire protection program documents that provide the facility's standards and practices for control of combustibles and housekeeping.
Nuclear Site Directive 313,"Control of Combustibles and Flammable Material,"
Revision 1, Section 313.3.3. and Nuclear Site Directive 104, "Housekeeping Materiel Condition, and Foreign Material Exclusion,"
Revision 13, Section 104.5.1 state, in part, that: (1)
The doors of site fire resistive flammable liquids storage cabinets be kept closed and latched at all times except for entry: (2)
Only fire retardant treated wood shall be used: (3)
Untreated combustible packing materials be removed immediately upon equipment unpacking: (4)
All work areas be cleaned of unnecessary material, waste materials and trash upon completion of a job *or at the end of each shift, whichever comes first:
and, (5)
Tools, materials, and equipment be removed at job completion and returned to designated storage areas.
Contrary to the above, as of May 15. 1998, the licensee failed to properly implement and maintain in effect the provisions of the approved fire protection program for the control of combustibles and housekeeping as evidenced by the following: fire resistive flammable liquids storage cabinets in the safe shutdown facility diesel generator room and on the turbine deck were left open or unlatched, non fire-retardant treated
pallets were stored on the turbine deck, non fire-retardant treated wood pieces were left in cable trays in the Unit 1 cable spreading room, combustible cardboard boxes containing piping insulation were being stored in a scaffold staging areas of the turbine building, and work related transient combustible materials, tools and hand-held equipment, were left unattended in the plant turbine building, without housekeeping tags or with out-of-date tags.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201. Duke Energy Corporation, is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission. ATTN:
Document Control Desk. Washington, DC 20555, with a copy to the Regional Administrator, Region II.
and a copy to the NRC Resident Inspector. Oconee Nuclear Station, 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 will be 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 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, U. S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001.
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. If personal privacy or proprietary information is 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 must specifically identify the portions of your response that you seek to have withheld and provide in 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 information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia this 13th day of July 1998