ML20249A219

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Notice of Violation from Insp on 980315-0425.Violation Noted:On 980331 Licensee Failed to Accomplish Scaffolding Erection Activities in Accordance W/Documented Procedure OMMM-022
ML20249A219
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/01/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20249A209 List:
References
50-324-98-05, 50-324-98-5, 50-325-98-05, 50-325-98-5, EA-98-146, NUDOCS 9806160190
Download: ML20249A219 (3)


Text

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NOTICE OF VIOLATION Carolina Power and Light Company Docket Nos. 50-325 and 50-324 Brunswick Units 1 & 2 License Nos. DPR-71 and DPR-62 EA 98-146 During an NRC inspection conducted from March 15 through April 25,1998, five 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.

10 CFR 50 Appendix B. Criteria V. Procedures recuires that activities affecting quality shall be accomplished in accorcance with documented instructions, procedures, and drawings.

Maintenance Management Manual 0MMM-022. Section 6.3.1 states

" Unrestrained scaffold should not be used near safety-related equipment that does not have adequate separation. When unrestrained scaffold is placed near safety-related ecuipment, it shall have a minimum 6" clearance from safety-relatec equipment or components." Additionally.

Section 5.2.1 states " scaffolding must not interfere with normal operation of plant equipment including snubbers and spring cans."

Contrary to the above. on March 31, 1998 the licensee failed to accomplish scaffolding erection activities in accordance with documented procedure OMMM-022.-

Specifically, scaffolding Soles were touching safety-related equipment, were less than six incies away from a Core Spray snubber and were less than six inches from safety-related electrical. conduit.

This is a Severity Level IV violation (Supplement 1).

B.

Technical Specification (TS) 6.8.1.c requires that written procedures shall be established. implemented. and maintained for surveillance and test activities of safety-related equipment.

Nuclear Generation Group Standard Procedure NUA-NGGC-1530. Equipment.

Pressure Test. Protective Coatings, and Special Process Inspection, requires that Quality Control (OC) personnel be qualified and perform the required inspections / verifications set forth in procedures.

Contrary to the above, on March 31. 1998. during the performance of maintenance surveillance test on the #2 Emergency Diesel Generator, an individual that was not qualified. verified that the torquing steps in a procedure were satisfied.

.This is a Severity Level IV violation (Supplement 1).

9806160190 980601 PDR ADOCK 05000324 G

PDR

CP&L-2 C.

.TS 6.8.1.f requires that written 3rocedures shall be established, implemented, and maintained for t1e Fire Protection Program.

Contrary to'the above..the licensee failed to properly establish.

implement, and maintain fire protection periodic test procedures in the.

following two examples:

1)

On March 26, 1998, a fire protection deluge valve was incorrectly reset by not following Periodic Test 2PT-34.16.1.1. Transformer Deluge System Functional Test sequentially.

2)

As of March-11, 1998, the test methodology and acceptance criteria contained in Period Test OPT-34.5.5.0. Engine and Electric Fire Pump Functional Test, was not adequate for the test being conducted in that it did not provide accurate results upon which to make a pump operability determination.

This is a Severity Level IV violation (Supplement I).

D.

License Condition 2.B.(6) requires that the licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the Facility and as approved in the Safety Evaluation Report dated November 22. 1997, as supplemented April 1979. June 11.1980, and December 30. 1986.

Plant Operating Manual 0PLP-01.1. Fire Protection Commitment Document, contains commitments for design, operation. and administrative controls that implement the fire protection 3rogram. Commitment number FB-033.

requires labeled 3-hour fire doors )e provided in all fire areas in the Diesel Generator Building.

Contrary to'the above the licensee failed to maintain labeled three-hour fire doors as designed in all fire areas in the Diesel Generator Building.

Between September 1996 and January 1998, the licensee performed unreviewed modifications to 28 labeled 3-hour fire doors that provided-separation between the Diesel Generators. Emergency Buses, and 4-Day. Fuel Oil Tanks.

The door lockset design was modified by removing operating levers such that, during a fire, the bimetallic strip in the lockset could not lock the door to prevent opening if the panic bar were struck.

This is a Severity Level IV violation (Supplement 1).

E.

10 CFR 50.72(b)(1)(ii) requires that the licensee within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, report any event or condition during operation that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded: or results in the nuclear power plant being in a condition that is outside the design basis of the plant.

L

CP&L 3

10 CFR 50.73(a)(2)(ii) requires that the licensee make a report, within 30 days of discovery, for. any event or condition that resulted in the

condition of the nuclear power plant, including its principal safety barriers, being seriously degraded: or that resulted in the nuclear power plant being in a condition that was outside the design basis of the plant.

Contrary to the above, on January 13.1998. after declaring twenty-eight fire doors inoperable, the licensee failed to report within one hour and make a subsequent report within 30 days that the condition was outside the 10 CFR 50 Appendix R desion basis of the plant. The licensee performed modifications that introduced a common mode failure which degraded the 3-hour rating for twenty-eight fire doors.

The degraded fire doors could have allowed the spread of a fire between redundant safety equipment.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201. Carolina Power and Light 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 II. 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 " 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 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 States Nuclear l-

- Regulatory Commission. Washington, DC 20555-0001.

Because your res)onse will be placed in the NRC Public Document Room (PDR), to the extent possi ale, it should not include any personal privacy. 3roprietary.

or safeguards information so that it can be placed in the PDR wit 1out i

redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be 1

placed in the PDR. and provide the legal basis to support your request for

-withholding the information from the public.

Dated at Atlanta, Georgia This 1st-day of June 1998

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