ML20135C707

Notice of Violation from Insp on 960805-09.Violation Noted: Fuel Handling Event Involving Fuel Assembly N8C6 Was Not Recorded in Operating Logs or Refueling Log & Main Fuel Handling Bridge Was Not Verified for Indexing

ML20135C707
Person / Time
Site:	Crystal River
Issue date:	02/21/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20135C667	List: ML20135C664 ML20135C707
References
50-302-96-10, EA-96-316, NUDOCS 9703040222
Download: ML20135C707 (4)

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NOTICE OF VIOLATION l

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Florida Power Corporation Docket No. 50 302 l Crystal River Unit 3 License No. DPR 72 EA 96 316 i During an NRC inspection conducted on August 5 9, 1996, 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:

A. Technical Specification 5.6.1.1 requires written procedures be established, implemented and maintained covering the applicable arocedures recommended in Regulatory Guide 1.33 Revision 2. Appendix A, rebruary 1978. Regulatory Guide 1.33, Appendix A requires administrative procedures regarding procedure adherence and log entries and procedures covering refueling and core alterations. Procedure AI-500. Conduct of Operations, paragraph 4.2, Nuclear Safety Standards and Procedures, requires that written procedures shall be adhered to at all times except as described by AI-400E. Procedure AI 400E, Performance and Transmittal of Procedures, paragraph 1.1. Policy, requires that j verbatim compliance of procedures is required but that procedures must i not be blindly followed.

0)erations Instruction 01-5, Log Keeping, states in the Standard, "4arrative and chronological logs shall contain enough detail to l

effectively transfer the full status of the watchstation to the 1 on coming crew. It shall be a complete and accurate historical record of significant events occurring during the shift and items discovered by the on duty o>erator". Procedure OI 5 step 3.1 states, in part, " Shift supervision s1ould ensure the crew's total record of shift activities contains the elements necessary to meet the standard," and includes examples of items that should be entered in Operating Logs which include, " Events involving radioactive mediums." Refueling Procedure FP-203 dated 3/15/96, "Defueling and Refueling Operations", paragraph 3.1.3.2. states, in part, that the refueling log is maintained on a shift basis to record refueling events and problems in chronological order.

Procedure FP-203 paragraph 4.4.8 states ,"The CCR0 shall provide permission to proceed after verifying the Main Fuel Handling Bridge is indexed to the proper location." Procedure FP 203 paragraph 4.4.9 states, "The Refueling Area Supervisor, or his designated spotter, should verify the mast is indexed over the proper location and that the location is empty prior to attempting to insert the fuel assembly." In addition, Procedure FP 203 paragraph 3.2.18 states, in part,"When a fuel assembly considered potentially damaged with respect to fuel handling concerns is encountered, the following will be performed immediately:

(a) Change the SNM move sheets to preclude movement of the fuel l assembly; and (b) Put a tag on the refueling tag board stating the fuel i assembly is not to be moved. Upon completion of a PRC review, these I restrictions may be removed, providing all PRC mandatory requirements are met."

9703040222 970221 Enclosure 1

$DR ADOCK 05000302 PDN

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2 Contrary to the above, on March 26, 1996, activities were not i accomplished in accordance with procedures in that:

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1. The fuel handling event involving fuel assembly N8C6 was not l recorded in any Operating Logs nor in the Refueling Log. )

2. The Control Center Refueling Operator (CCRO) did not verify the Main Fuel Handling Bridge was indexed to the proper location of position 010 prior to providing permission to proceed.

3. The Refueling Area Supervisor did not verify that the mast was indexed over the proper location and that the location was empty prior to inserting fuel assembly N8C6 into position R10.

4. Fuel assembly NSC6 was moved from position R10 to position 010 and lowered into the core without an analysis or visual verification that the assemblies involved or parts thereof were not damaged.

(01014)

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

B. 10 CFR 50, Appendix B, Criterion XVI requires that measures shall be  !

established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure i that the cause of the condition is determined and corrective action  ;

taken to preclude repetition. i l

Contrary to the above, on August 9, 1996, conditions adverse to quality I regarding the fuel handling event of March 26, 1996, had not been promptly identified and corrected. The licensee's investigation of the event did not assure that the cause of the condition was adequately determined and that sufficient corrective actions had been taken to preclude repetition. The licensee failed to adequately identify the significance of the event and the reason why it had not been immediately  :

reported to licensee management and failed to identify the failure to follow procedures as a root cause contributor. Furthermore, the licensee's investigation report was not reviewed by the Manager of the Safety Assessment Team until June 25, 1996. Three months passed before the report was forwarded for departmental review of the proposed corrective actions. (02014)

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

Pursuant to the provisions of 10 CFR 2.201 Florida 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 II, and a copy to the NRC Resident Inspector at the Crystal River facility 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 Enclosure 1

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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 com)liance will be achieved. Your response may reference or include 3revious docceted correspondence, if the correspondence adequately addresses t;e 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.

4 Because your res>onse will be placed in the NRC Public Document Room (PDR), to the extent possi 31e, it should not include any personal privacy, aroprietary, or safeguards information so that it can be placed in the PDR wit 1out 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 l redacted copy of your response that deletes such information. If you request withholding of such material, you must s)ecifically identify the portions of i your response that you seek to have withield 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.

1 Dated at Atlanta, Georgia l this J/# day of February 1997 l

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SYNOPSIS The U.S. Nuclear Regulatory' Commission (NRC). Region II, Office of Investigations, initiated this investigation based on NRC staff findings of procedural violations by Florida Power Cor) oration reactor operators at the Crystal River Nuclear Plant. A fuel.assemaly was lowered on top of another during an outage. No report was made of the event and management was not notified for two days.

Based on testimony provided by the shift personnel involved and NRC technical staff evaluation of the testimony, it is concluded there was not sufficient evidence developed to substantiate wrongdoing by the persons involved in the event. Furthermore, it is concluded the licensee was not required to report the event to the NRC.

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Case No. 2-96 033 .

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