05000298/LER-2009-001, Regarding Disarmed Control Rod Technical Specification Requirements Not Met

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Regarding Disarmed Control Rod Technical Specification Requirements Not Met
ML100050071
Person / Time
Site: Cooper Entergy icon.png
Issue date: 12/29/2009
From: Dori Willis
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2009098 LER 09-001-00
Download: ML100050071 (6)


LER-2009-001, Regarding Disarmed Control Rod Technical Specification Requirements Not Met
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2982009001R00 - NRC Website

text

N Nebraska Public Power District "Always there when you need us" NLS2009098 December 29, 2009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Licensee Event Report No. 2009-001-00 Cooper Nuclear Station, NRC Docket 50-298, DPR-46

Dear Sir or Madam:

The purpose of this correspondence is to forward Licensee Event Report 2009-001-00.

Sincerel,,

/jf Enclosure cc:

Regional Administrator w/enclosure USNRC - Region IV Cooper Project Manager w/enclosure USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/enclosure USNRC - CNS SRAB Administrator w/enclosure NPG Distribution w/enclosure INPO Records Center w/enclosure SORC Administrator w/enclosure CNS Records w/enclosure COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

Abstract

On November 1, 2009 at 0746 Central Standard Time, Operations personnel determined the requirements of Technical Specifications (TS) Limiting Condition for Operation 3.10.4, Single Control Rod Withdrawal-Cold Shutdown, were not met when it was discovered the control rods in the five by five (5x5) array around control rod 50-19 had been rearmed and the clearance order released. Cooper Nuclear Station was in day 37 of refueling outage RE25, Mode 4, Cold Shutdown operation. Control rod 50-19 was being returned to service after replacement of its control rod drive mechanism (CRDM) O-ring seal with the control rod still withdrawn and uncoupled from its CRDM at the time of discovery, The cause of the error is attributed to inadequate programmatic controls for maintaining configuration control of the 5x5 array. Immediate actions were taken to restore compliance with TS until control rod 50-19 was restored to operability.

Actions to preclude recurrence include revising appropriate procedures and

.communicating management expectations for clearance order activities. This event is considered to have negligible safety significance.

NRC FORM 366 (9-2007)

(If more space is required, use additional copies of (If more space is required, use additional copies of log documented the CRDM flange bolts were torqued at 0333 CST, the clearance order tags for the control rods in the 5x5 array were authorized for release at 0405 CST, and signed as released at 0552 CST. Prior to and during the CRDM maintenance, TS LCO 3.10.4 requirements were met. However, the requirements of TS LCO 3.10.4 for having control rod 50-19 withdrawn in Mode 4 required either the control rod to be operable or the control rods in a 5x5 array around the inoperable control rod to be disarmed.

A control rod is disarmed by disconnecting its Amphenol connector at the Control Rod Drive System [EIIS: AA] Hydraulic Control Unit [EIIS: HCU]. The control rods in the 5x5 array centered on control rod 50-19 were rearmed by connecting the Amphenol connectors on the control rods before control rod 50-19 had been recoupled to its CRDM and declared operable. Upon discovery, compliance with TS LCO 3.10.4 was re-established by disconnecting the Amphenol connectors to disarm the control rods in the 5x5 array and a clearance order hung until control rod 50-19 was recoupled and made operable.

Investigation into the event identified that the assigned Senior Reactor Operator (SRO) did not recognize the 5x5 array requirement existed for this maintenance activity while in Mode 4. Consequently, the SRO treated the task like CRDM work in Mode 5-Refueling, where the 5x5 array requirement was not applicable. No specific procedure guidance existed for the clearance order method to be used for this configuration. The need for maintaining the 5x5 array was not adequately communicated to the assigned SRO during turnover; therefore, the SRO misunderstood a notation on the clearance order regarding use of the temporary lift process. The Work Control Center SRO authorizing release of the 5x5 array clearance order did not validate the operational impact of its release as directed by the tagout procedure. While not a specific requirement, the authorizing SRO also did not use the available checklist for authorizing the.clearance order release and consequently did not inform the Control Room of the clearance order release.

BASIS FOR REPORT This event is being reported as an operation or condition prohibited by plant TS per 10 CFR 50.73(a)(2)(i)(B). Although CNS took actions in accordance with the TS once the condition was discovered, the condition that the TS prohibited had existed for up to four hours. The applicable actions required by the TS are required to be taken immediately.

(If more space is required, use additional copies of Form 366A)

SAFETY SIGNIFICANCE

This non-compliance with the TS is considered to have negligible safety significance.

Unacceptable reactivity excursions were always precluded through compliance with other aspects of TS LCO 3.10.4. Specifically, all other control rods were fully inserted and a control rod withdrawal block was inserted. Therefore, reactivity excursions were prevented and the reactor remained within analyzed conditions for a single control rod being withdrawn. Additionally, adequate shutdown margin was maintained even if the next strongest rod was withdrawn.

CAUSE

The root cause of this event is that programmatic controls in place were inadequate to maintain configuration control of the control rods in the five by five array required by TS LCO 3.10.4 while in Mode 4.

CORRECTIVE ACTION

The following corrective actions will be taken and tracked in the CNS corrective action program:

1. Revise the controlling surveillance procedure used to withdraw the control rod during Mode 4 or 5 operation to ensure a clearance order is controlling configuration of the five by five array requirement separate from the maintenance clearance order.
2. Revise a conduct of operations procedure to include use of separate clearance orders for maintenance and configuration control of components specified by TS conditions and required actions.
3. Revise the tagout procedure to add a requirement to use the Clearance Order Approval Checklist when authorizing a clearance order for hang and release activities.
4. Communicate management expectations to Operations Department personnel stressing the importance of informing the Control Room of all clearance order hang and release activities.

An interim action is in place for controlling configuration of equipment involving TS LCOs of control rods, primary containment isolation valves and secondary containment isolation valves until the listed actions have been completed.

PREVIOUS EVENTS There have been no related reportable events.

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© 4 ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© 4

Correspondence Number: NLS2009098 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory

commitments

Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITMENT

COMMITTED DATE

COMMITMENT

NUMBER OR OUTAGE None 4

4 4

4 PROCEDURE 0.42 REVISION 24 PAGE 18 OF 25