05000219/LER-2005-001, Regarding a Control Rod Drive Pump Was Returned to Service Prior to Correcting the Cause of Failure Resulting in a Technical Specification Violation

Regarding a Control Rod Drive Pump Was Returned to Service Prior to Correcting the Cause of Failure Resulting in a Technical Specification Violation

ML051180012
Person / Time
Site:	Oyster Creek (DPR-016)
Issue date:	04/15/2005
From:	Swenson C AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-05-20069 LER 05-001-00
Download: ML051180012 (4)

LER-2005-001, Regarding a Control Rod Drive Pump Was Returned to Service Prior to Correcting the Cause of Failure Resulting in a Technical Specification Violation

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2192005001R00 - NRC Website

text

AmerGen S.

AmerGen Energy Company, LLC www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ o8731,o388 License Condition 2.E 10 CFR 50.73 (b), (c), (e)

April 15, 2005 2130-05-20069 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

License Event Report 2005-001-00, A CRD Pump was Returned to Service Prior to Correcting the Cause of Failure Resulting in a Technical Specification Violation Enclosed is License Event Report 2005-001, Revision 0, a 30 day report required by Oyster Creek license condition 2.E. This event did not affect the health and safety of the public or plant personnel. This event did not result in a safety system functional failure.

If any further information or assistance is needed, please contact David Fawcett at 609-971-4284.

Sincerely, N. Swenson Vice President, Oyster Creek Generating Station CNS/DIF Enclosure: NRC Form 366, License Event Report 2005-001-00 cc:

S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 05030

NR IOR 36 U.S NULA REGULATORY C-

'I NRCSFORM 366 U.S. NUCLEAR REGULATORY C (6-2004)

LICENSEE EVENT REPORT (LER)

COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES 06@3C007

, the NRC may not conduct or sponsor. and a person Is not required to respond to. the Information collection.

(See reverse for required number of digits/characters for each block)

3. PAGE

- OysterCreekUrnit l

05000 1

OF

--- i

4.

y TItLe Fo eek u 00 OF [7

4. TITLE Cori'Fol Rod.Dinve Pump Was Returned to Ser'vce Prior to Correcting t e Cause of Failure ResuIng i a Technical Snecification Violatio'n

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE S. OTHER FACILITIES INVOLVED SEOUEN1RAL FACnUTY NAME DOCKET NUMBER MONTH DAY YEAR YAR NNO MONTH DAY YEAR 05000 03

^18.

'2005.2005

001

,-0 i

005'FACILITYNAME DOCKETNUMBER 0....

. 005- - -:'C0 0

04.; 5-.2*.-

05000

9. OPERATING MODE 11.THIS REPORT IS SUBMITTED PURSUANTTO THE REOUIREMENTS OF 10 CFR 5: (Check all that apply)

I 20.2201 (b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201 (d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)Cii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(ix)(A)

10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(1v)(A) 50.73(a)(2)(x) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 100 20.2203(a)(2)(v) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

/

OTHER 20.2203(a)(2)(vi)

/

50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Spe-fy In Abstract below or Ini (If more space Is required, use additionalcoples of (If mreorspace is required, use additional copies of NRC Form 366A)

Cause of Event

The apparent cause of this event was failure to determine and correct the cause of UAU CRD Pump failure on February 17,2005 prior to returning it to service. The apparent cause of the loose connection was poor construction technique by the vendor who supplied the relay panel.

Immediate corrective actions

(1) Replaced the relay, sent it out for failure analysis and tightened the loose connection.

(2) Verified the closing spring condition on all safety related 480 VAC breakers.

The Root Cause Analysis that is currently in progress will determine long-term corrective actions and will be reported in a supplemental report.

Additional Information

A. Failed Components:

Loose wire connected to the cross-threaded screw. The relay that this loose contact is associated with was supplied pre-wired to the relay panel that was installed in the 1A2 Local Shutdown Panel, which included the cross-threaded connection.

B. Previous similar events

None C. Identification of components referred to in this Licensee Event Report:

Components IEEE 805 System ID IEEE 803A Function CRD Pump EIIS-AA P

480 VAC Breaker EIIC-52 JX NRC FORM 366 (6-2004)