05000313/LER-2009-001, Manual Reactor Trip from Power in Response to a Loss of Control Rod Drive Cooling Water Flow Due to a Gasket Failure Which Resulted in Air Intrusion Into the Intermediate Cooling Water System

Manual Reactor Trip from Power in Response to a Loss of Control Rod Drive Cooling Water Flow Due to a Gasket Failure Which Resulted in Air Intrusion Into the Intermediate Cooling Water System

ML090930544
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/03/2009
From:	David Bice Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
1CAN040904 LER 09-001-00
Download: ML090930544 (6)

LER-2009-001, Manual Reactor Trip from Power in Response to a Loss of Control Rod Drive Cooling Water Flow Due to a Gasket Failure Which Resulted in Air Intrusion Into the Intermediate Cooling Water System

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 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
3132009001R00 - NRC Website

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1CAN040904 April 3, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Licensee Event Report 50-313/2009-001-00 Arkansas Nuclear One - Unit 1 Docket Nos. 50-313 License Nos. DPR-51

Dear Sir or Madam:

In accordance with 10CFR50.73(a)(2)(iv)(A), enclosed is the subject report concerning a manual reactor trip from power.

There are no new commitments contained in this submittal.

Sincerely, DBB/dce Enclosure Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-5338 David B. Bice Acting Manager, Licensing Arkansas Nuclear One

1CAN040904 Page 2 cc:

Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents@inpo.org

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (9-2007)

LICENSEE EVENT REPORT (LER)

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

APPROVED BY OMB NO. 3150-0104 EXPIRES 8/31/2010 Estimated burden per response to comply with this mandatory information collection request:

80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to bjs1@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Arkansas Nuclear One 05000313 1

OF 4

4. TITLE Manual Reactor Trip From Power in Response to a Loss of Control Rod Drive Cooling Water Flow Due to a Gasket Failure Which Resulted in Air Intrusion Into the Intermediate Cooling Water System

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 02 05 2009 2009 - 001 - 00 04 03 2009 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 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)(ii)(B) 50.73(a)(2)(viii)(B) 1 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)

10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 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) 61 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

OTHER-Specify in Abstract below or in Root Cause One was determined to be that the original design was inadequate in that the selection of the ICW as the cooling water for these compressors was inappropriate since the same water supply provides cooling for the CRD system which is critical for power production.

Root Cause Two was determined to be inadequate documentation of procedures, and instructions which contained erroneous or insufficient information to support the actual configuration and/or design of the components.

D. Corrective Actions

The SA compressors were secured and the ICW supply and return were isolated and the ICW system was vented restoring flow to the CRD cooling system. ICW and CRD Cooling Water flows both returned to normal.

An alternate source of SA without connection to the ICW system was placed in service and the water cooled SA and Instrument Air (IA) compressors were tagged out of service. The air-cooled IA compressors remain in service.

Development of a plant modification to replace the current ICW cooled SA Compressors with appropriately sized air cooled units is being considered.

E. Safety Significance

The event resulted in a plant manual trip from approximately 61% power. Any plant trip is considered a challenge to safety equipment; however, the plant shutdown was uneventful and all systems responded normally. The ICW system is not safety related and is not required to mitigate a design basis accident. Loss of ICW has an adverse affect on plant operation that requires the unit to be shutdown, but does not result in a loss of a safety function.

Nuclear safety, industrial safety, radiological safety and the general safety of the public were not challenged at any time during this event. U.S. NUCLEAR REGULATORY COMMISSION (9-2007) LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

1. FACILITY NAME

2. DOCKET NUMBER (2)

6. LER NUMBER

3. PAGE YEAR SEQUENTIAL NUMBER REVISION NUMBER Arkansas Nuclear One - Unit 1 05000313 2009 001 00 4

OF 4

F. Basis for Reportability A manual reactor trip from power in response to actual plant conditions is reportable pursuant to 10CFR50.73(a)(2)(iv)(A).

G. Additional Information

There were no previous similar events reported as Licensee Event Reports by ANO.

Energy Industry Identification System (EIIS) codes are identified in the test as [XX].