05000313/LER-2005-001, Unit 1 Movement of Irradiated Fuel Assemblies in Reactor Building W/ Reactor Building Purge Effluent Monitor Inoperable & Purge Isolation Valves Open Resulted in Operation Prohibited by Technical
| ML053610164 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/12/2005 |
| From: | James D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1CAN120502 LER 05-001-00 | |
| Download: ML053610164 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 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)(iv)(A), System Actuation 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 |
| 3132005001R00 - NRC Website | |
text
, Entergy Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 501 858 5000 1CAN120502 December 12, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 50-313/2005-001-00 Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51
Dear Sir or Madam:
In accordance with 10CFR50.73(a)(2)(i)(B), enclosed is the subject report concerning operation prohibited by Technical Specifications.
New commitments contained in this submittal are summarized in Attachment 1.
Sincerely, Dale E. James Manager, Licensing DEJ/dh attachment enclosure
-")
4 1CAN120502 Page 2 cc:
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 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 LEREventseinpo.org
Attachment I ICAN120502 List of Regulatory Commitments
II Attachment I to 1 CAN1 20502 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document.
Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TPek l
SCHEDULED ONE-COMPLETION TIME CONTINUING DATE
COMMITMENT
ACTION COMPLIANCE (If Required)
Chemistry procedures will be revised to ensure SPING-1 is not removed from service during fuel handling operations X
February 10,2006 in the reactor building unless TS requirements are satisfied.
U NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may tdioitschisrt~ine rs for Fra h hulork' not conduct or sponsor, and a person is not required to respond to, the
- 3. PAGE Arkansas Nuclear One - Unit 1 05000 313 1 OF 3
- 4. TITLE Movement of Irradiated Fuel Assemblies in the Reactor Building with Reactor Building Purge Effluent Monitor Inoperable and Purge Isolation Valves Open Resulted in Operation Prohibited by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNTA RVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER REV MONTH DAY YEAR 0A000 FACILITY NAME DOCKET NUMBER 10 13 2005 2005 -
001 -
00 12 12 2005 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check al that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 03 50.73(a)(2)(i)(C)
O 50.73(a)(2)(vii) 6 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(iI)(A)
El 50.73(a)(2)(viii)(A) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) l 50.73(a)(2)(viii)(B)
O 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E
20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
E3 50.73(a)(2)(iv)(A) a3 50.73(a)(2)(x) 0 20.2203(a)(2)(iii)
E 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El 73.71(a)(4) 000 0
20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 0l 50.73(a)(2)(v)(B)
E3 73.71(a)(5) o 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C)
E OTHER O 20.2203(a)(2)(vi) 0 50.73(a)(2)(')(B)
E3 50.73(a)(2)(v)(D)
Specify in Abstract below
-~ i., KIW I C.........
A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Arkansas Nuclear One / Dee Hawkins 479-858-5589CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE MPNNJFACTURER j TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR o
YSUBMISSION El YES (if yes, complete 15. EXPECTED SUBMISSION DATE)
NO l
DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On October 13, 2005, during a scheduled refueling outage, with fuel offload in progress, super particulate iodine noble gas (SPING) effluent monitor, SPING-1, was removed from service for required surveillance testing. Operations personnel failed to recognize that Technical Specifications (TS) require SPING-1 to be operable when the reactor building purge isolation valves are open and fuel movement is in progress in the reactor building. Sampling was performed and SPING-1 was returned to service. On October 14, 2005, prior to removing SPING-1 from service again for sampling, operations personnel recognized that this configuration was not allowed with fuel movement in progress in the reactor building and realized that the removal of SPING-1 from service the previous day resulted in operation prohibited by TS. This event can be attributed to inadequate guidance regarding the TS requirement to maintain SPING-1 operability during fuel movement in the reactor building.
Procedures will be revised to ensure SPING-1 is not removed from service during fuel handling operations in the reactor building unless TS requirements are satisfied.
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A.
Plant Status At the time this condition was discovered, Arkansas Nuclear One, Unit 1 (ANO-1) was in a scheduled refueling outage with fuel handling activities in progress in the reactor building [NH].
B.
Event Description
ANO-1 Technical Specifications (TS) requires super particulate iodine noble gas (SPING) effluent monitor, SPING-1 [IL], to be operable when the reactor building purge isolation valves are open and fuel movement is in progress in the reactor building. If the SPING becomes inoperable, TS requires the movement of irradiated fuel to be suspended immediately. On October 13, 2005, SPING-1 was removed from service for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 43 minutes, with fuel movement in progress in the reactor building. Fuel movement was not suspended as required.
SPING-1 is a self-contained microprocessor-based radiation detection system for monitoring particulate, iodine and noble gases in the reactor building ventilation system [VA]. On October 13, 2005, chemistry personnel requested permission from the control room to remove SPING-1 from service to perform surveillance testing in accordance with Off Site Dose Calculation Manual (ODCM) requirements. The ODCM requires weekly sampling of active effluent pathways. Although fuel offload was in progress at the time, operations personnel did not recognize that the removal of SPING-1 from service was prohibited by TS and granted chemistry personnel permission to remove SPING-1 from service for sampling. Sampling was performed and SPING-1 was returned to service.
On October 14, 2005, chemistry personnel again requested permission to remove SPING-1 from service for sampling. At this time, operations personnel in the control room recognized that this configuration was not allowed with fuel movement in progress in the reactor building.
Operations personnel further realized that the removal of SPING-1 from service the previous day was performed during fuel movement, thus resulting in operation prohibited by TS.
C.
Root Cause This event can be attributed to inadequate guidance regarding the TS requirement to maintain SPING-1 operability during fuel movement in the reactor building.
The chemistry procedure used to perform sampling of Unit I vents did not require verification that fuel movement was not in progress in the reactor building prior to the removal of SPING-1 from service.
The TS requirement for SPING-1 to be operable to maintain the reactor building purge isolation valves operable during fuel movement was not common knowledge among the operations staff.
11-(If more space is required, use additional copies of NRC Forn 366A)
D.
Corrective Actions
Chemistry procedures will be revised to ensure SPING-1 is not removed from service during fuel handling operations in the reactor building unless TS requirements are satisfied.
The requirement to verify SPING-1 operability was clarified in operations procedure 1502.004, "Control of Unit 1 Refueling," Attachment B, to ensure the TS requirement for maintaining the SPING operable during refueling operations is met.
This event was incorporated into the operations continuing training program to increase operator cognizance of the requirement to maintain SPING-1 operable during fuel handling in the reactor building when the reactor building purge valves are required to be operable.
E.
Safety Significance
Spent fuel assemblies are handled entirely under water. Before refueling, the boron concentrations of the reactor coolant and the fuel transfer canal water above the reactor are increased so that, with all control rods removed, the core will not become critical. Although mechanical damage to the fuel assemblies during transfer activities is improbable, a mechanical damage type of accident is considered the maximum potential source of activity release during refueling operations. The offsite dose consequences from gases released during a fuel handling accident directly to the atmosphere with no filtration, assuming the reactor has been shut down for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> (TS prohibits fuel handling operations prior to this time), will not exceed 25 percent of IOCFR100 limits. Therefore, this condition had minimal
safety significance
F.
Basis for Reportability Technical Specification 3.9.3 requires each penetration providing direct access from the reactor building atmosphere to the outside atmosphere to be capable of being closed by an operable reactor building purge isolation valve with the purge exhaust radiation monitoring channel operable. With a reactor building penetration not in the required status, movement of irradiated fuel assemblies within the reactor building is to be suspended immediately.
Movement of irradiated fuel assemblies on October 13, 2005, with SPING-1 inoperable resulted in operation prohibited by TS. This report is submitted in accordance with 1 OCFR50.73(a)(2)(i)(B).
G.
Additional Information
There have been no previous similar Licensee Event Reports submitted by ANO.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].