05000397/LER-2011-001, Regarding Failure to Follow Technical Specification During Control Rod Exercise
| ML11256A028 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/29/2011 |
| From: | Sawatzke B Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-11-143 LER 11-001-00 | |
| Download: ML11256A028 (4) | |
| 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)(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)(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 |
| 3972011001R00 - NRC Website | |
text
Bradley J. Sawatzke Columbia Generating Station ENOERGYWa.O. Box 968, Richland, WA 99352-0968 UIRIHI' EST Ph. 509.377.43001 F. 509.377.4150 bjsawatzke @ energy-northwest.com August 29, 2011 G02-11-143 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSEE EVENT REPORT NO. 2011-001-00
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2011-001-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(i)(B). The enclosed report discusses items of reportability and corrective actions taken related to non-compliance with Technical Specifications concerning Rod Position Indication. This discrepant condition was discovered on June 29, 2011.
There are no commitments being made to the NRC herein. If you have any questions or require additional information, please contact Ms. L.L. Williams at (509) 377-8148.
Respectfully, B.J. S /iake Vice President, Nuclear Generation & Chief Nuclear Officer
Enclosure:
Licensee Event Report 2011-001-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C R.N. Sherman - BPA/1 399 W.A. Horin - Winston & Strawn
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Columbia Generating Station 05000397 1 OF3
- 4. TITLE Failure to follow Technical Specification during Control Rod Exercise
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUBR N.
MONTH DAY YEAR050 NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 06 29 2011 2011 - 001 - 00 08 29 2011 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITFED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5 El 20.2201(b)
El 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
[E 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203 (a)(1)
El 20.2203(a)(4)
[E 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
[E 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A)
[: 50.73(a)(2)(x) 0%
[E 20.2203(a)(2)(iii)
El 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
Cl 50.46(a)(3)(ii)
[I 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
[E 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in Further Corrective Actions The following corrective actions are planned or have been completed:
Provided remediation training for the on-duty RO and CRS to address inadequate verification of required TS. (Completed)
Developed training for licensed operators concerning shutdown TS. (In Progress)
Reinforced expectations for TS implementation and verification through a night order. (Completed)
Replaced the control rod RPIS probe for control rod 34-47. (Completed)
Assessment of Safety Consequences
The full-in position indication channel is required to be operable so that the refueling interlocks can ensure that fuel cannot be loaded with any control rod withdrawn and that no more than one control rod can be withdrawn at a time. These restrictions prevent inadvertent criticality during refueling operations. At the time that the rod position indication failed to meet the TS surveillance requirements, Columbia was not moving fuel, only one control rod was being withdrawn, and all other control rods were fully inserted. There was no potential for an inadvertent criticality. The plant remained within the assumptions of the safety analysis at all times.
Withdrawal of control rod 34-47 was suspended and the rod was fully inserted prior to movement of another rod. This event was of low safety consequence.
Similar Events
A search of the last ten years of Columbia's condition reports and LERs showed no previous occurrences of a failure to enter the required action statement of TS 3.9.4. However, there have been four similar events in which other TS and their bases were not verified prior to performance of an evolution that resulted in a TS not being met at Columbia within the last ten years. These incidences are documented in LERs 2001-001-00, 2003-004-00, and 2004-001-00.
Energy Industry Identification System (EIIS) Information EIIS codes are bracketed [ ] where applicable in the narrative.
26158 R5