05000482/LER-2005-003, Re Failure to Maintain Closure of Containment Penetrations During Fuel Movement
| ML051870321 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/29/2005 |
| From: | Hedges S Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| WO 05-0021 LER 05-003-00 | |
| Download: ML051870321 (6) | |
| 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 |
| 4822005003R00 - NRC Website | |
text
WELF CEEK
'NUCLEAR OPERATING CORPORATION Stephen E. Hedges Vice President Operations and Plant Manager June 29, 2005 WO 05-0021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,-DC 20555
Subject:
Docket No. 50-482: Licensee Event Report 2005-003-00 Gentlemen:
The enclosed Licensee Event Report (LER) 2005-003-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) regarding a failure to maintain closure of containment penetrations during fuel movement.
Commitments made by Wolf Creek Nuclear Operating Corporation in the enclosed LER are identified in the Attachment to this letter.
If you have any questions concerning this matter, please Kevin Moles at (620) 364-4126.
contact me at (620) 364-4190, or Mr.
Very truly yours, E. Hedges SEH/rIg Enclosure cc:
J. N. Donohew (NRC), w/a, w/e W. B. Jones (NRC), wla, w/e B. S. Mallett (NRC), wla, w/e Senior Resident Inspector (NRC), wla, w/e
x'92)N P.O. Box 411 / Burlington. KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer MIF/HCNET
Attachment to WO 05-0021 Page 1 of 1 LIST OF COMMITMENTS The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation (WCNOC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr. Kevin Moles, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4126.
COMMITMENT
Due Date/Event Steps will be added to procedure CKL PE-352 to install and August 16, 2005 remove a blind flange to the exterior auxiliary access hatch equalizing valve.
The exterior auxiliary access hatch equalizing valve will be
- - August 16, 2005 added to procedure STS GP-006 as a containment penetration.
STS GP-006 will be revised to have operations provide a September 13, 2005 dedicated computer and work station for the Containment Closure Trackers that will integrate the individuals performing this task into the Work Control Center during Refueling outages.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3W2007 (6-2004)
, the NRC may (See reverse for required number of not conduct or sponsor, and a person Is not required to respond to, the digits/characters for each block)
Information collection.
- 3. PAGE WOLF CREEK GENERATING STATION 05000 482 1 OF 4
- 4. TITLE Failure to Maintain Closure of Containment Penetrations During Fuel Movement
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED EA SEQUENTIALI REV
.FACILrrY NAME DzOCKE TNUMBER MONTH DAY YEAR E
EUE R
MONTH DAY YEAR NUBR NO.
50
.FACILITY NAME DOCKETrNUMBER 04 30 2005 2005 -
003 -
00 06 29 j 2005 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 6 5 20.2201(b)
D 20.2203(a)(3)(i) a 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii) o 20.2201(d) 5 20.2203(a)(3)(ii) 5 50.73(a)(2)(ii)(A) 5 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 5 20.2203(a)(4) 5 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
D 20.2203(a)(2)(i) 5 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL a
20.2203(a)(2)(ii) 5 50.36(c)(1)(ii)(A) 5 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) o 20.2203(a)(2)(iii)
D 50.36(c)(2) 5 50.73(a)(2)(v)(A)
D 73.71(a)(4) 0 D 20.2203(a)(2)(iv) 5 50.46(a)(3)(ii) 5 50.73(a)(2)(v)(B) 5 73.71(a)(5)
D 20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C) 5 OTHER O 202203(a)(2)(vi) 50.73(a)(2)(i)(B) 5 50.73(a)(2)(v)(D)
Specify In Abstract below or In (if more space Is required, use additional copies of (if more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
Steam Generator Pathway STS GP-006 will be revised to have operations provide a dedicated computer and work station for the Containment Closure Trackers that will integrate the individuals performing this task into the Work Control Center during Refueling outages. This change will be completed by September 13, 2005.
Lessons learned from this event have been incorporated into Operating Experience for Licensed Operator Requalification training.
SAFETY SIGNIFICANCE
During movement of irradiated fuel assemblies within Containment, the most severe radiological consequences result from a fuel handling accident. The fuel handling accident is a postulated event that involves damage to irradiated fuel. Fuel handling accidents include dropping a single irradiated fuel assembly and handling tool or a heavy object onto other irradiated fuel assemblies. In Mode 6, the potential for Containment pressurization as a result of a fuel handling accident is minimal.
Therefore, it is highly unlikely that there will be any significant release of radioactive material through the leakage path as described above. If a release were to take place through this path, the quantity of radioactive materials released to the outside environment would be insignificant. Even though the rate of leakage can not be determined, based on engineering judgment, the consequences of this release will be bounded by the fuel handling accident analysis performed for Amendment 95 to the WCGS T/S. The analysis assumes that the gaseous effluents escaping from the damaged fuel rods are released directly to the environment within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> through the open personnel airlock doors. The effluents do not mix with the surrounding air of the adjacent Auxiliary Building, and no credit is taken for any iodine removal by the atmosphere filtration system filters. The analysis results demonstrate that the potential dose consequences from a fuel handling accident with the personnel airlock doors remaining open will be well within the 10 CFR 100 limits.
OPERATING EXPERIENCE/PREVIOUS EVENTS:
LER 1999-004-00 reported a failure to maintain closure of containment penetrations during fuel movement. A direct flow path had been created between the Containment Building atmosphere and the Auxiliary Building during fuel movement. This event was caused by a series of personnel errors in the implementation of the work control process.
LER 1996-005-00 reported opening of a containment isolation valve to allow draining of the B and C steam generators while core reload was underway. A dedicated non-licensed individual with the sole responsibility to close the valve upon direction from the Control Room was sufficient administrative controls. However, this was thought to be contrary to the T/S. LER 1996-005-00 was later retracted due to an evaluation that determined that a loop seal was adequate and Containment closure maintained.
LER 1996-003-00 reported a failure to maintain Containment closure due to four of eight bolts being loose on a blind flange installed on the Steam Generator "D" Main Steam Safety Valve. The corrective actions for this LER were directed toward instructions for installing blind flanges and would not have prevented this event.