05000271/LER-2008-001, For Vermont Yankee Regarding Crane Travel Limit Stops Not Installed as Required by Technical Specifications Due to an Inadequate Procedure
| ML082200278 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/31/2008 |
| From: | Ted Sullivan Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 08-045 LER 08-001-00 | |
| Download: ML082200278 (5) | |
| 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 |
| 2712008001R00 - NRC Website | |
text
En tergy Entergy Nuclear Operations, Inc.
Vermont Yankee P-O Box 0250 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 July 31, 2008 BVY 08-045 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Reportable Occurrence Number: LER 2008-001-00
Dear Sir or Madam,
As defined by 10 CFR 50.73(a)(2)(i)(B), we are submitting the attached revised Licensee Event Report, LER 2008-001-00, for a Reportable Occurrence that was discovered on June 10, 2008.
There are no regulatory commitments contained within this correspondence.
If there are any questions regarding this letter please contact Mr. David Mannai at (802) 451-3304.
Sincerely,
.,rmt A.
N Site Vide Pr=esidýent Vermont Yankee Nuclear Power Station cc: (next page) 11-ýýo
'- op'p-
BVY 08-045 / page 2 of 2 cc:
Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB:
NO. 3150-0104 EXPIRES 08/31/2010 (9-2007)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Vermont Yankee Nuclear Power Station 05000-271 1 of 3
- 4. TITLE Crane Travel Limit Stops not Installed as Required by Technical Specifications due to an Inadequate Procedure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED M SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY IYEAR None DCENME FACILITY NAME DOCKET NUMBER 06 10 2008 2008 001 00 07 31 2008 None
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
N El 20.2201(d)
El 20.2203(a)(3)(ii)
[] 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
E] 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
E] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 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)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4) 100%
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
E] 50.73(a)(2)(v)(B)
H 73.71 (a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
U OTHER Specify in Abstract below El 20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D) or in (If more space is required, use additional copies of NRC Form (366A)
DESCRIPTION
On 06/10/08, with the reactor at 100 percent power, Vermont Yankee (VY) identified that the reactor building crane (EIIS=DF) travel limit mechanical stops were not installed in accordance with Technical Specification (TS) 4.12.G.2 "Crane Travel". TS 4.12.G.2 requires "Crane travel limit mechanical stops shall be installed on the crane trolley rails prior to cask handling operations to prohibit cask travel over irradiated fuel assemblies."
VY was performing dry fuel storage (DFS) activities and had just removed a loaded cask from the spent fuel pool. The cask was suspended over the refuel floor adjacent to the spent fuel pool. Once the cask is removed from the pool there is a need to rearrange the crane travel limit mechanical stops to.provide a means to prohibit movement of the cask over irradiated fuel. To prepare for this the refuel crane was de-energized and the stops were rearranged. The procedure provided the sequence that the stops were to be installed and removed to comply with the station Technical Specifications but provided allowance for performing steps out of sequence as allowed by the DFS supervisor. The DFS Supervisor decided that the order that the stops were installed was not significant since the crane was de-energized.
VY subsequently determined that the sequence that the crane travel limit mechanical stops were removed and reinstalled did not comply with the requirements of the TS in that there was a time, with the cask suspended, where the crane travel limit mechanical stops were not installed to prohibit travel over the fuel. It was determined that having the crane de-energized did not satisfy the TS requirement to have mechanical travel limit stops installed.
This event is reportable as a Licensee Event Report per 10CFR50.73(a)(2)(i)(B) as a condition that is prohibited by TS.
CAUSE
Root Cause:
The cause was determined to be a lack of sufficient detail in the procedure controlling the activity. The procedure did not provide adequate emphasis that the specific steps be performed in the required sequence to ensure compliance with the station Technical Specifications.
(If more space is required, use additional copies of NRC Form (366A)
ASSESSMENT OF SAFETY CONSEQUENCES
The intent of the Technical Specifications, related to handling spent fuel casks, is to provide a means to prohibit movement of a spent fuel cask over spent fuel assemblies stored in the fuel pool. During the time the crane travel limit mechanical stops were being rearranged, the reactor building crane was de-energized. The crane was suspended adjacent to the fuel pool over an area that was evaluated to handle the weight of the loaded cask. VY personnel were in the area monitoring the evolution and in contact with the crane operator. There was no movement or intended movement of the cask during the period of time the stops were being re-arranged. At all times while the stops were being relocated the crane was de-energized and administrative barriers were in place to prohibit cask movement over the irradiated fuel assemblies. Consequently, the event did not have an adverse impact on the health and safety of the public.
CORRECTIVE ACTIONS
J Immediate Actions
- 1) Ensured that current DFS qualified personnel were trained on what constitutes "cask handling operations" and how to comply with TS 4.12.G.2 requirements.
- 2) Ensured that all TS related steps in dry fuel storage procedures will be performed in the sequence written.
- 3) As an interim action, the specific controlling procedure was revised to require steps to be performed out of sequence to require the approval of the DFS Project Manager and to require TS required steps to be performed in the order specified.
Long Term Corrective Actions
- 4) Ensure that future DFS training includes a discussion of this operating experience and address the impact of following the subject steps to ensure compliance with the TS.
- 5) Revise DFS procedures to eliminate the ability to perform any step out of sequence.
Specific steps may still be allowed to be performed out of sequence however will need to be specifically identified.
ADDITIONAL INFORMATION
No similar events have occurred at VY within the past five years.