05000461/LER-2007-002, Regarding Improper Installation of Stanchions in Containment Pool Swell Zone
| ML071410186 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/10/2007 |
| From: | Bryan Hanson AmerGen Energy Co |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| U-603817 LER 07-002-00 | |
| Download: ML071410186 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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) 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)(v), Loss of Safety Function |
| 4612007002R00 - NRC Website | |
text
AmerGen An Exelon Company Clinton Power Station R. R. 3, Box 228 Clinton, IL 61727 1 OCFR50.73 U-603817 May 10, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating Ucense No. NPF-62 NRC Docket No. 50-461
Subject:
Licensee Event Report 2007-002-00 Enclosed Is Licensee Event Report (LER) No. 2007-002-00: Improper Installation of Stanchions in Containment Pool Swell Zone. This report is being submitted in accordance with the requirements of 10CFR50.73.
This letter contains no regulatory commitments.
Should you have any questions concerning this report, please contact Mr. Kent Scott, Regulatory Assurance Manager, at (217) 937-2800.
Respectf ully, Bryan Hanson Site Vice President Clinton Power Station JLP/blf
Enclosure:
License Event Report 2007-002-00 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - IEMA Division of Nuclear Safety
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may d t aa l
not conduct or sponsor, and a person Is not required to respond to, the digits/characters for each blc)Ifmudn ftfn
- 3. PAGE Clinton Power Station 05000461 1 OF 3
- 4. TITLE Improper Installation of Stanchions in Containment Pool Swell Zone
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED ENIA REV ACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUEN MONTH DAY YEAR None
___NUMBER NO.
None 05000 I 0FACILITY NAME
.DOCKET NUMBER 03 15 2007 2007 - 002 05 10 2007 None 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO ThE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[o 20.2201(b)
[3 20.2203(a)(3)(I)
[3 50.73(a)(2)(i)(C)
[0 50.73(a)(2)(vii) 1 0 20.2201(d)
[3 20.2203(a)(3)(li)
[] 50.73(a)(2)(ii)(A)
[0 50.73(a)(2)(viii)(A) o3 20.2203(a)(1)
[0 20.2203(a)(4)
[0 50.73(a)(2)(ii)(B)
[0 50.73(a)(2)(vlii)(B) 1[3 20.2203(a)(2)(I) 03 50.36(c)(1)(l)(A)
[0 50.73(a)(2)(iii) 03 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii)
[0 50.36(c)(1)(ii)(A) 03 50.73(a)(2)(iv)(A) 03 50.73(a)(2)(x) o 20.2203(a)(2)(11i)
[0 50.36(c)(2)
[0 50.73(a)(2)(v)(A)
[0 73.71(a)(4) o 20.2203(a)(2)(Iv)
[0 50.46(a)(3)(ii)
[0 50.73(a)(2)(v)(B)
[0 73.71(a)(5) 96 [3 20.2203(a)(2)(v)
[0 50.73(a)(2)(I)(A) 03 50.73(a)(2)(v)(C) 0 OTHER (10 CFR 21) o1 20.2203(a)(2)(vI)
[0 50.73(a)(2)(l)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below
_r In NRC Form RRRA
- 12. LICENSEE CONTACT FOR THIS LER NAME ITELEPHONE NUMBER (Include Area Code)
Glen Vickers, Radiation Protection Manager 1(217) 937-2700CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE a Y ~
FACTURER TO EPIX fCMI FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION
[
YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
C9 NO DATE ABSTRACT (Limit to 1400 spaces, Le., approximately 15 single-spaced typewritten lines)
On March 15, 2007, it was observed that four stanchions, used to post a radiologically contaminated area in the containment building, were improperly installed. The stanchions, used for holding a nylon rope boundary around the contamination zone, were not secured to the grating in accordance with procedure requirements. Plastic tie wraps were used to hold the stanchions in place rather than grating clips with hold-down bolts. An engineering analysis determined that the stanchions were within the suppression pool swell zone subject to hydrodynamic loads following a loss of coolant accident (LOCA), and had the potential to become dislodged and damage plant equipment. The analysis determined that a stanchion striking a nearby containment isolation valve during a concurrent LOCA and Loss of Offsite Power (LOOP) event could affect containment isolation capability. Since it was determined that these stanchions had been installed during periods of diesel generator inoperability, the containment isolation function could have been affected. The root cause determined that radiation protection technicians had a knowledge gap on the requirements of the procedure used for stanchion placement in containment. This event will be emphasized in initial and continuing training for radiation protection technicians.
NRC FORM 368(8-2004)
PRINTED ON RECYCLED PAPER NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER (If more space Is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
CAUSE OF EVENT
The root cause was determined to be that RP Technicians had a knowledge gap on the requirements of CPS 1019.05 used for stanchion placement in containment pool swell zones.
CORRECTIVE ACTION
Corrective Actions include adding training on CPS 1019.05 with specific emphasis on the issues identified in this event to the site initial and site continuing RP Technician training program. All current RP department personnel, other than clerical personnel, will complete this training.
PREVIOUS SIMILAR EVENTS
None.
COMPONENT FAILURE DATA
None.
~4HL~ ILJtIM ~OOA ~1.~UJ1J NHC FORIM 366 (1-20UD1)