05000249/LER-2007-001, Regarding High Pressure Coolant Injection System Declared Inoperable
| ML071280263 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/01/2007 |
| From: | Bost D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| SVPLTR # 07-0024 LER 07-001-00 | |
| Download: ML071280263 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i)(B), Prohibited by Technical Specifications |
| 2492007001R00 - NRC Website | |
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Exelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station Nucear 6500 North Dresden Road Morris, IL 60450-9765 10 CFR 50.73 SVPLTR # 07-0024 May 1,2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Licensee Event Report 249/2007-001 -00, "Unit 3 High Pressure Coolant Injection System Declared Inoperable" Enclosed is Licensee Event Report 249/2007-001-00, "Unit 3 High Pressure Coolant Injection System Declared Inoperable," for Dresden Nuclear Power Station, Unit 3. This event is being reported in accordance with 10 CFR 50.73(a)(2)(v)(D), "Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident."
Should you have any questions concerning this report, please contact Mr. James Ellis, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, Danny G ost Site Vi President Dresden Nuclear Power Station Enclosure cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
ý6-200)4)
, the NRC may dig its/characters for each block)inot conduct or sponsor, and a person is not required to respond to, the digis/carater foreac blck)infnrm~tinn conllecrtion.
- 3. PAGE Dresden Nuclear Power Station, Unit 3 05000249 1 OF 3
- 4. TITLE Unit 3 High Pressure Coolant Injection System Declared Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR ISEOUENTIAL REV FACILITY NAME DOCKET NUMBER YEAR NUMBER NO.
MONTH DAY YEAR N/A N/A I
t IFACILITY NAME DOCKET NUMBER 03 02 2007 2007 001 00 05 01 2007 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
[I 20.2203(a)(3)(i) 0i 50.73(a)(2)(i)(C)
L-50.73(a)(2)(vii) 1l 20.2201(d) 0i 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)
EL 50.73(a)(2)(ii)(B)
EL 50.73(a)(2)(viii)(B)
_L 20.2203(a)(2)(i)
[I 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)
[3 20.2203(a)(2)(iii)
El 50.36(c)(2)
EL 50.73(a)(2)(v)(A)
EL 73.71 (a)(4) 1L 20.2203(a)(2)(iv)
EL 50.46(a)(3)(ii)
EL 50.73(a)(2)(v)(B)
EL 73.71(a)(5) 100 EL 20.2203(a)(2)(v)
[L 50.73(a)(2)(i)(A)
EL 50.73(a)(2)(v)(C)
E] OTHER [L
20.2203(a)(2)(vi)
EL 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of NRC Form 366A) (17) closure documentation that did not clearly document that not all of the original work scope was completed. As a result, several sections of Unit 2 and 3 HPCI System piping susceptible to FAC that were not replaced were incorrectly removed from the FAC Inspection Program.
D.
Safety Analysis
The safety significance of the event is minimal. TS 3.5.1 allows Unit 3 to remain at power for 14 days with an inoperable HPCI if the Isolation Condenser System (IC) is operable. Unit 3 was in compliance with TS 3.5.1 during this event as the IC was operable and HPCI was inoperable for approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. Therefore, the consequences of this event had minimal impact on the health and safety of the public and reactor safety.
E.
Corrective Actions
Unit 3 HPCI System Inlet Drain Pot drain piping with the pinhole leak was replaced.
Unit 2 and 3 HPCI System carbon steel piping susceptible to FAC has been identified, evaluated for acceptance of the degraded condition until replacement and scheduled for replacement in future outages.
The Work Control process has been significantly enhanced since 1997 to ensure sufficient closeout documentation including the use of a computerized process (PASSPORT) for entering closeout documentation, implementation of procedure MA-AA-716-011, 'Work Execution and Closeout," and the use of First Line Supervisors to enter work documentation notes.
F.
Previous Occurrences
A review of DNPS Licensee Event Reports (LERs) for the last three years did not identified any LERs associated with piping that was found with a through wall leak and susceptible to FAC.
G.
Component Failure Data
NA