05000219/LER-2004-005, Regarding Main Steam Isolation Valve Failure to Close During Partial Valve Closure Surveillance Due to Mechanical Binding
| ML043220089 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/10/2004 |
| From: | Swenson C AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-04-20232 LER 04-005-00 | |
| Download: ML043220089 (6) | |
| 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)(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)(1) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2192004005R00 - NRC Website | |
text
AmerGenSM AmerGen Energy Company, LLC Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 www.exeloncorp.com An Exelon Company 10 CFR 50.73 November 10, 2004 2130-04-20232 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2004-005-00, Main Steam Isolation Valve Failed to Close During Partial Valve Closure Surveillance Due to Mechanical Binding Enclosed is Licensee Event Report 2004-005, Revision 0. This event did not affect the health and safety of the public or plant personnel. There was no safety system functional failure associated with this event.
If any further information or assistance is needed, please contact David Fawcett at 609-971-4284.
Sinceey I
C. N. Swenson Vice President, Oyster Creek Generating Station CNS/DIF : List of Regulatory Commitments cc:
S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 04112
ATTACHMENT 1 SUMMARY OF AMERGEN ENERGY CO. LLC COMMITMENTS The following table identifies commitments made in the document by AmerGen Energy Co. LLC (AmerGen). Any other actions discussed in this submittal represent intended or planned actions by AmerGen. They are described to the NRC for the NRC's information and are not regulatory commitments.
COMMITMENT
COMMITTED DATE OR "OUTAGE" Schedule and install the poppet backseat modification on all remaining MSIVs. (NSO3B was completed in 1998 (17R), NS04A was completed 11/30/2006 prior to restart from 1 F07, NS03A is scheduled for 1 R20, and NS04B is scheduled for 1 R21)
Fully develop the stem strain gauge testing technique for MSIV testing to monitor rib wear. Institutionalize the testing in the form of a preventive 03/30/2005 maintenance or surveillance test program
a0 r
A
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NRC FORM 366 (62004)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 06/30/2007
, the NRC may not conduct or sponsor. and a person Is not reouired to respond to. the information collection.
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
- 3. PAGE
__C_
__k,_
050 {t 1
OF500o
- 4. TITLE Main Ste Iso ation Valve Failed to Close Dunng Partia Valve Closure Surveillance Due to Mechanical Binding
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV.
D FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR 05000 09 11 2004 2004 005 FACILTY NAME DOCKET NUMBER
.'05000
- 9. OPERATING MODE 11.THIS REPORTIS SUBMrrIED PURSUANTTOTHE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201 (b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
N 20.2201 (d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(C)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(1)(A) 50.73(a)(2)(v)(C)
OTHER I =20.2203(a)(2)(vi)
/
50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
S_-Ify I Abstract below I__
I or In NRC Form 368A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER Rnoude Area Code)
David FacC'Lic6nsing En0giner
^
(9) 971-4284L YES (If yes. complete EXPECTED SUBMISSION DATE)
ABSTRACT (LhT to 40o spacs Be.,,pproxna*ey 15 sk5spacedtoewten ws) nS~aturday, Septemiber 11, 2004, with the plant in the Run Mode at 100%o power, the outboard Main Steam Isolation Valve (MSIV) NS04 failed the' 10% MSIV closure test. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS LCO was entered at:
0930. To verify operability of the valve, plant power was reduced to 40% power and the MSIV full closure test was performed at;1747. This test also'failed. At 1823 the inboard MSIV NSO3A was'isolated and i electronically locked in place due to the' NS04A being inoperable. With power maintained at approximately '
40%," a complex troubleshooting plan was perfomrmed that concluded the valve was stuck open due'to 'an internal problem. A plant shutdown was performed on September 14, 2004 to repair the MSIV.
Internal inspection of the valve determined the failure of the poppet to close was caused by excessive rib
- and poppet guide wear resulting from poppet vibration' induced by steam flow..1 All safetysystems were fully operable and the-safety significance of this event is considered minimal -
based on the demonstrated capability of the inboard MSIV NSO3A to fully close.:-
No other MSIV failures caused by rib wear were identified. LER 88-013, occurred on July'9, ;1988 when inboard MSIV (NS03A) failed the then quarterly full closure'test due to stem failure caused by poppet'..
vibration.
NRC FORM 366 (6-2004)
r.-
(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)
Additional Information
A. Failed Components:
Main Steam Isolation Valve (NS04A) was manufactured by Atwood and Morrill (A&M)
B. Previous similar events
No other MSIV failures caused by rib wear were identified. LER 88-013, MSIV (NS03A) stem failure caused by poppet vibration.
C. Identification of components referred to in this Licensee Event Report:
Components IEEE 805 System ID IEEE 803A Function MSIV SB ISV