05000219/LER-2002-002, Local Leak Rate Test Results in Excess of Technical Specification Limits
| ML023520063 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/04/2002 |
| From: | Degregorio R AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-02-20334 LER 02-002-00 | |
| Download: ML023520063 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) |
| 2192002002R00 - NRC Website | |
text
AmerGen SM AmerGen Energy Company, LLC An Exelon/British Energy Company Oyster Creek US Route 9 South PO Box 388 Forked River, NJ 08731-0388 10 CFR 50.73(a)(2)(i)
December 4, 2002 2130-02-20334 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report 02-002 Local Leak Rate Test Results in Excess of Technical Specification Limits Enclosed is Licensee Event Report LER 02-002. This event did not affect the health and safety of the public.
If any additional information or assistance is required, please contact Mr. John Rogers of my staff at 609.971.4893.
Very truly yours, Ron J. DeGregorio Vice President, Oyster Creek RJD/JJR cc:
Administrator, Region I NRC Project Manager Senior Resident Inspector
NRC FORM 366 US. NUCLEAR REGULATORY COMMISSION (4-95)
APPROVED BY OMB NO. 3150-0104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLECrION REQUEST 50 0 0HRS REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY FORWARD COMMENTS REGARDING BURDEN ESTIMAFE TO THE NORMATION AND RECORDS MANAGEMENT BRANCH (T-6 P33), U S NUCLEAR LICENSEE EVENT REPORT (LER)
REGULATORY COMRMISSION WASHINGTON. DC 20555-0001.
AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), omCE or MANAGEMENT AND BUDGET. WASHINGTON, DC 20503.
lFACILITY NAME (I)
DOCKET NUMBER (2)
PAGE (3)
Oyster Creek Unit 1 05000 - 219 1 of 3 [lITE Local Leak Rate Test Results in Excess of Technical Specification Limits EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR I SEQUENTIAL I
REV MONTH DAY YEAR I-ACILIFY NAME I)CICKET NUMBER NUMBER 05000 10 1 1 02 02 02
-- oo
,ACILILYNAME J EINUMBER I
05000 OPERA TING N
TIUS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMfENTS OF 10 CFR 8: (Check one or more) (11)
MODE_(9) 20.2201(b) 20.2203(a)(2Xv)
X 50.73(aX2)(i) 50.73(a)(2Xviii)
E POWER O
20.2203(aXI) 20.2203(a)(3Xi) 50.73(aX2)(ll) 50 73(a)(2Xx)
LEVEL (10) l 20 2203(aX2Xi) 20.2203(a)(3Xii) 50.73(aX2)(ini) 173.7 20 2203(aX2Xii) 20.2203(a)(4) 50.73(aX2)(iv) l OTHER 20 2203(aX2)(iii) 50 36(cXI) 50.73(aX2)(v) 1 120 2203(aX2)(iv) 50 36(cX2) l 50.73(aX2)(vii) r_
LICENSEE CONTACT FOR THIS LER (12) lNAME TLLEPHONE NUMBER (Inchde Axea Code)
John Rogers 609.971.4893 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE i tz,`1
CAUSE
SYSTEM I COMPONENT I MANUFACTURER
I EXPECTED I MONTH DAY YEA lYES lXlNO SUBMISSION l(Iffyes, complete EXPECTED SUBMISSION DATE)
DATE (15)
ABSTRACT (Linmu to 1400 spaces, I e, approximately 15 single-spaced typewntten lines) (16)
On October 11, 2002, Local Leak Rate Test results indicated that Main Steam Isolation Valve V-1-0007 exceeded the Technical Specification leak rate limit of.05(.75)La at 35 psig (equivalent to 15.98 SCFH). The leak was unable to be quantified and was greater than 50 SCFH at 35 psig.
The cause of this occurrence was attributed to component degradation.
The safety significance of this occurrence is considered minimal as the total penetration leakage would have been limited by Main Steam Isolation Valve V-1-0009 in the same header. The leakage past V-1-009 was quantified at 2.214 SCFH.
V-1-0007 was refurbished and successfully leak rate tested prior to restart from the 1R19 Refueling Outage.
NRC FORM 366 (4-95)(4-95)
US. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
Oyster Creek, Unit 1 TEXT (If mnore space is required, use additional copies of NRC Formn 366A) (17)
DATE OF DISCOVERY The condition being reported was discovered on October 11, 2002.
IDENTIFICATION OF OCCURRENCE Main Steam Isolation Valve(MSIV) V-1-0007 (EHC SB-ISB) exceeded the leak rate criteria specified in Technical Specification 4.5.D.2. This condition is considered to be reportable in accordance withl0 CFR 50.73(a)(2)(i).
CONDITIONS PRIOR TO DISCOVERY The plant was in a COLD SHUTDOWN condition for refueling outage IRI9 when this condition was discovered.
DESCRIPTION OF OCCURRENCE On October 11, 2002, Local Leak Rate Testing (LLRT) results indicated that Main Steam Line Isolation Valve V-1-0007 exceeded the Technical Specification limit of.05(.75)La at 35 psig (equivalent to 15.98 SCFH). The leak could not be quantified, but was in excess of 50 SCFH at 35 psig.
APPARENT CAUSE OF OCCURRENCE The apparent cause of this occurrence was component degradation. This MS1V had previously exceeded Technical Specification limits during the 14R refueling outage, but had successfully passed LLRT in 15R, 16R, 17R and 18R.
tUS. NUCLEAR REGULATORY COMDMSSION (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET (2)
.ER NUMBER (6)
PAGE (3) l05000 YEAR l SEQUENTIAL l REV Oyster Creek, Unit 1
- - 219 02 02 00 3
of 3
TEXT (If more space is required, use additonal copies of NRC Form 366A) (17)
ANALYSIS OF OCCURRENCE AND SAFETY SIGNIFICANCE The MSIVs are containment isolation valves designed to minimize the coolant loss from the vessel, and the resultant offsite dose, in the event of a main steamline break accident. The design basis loss of coolant accident was evaluated for the primary containment maximum allowable accident leak rate of 1.0% per day at an initial pressure of 35 psig, which decays to 1.0 psig after 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
The 1.0 psig is assumed to remain for the next 21.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The calculated leakage provides adequate margin between projected potential offsite dose and 10 CFR 100 guidelines. This projected dose was not exceeded.
The analysis for the contribution of MSIV leakage to control room habitability was reviewed. The MSIV contribution is approximately 25% (243 SCF) of the total radioactive leakage assumed (1000 SCF). The minor increase in leakage rate from the V-1-007 penetration is well bounded by the existing total radioactive leakage and, therefore, has no impact on control room habitability.
The safety significance of this event is considered minimal. The leakage past the MSIV would have been limited by the leak rate of the other MSIV in the same header which met the leak rate acceptance criteria of Technical Specification 4.5.D.2.
CORRECTIVE ACTIONS
The MSIV components were repaired and retested with satisfactory results prior to restart from the IR19 outage.
SIMILAR EVENTS
LER 00-0010; Local Leak Rate Test Results in Excess of Technical Specification Limits Oyster Creek Licensing Correspondence Distribution Sheet File No.
Reference/Letter No.
02082 2130-02-20334 Letter Date Date Sent / Received 12104/2002 12/0612002 Title Description: LER 2002-002; Test Results in Excess of Tech Spec Limits LICENSING ENGINEER: John Rogers SPECIAL NOTES: Distributed without attachment except as noted.
Office of the President R. J. DeGregorio (Letter Only)
R. Maldondo Communications Engineerin2 V.Aggarwal M. Newcomer A. Agarwal D. Barnes T. E. Quintenz M. Button F. Buckley T. Powell R. Larzo C. Lefler AmerGen/Exelon C. Pardee G. Vanderheyden M. Gallagher (Outgoing Only)
J. Hufnagel (Outgoing Only)
D. Walker KS Document Ctr w/ attachment I Toncic D Distel Jeff Benjamin OCAB2 OCAB2 OCAB2 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 OCAB3 KSA 3-N KSA 3-N KSA 3-E KSA 3-E KSA 3-E KSA 1-N KSB 3-W KSA 3-E Cantera xx x
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Oyster Creek E. Harkness C Wilson J Freeman J. Vacaro S Bailey J..Bobba A. Krukowski R. Ewart G. True D. Norton W. Collier D. McMillan J. Magee M. Massaro R Adams M. Moore MOB MOB MOB MOB AOB AOB NMB OCAB2 Whse 2 Whse 1 AOB Aux Bldg 12 NMB OCAB2 OCAB2 AOB xxx x
Other NSRB (22 copies)
B Mussel R Milos X
OCAB3 X
OCAB2 X
External Distribution NJBNE - K. Tosch INPO ANI - R. Oliveira BPU - R. Chilton T. Gould GE - P. Ray x
File Index Number: 20.16.01.01 w/attachment Cross Reference Number: 20.16.01.01 w/attachment