05000333/LER-2008-002, Regarding Reactor Pressure Vessel Recirculation Inlet Nozzle Axial Flaw Indication Discovered During Refueling Outage Consistent with Inter-Granular Stress Corrosion Cracking
| ML083300360 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/20/2008 |
| From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-08-0123 LER 08-002-00 | |
| Download: ML083300360 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 3332008002R00 - NRC Website | |
text
-Entierg Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich Site Vice President - JAF November 20, 2008 JAFP-08-0123 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-333 License No. DPR-59 LICENSEE EVENT REPORT: LER-2008-002-00 Reactor Pressure Vessel Recirculation Inlet Nozzle Axial Flaw Indication, Discovered During Refueling Outage, Consistent With Inter-Granular Stress Corrosion Cracking Dear Sir or Madam' This~report-is sub'mittedinaccordance vwith7 1,:0 CFR 50.73(a)(2)(ii)(A), "Any event or condition that-resulted in the condition of the nuclear power. pant,.including its principal safety barriers; being seriously degraded".
There are no commitments contained in this report.
Questions concerning this report may be addressed to Mr. Gene Dorman, Acting Licensing Manager, at (315) 349-6810.
Pete Dietrich Site Vice President PD:jm Enclosure cc:
USNRC, Region 1 USNRC, Project Directorate USNRC Resident Inspector INPO :Records Center
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 James A. FitzPatrick Nuclear Power Plant 05000 333 1
OF 5
- 4. TITLE Reactor Pressure Vessel Recirculation Inlet Nozzle Axial Flaw Indication discovered during Refueling Outage Consistent with Inter-Granular Stress Corrosion Cracking
- 5. EVENT DATE
- 6. LER NUMBER 1
- 7. REPORT DATE I
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR NUMBER DOCKET NUMBER 05000 09 23 2008 2008 002 00 DOCKET NUMBER 05000
- 9. OPERATING MODE 5
- 10. POWER LEVEL 000
- 11. THIS REPORT Li 20.2201(b)
[
20.2201(d)
Li 20.2203(a)(1)
L] 20.2203(a)(2)(i)
E] 20.2203(a)(2)(ii)
Li 20.22'03(a)(2)(iii)
[
20.2203(a)(2)(iv) r,. 20.22"03(a)(2)(v)
.-'L] 20.2203(a)(2)(vi)
IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1 )(i)(A) 50.36(c)(1 )(ii)(A) 50.36(c)(2).
50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B)
El R]
El E]
E]
E]
50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii).
50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C).
50.73(a)(2)(v)(D)
F] 50.73(a)(2)(vii)
Li 50.73(a)(2)(viii)(A)
LI 50.73(a)(2)(viii)(B)
LI 50.73(a)(2)(ix)(A)
.50.73(a)(2)(x)
Li 73'71(a)(4)
Li 73.71(a)(5)
.] OTHER Specify in Ab'stract below or in (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 (If more space is required, use additional copies of NRC Form 366A)
SIMILAR EVENTS
There are no known similar events which have occurred at the JAF site.
REFERENCES JAF Condition Report CR-JAF-2008-0331 1, Axial flaw indication on Reactor Vessel Nozzle Results in Degraded Condition.
Entergy Letter to NRC, JAFP-08-0099, "James A. FitzPatrick Request for Relief (RR-7) - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs", dated September 26, 2008 Entergy Letter to NRC, JAFP-08-0102, "James A. FitzPatrick Request for Relief (RR-7 Revision 1) - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs", dated October 1, 2008
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