05000368/LER-2005-001, Unit 2 Re Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of Pressurizer Heater Sleeves
| ML051310236 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/09/2005 |
| From: | James D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 05-001-00 | |
| Download: ML051310236 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3682005001R00 - NRC Website | |
text
~-EntaVg Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802 Tel 501 858 5000 2CAN050502 May 9, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 50-368/2005-001-00 Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
In accordance with 10CFR50.73(a)(2)(ii)(A), enclosed is the subject report concerning reactor coolant system pressure boundary leakage.
There are no new commitments contained in this submittal.
Sincerely, r Dale E. James Manager, Licensing DEJ/dh enclosure
,--- 'I
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e, 2
' 2CAN050502 Page 2 cc:
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents@inpo.org
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may dioits/r~h~rnr1ers for slr~h htor.k) not conduct or sponsor, and a person is not required to respond to, the
- 3. PAGE Arkansas Nuclear One - Unit 2 05000 368 1 OF 5
- 4. TITLE Reactor Coolant System Pressure Boundary Leakage Due To Primary Water Stress Corrosion Cracking Of Pressurizer Heater Sleeves
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUN iALRE FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SENUENTAL MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 03 09 2005 2005 - 001 -
00 05 09 2005 05000
- 9. OPERATING MODE
- 11.
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 3 0 20.2201(d)
E 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viiX(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
Co 20.2203(a)(2)(i) 0 50.36(c)(1)(i (A) 0 50.73(a)(2)(iii)
[
50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
°°° E 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Indude Area Code)
Arkansas Nuclear One / Dee Hawkins 479-858-5589CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MAN U-REPORTABLE FACTURER j TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes. complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On March 9, 2005, following shutdown for a scheduled refueling outage, a visual inspection of the reactor coolant system pressurizer revealed indications of leakage below the insulation around three pressurizer heater sleeves. On March 12, 2005, with the insulation removed from the heater sleeves and bottom head of the pressurizer, a total of eight heater sleeves and one pressurizer heater penetration containing a plug were found to be leaking. Leakage was Identified by small amounts of boron discovered at the sleeve penetration interfaces. On March 15, 2005, with the pressurizer filled with water, one additional leaking pressurizer heater sleeve was identified by visual observation of moisture on the sleeve. Leakage was confirmed in nine pressurizer heater sleeves and one plugged penetration. The failure mechanism for the ten leaking pressurizer penetrations was primary water stress corrosion cracking of Alloy 600 material. Non-destructive examination of the penetrations confirmed the presence of axially oriented flaws. Inspection of the pressurizer base material surrounding each penetration indicated that no boric acid wastage had occurred. The leaking heater sleeves were repaired using NRC approved ASME Code-qualified mechanical nozzle seal assemblies. The leaking plugged penetration was replaced with an Alloy 690 sleeve and plug. The pressurizer will be replaced during the refueling outage scheduled for the fall of 2006.
IRC 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 (Ifmore space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) weld. In LER 50-368/87-003-01 (letter 2CAN088801 dated August 12,1988), ANO-2 reported leaking pressurizer heater sheaths. In LER 50-368/2000-001-00 (letter 2CAN080011 dated August 29, 2000), ANO-2 reported leaking pressurizer heater sleeves and an RCS resistance temperature detector nozzle. In LER 50-368/2002-001-00 (letter 2CAN060201 dated June 13, 2002), ANO-2 reported leaking pressurizer heater sleeves. Corrective actions for these conditions were not intended to prevent recurrence of PWSCC in Alloy 600 material that is subject to this failure mechanism.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].