05000278/LER-2006-001, Regarding Technical Specification Non-Compliance Due to Inoperable Primary Containment Isolation Valve
| ML061450306 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/23/2006 |
| From: | Grimes J Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-001-00 | |
| Download: ML061450306 (5) | |
| 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) 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)(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 |
| 2782006001R00 - NRC Website | |
text
Exel n5M Exelon Nuclear Telephone 717.456.7014 Nuclear Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road Delta, PA 17314-9032 10CFR 50.73 May 23, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station (PBAPS) Unit 3 Facility Operating License No. DPR-56 NRC Docket No. 50-278
Subject:
Licensee Event Report (LER) 3-06-01 This LER reports a condition prohibited by Technical Specifications involving an inoperability of a Primary Containment Isolation Valve associated with the High Pressure Coolant Injection System.
In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that are planned to restore and maintain compliance are discussed in the LER.
If you have any questions or require additional information, please do not hesitate to contact us.
Sincerely, Josph P. Grimes Plant Manager Peach Bottom Atomic Power Station JPG/djf/IR 475597 Attachment cc:
PSE&G, Financial Controls and Co-owner Affairs R. R. Janati, Commonwealth of Pennsylvania INPO Records Center S. Collins, US NRC, Administrator, Region I R. I. McLean, State of Maryland US NRC, Senior Resident Inspector CCN 06-14032
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the Information digits/characters for each block)
Collection.
- 3. PAGE Peach Bottom Atomic Power Station Unit 3 05000 278 1 OF 4
- 4. TITLE Technical Specification Non-Compliance due to Inoperable Primary Containment Isolation Valve
- 5. EVENT DATE
- 6. LER NUMBER l
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH TDAY lYEARq YEAR lSNQUMEBNETR
- lNO, MONTH I DAY YEA 0FC~
AEn 5o000 FACILITY NAME DOCKET NUMBER 4
6 2006 06 01 -
0 5
23 2006 05000
- 9. OPERATING MOE
- 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) a 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(iI)(A) 0 50.73(a)(2)(viii)(A) 0 20.2203(a)(1) 0 20.2203(a)(4)
D 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(1) 0 50.36(c)(1)(i)(A) 3 50.73(a)(2)(i) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 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)
E 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4)
O 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii)
E3 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 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 or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
Corrective Actions
Foreign material was removed from the internals of the AO-137 PCIV and associated test taps. The valves were repaired and appropriate valve leak-tightness was verified as part of an as-left local leak rate test.
A foreign material inspection was performed within the attached piping to the AO-137 valve. No additional foreign material was identified.
Additional corrective actions including extent of condition evaluations are being evaluated in accordance with the Corrective Action Program. Pending further piping inspections for foreign material, proper stroke operation of the AO-137 valve is being performed after each HPCI system operation.
Previous Similar Occurrences There was one previous LER identified concerning a condition prohibited by Technical Specifications involving an inoperable Primary Containment Isolation Valve. On 11/19/04, LER 2-04-02 reported a Unit 2 condition where foreign material was found in the AO-137 valve on the HPCI system. Corrective actions associated with LER 2-04-02 involved removal of foreign material and extent of condition examinations for Unit 2.
Foreign material searches performed during the last Unit 3 Refueling Outage (P3R15) did not detect the foreign material that migrated into the PCIVs discussed in this report.