05000277/LER-2006-002, Re Automatic Depressurization System Safety Relief Valve Deficiencies
| ML063260046 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/15/2006 |
| From: | Grimes J Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CCN 06-14086 LER 06-002-00 | |
| Download: ML063260046 (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)(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 |
| 2772006002R00 - NRC Website | |
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Exelon Nuclear Telephone 717.4S6.7014 Nuclear Peach Bottom Atomic Power Station www.exeloncorp.com 1848 Lay Road Delta, PA 17314-9032 10CFR 50.73 November 15, 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-44 NRC Docket No. 50-277
Subject:
Licensee Event Report (LER) 2-06-02 This LER reports a condition involving Automatic Depressurization Valve deficiencies that was discovered during a recent Refueling Outage. 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, Jos h P. Grimes Plant Manager Peach Bottom Atomic Power Station JPG/djf/I R 539277/538660/537127 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 06-14086
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 2 05000 277 1 OF 5
- 4. TITLE Automatic Depressurization System Safety Relief Valve Deficiencies
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET0NUMBER NUMBER NO.
05000 I
FACILITY NAME DOCKET NUMBER 09 28 2006 06 02 0
11 15 2006 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
[E 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 5 20.2201(d)
[I 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[I 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
__ 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL I] 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 0 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 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 (If more space is required, use additional copies of NRC Form 366A) (17)
Corrective Actions, continued In accordance with preventive maintenance program, a refurbished SRV was installed in the 71 C SRV location to replace the SIN 83 SRV. Further corrective actions in addition to those involving events reported previously (LER 2-03-04, LER 3-05-04) will be evaluated in accordance with the Corrective Action Program.
Previous Similar Occurrences There was one previous LER identified involving the failure of an SRV to re-close following automatic operation. LER 2-03-04 identified an event on Unit 3 that involved a failure of SRV S/N 18 to re-close in September 2003. A laboratory failure analysis determined that tightly adhered foreign material on the pilot valve disc may have prevented the first stage pilot valve disc from properly re-closing. LER 2-03-04 also identified a condition involving a failure of a Unit 3 SRV to manually open as a result of a degraded actuator diaphragm. Corrective actions identified through the Corrective Action Program as a result of LER 2-03-04 included the improved decontamination, cleaning, refurbishment and examination processes. LER 3-05-04 also identified a condition discovered during laboratory testing in September 2005 where SRV S/N 193 failed to re-close after testing. The cause of the failure to re-close was due to vendor human performance issues during SRV maintenance. Because SRV S/N 83 was installed in the 71 C SRV location in September 2002, previous corrective actions would not be expected to have prevented the SRV S/N 83 failure to re-close concern.