05000528/LER-2004-011, Re Missed Surveillance Requirements for Containment Lvs Test/Drain Valves
| ML050130150 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/06/2005 |
| From: | Danni Smith Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 192-01158-DMS/SAB/DJS LER 04-011-00 | |
| Download: ML050130150 (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) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 5282004011R00 - NRC Website | |
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sli/sidiar of Pinnae Memg Capital Corpoation 10 cFR 50.73 Palo Verde Nuclear Generating Station David M. Smith Tel.
623-393-6116 Mail Station 7602 Plant Manager Fax.
623-393-6077 P.O. Box 52034 Nuclear Production e-mail: DSMITH10@apsc.com Phoenix, AZ 85072-2034 192-01158-DMS/SAB/DJS January 6, 2005 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket No. STN 50-528, 50-529 and 50-530 License No. NPF-41, NPF-51 and NPF-74 Licensee Event Report 1-2004-011-00 Attached please find Licensee Event Report (LER) 50-528/2004-011-00 that has been prepared and submitted pursuant to the Palo Verde Operating Licenses (OLs). This LER reports a condition where APS did not adequately meet a Technical Specification Surveillance requirement.
In accordance with 10CFR50.4, a copy of this LER is being forwarded to the NRC Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact Daniel G. Marks, Section Leader, Regulatory Affairs, at (623) 393-6492.
Arizona Public Service Company makes no commitments in this letter. The corrective actions described in this LER are not necessary to maintain compliance with regulations.
Sincerely, DMS/SAB/DJS/kg Attachment cc:
B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager N. L. Salgado NRC Senior Resident Inspector for PVNGS
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
- 6-2004)
, the NRC may sfor each block) not conduct or sponsor, and a person Is not required to respond to, the digits/characters frecblk)information collection.
- 3. PAGE Palo Verde Nuclear Generating Station Unit I 05000 528 1 OF 5
- 4. TITLE Missed Surveillance Requirements for Containment lWs TestfDrain Valves
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACIUTY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR PVNGS Unit 2 05000 529 FACIUTY NAME DOCKET NUMBER 11 10 2004 2004 - 011 -
00 01 06 2005 PVNGS Unit 3 05000 530
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANTTOTHE REQUIREMENTS OF 10 CFR§: (Checkallthatapply)
O 20.2201(b) 0 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
E 50.73(a)(2)(vii) l 0
20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
E 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i)
El 50-36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
Dl 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii) 0l 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
El 20.2203(a)(2)(iv) a 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 0
20.2203(a)(2)(v)
E 50.73(a)(2)Q)(A)
Dl 50.73(a)(2)(v)(C)
E OTHER 0 20.2203(a)(2)(vi) 0D 50.73(a)(2)(i)(B)
El 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 (If more space Is required, use additional copies of NRC Form 366A)
- 6.
CAUSE OF THE EVENT
The direct cause of the event was an inadequate procedure. Due to human error, these containment penetration test and drain valves, from initial plant operations until November 2004, were not included in the surveillance test for Containment Isolation Valves.
No unusual characteristics of the work location (e.g., noise, heat, poor lighting) directly contributed to this event.
- 7.
CORRECTIVE ACTIONS
These eight ECCS injection containment penetration test and drain valves were added to Surveillance Test procedure 40ST-9ZZ13 (Containment Isolation Valves).
The surveillance test procedure was revised to include these test and drain valves and then successfully performed in Unit 1 and Unit 2 on November 11, 2004. Unit 3 successfully completed the ST prior to entering MODE 4 from its refueling outage.
Any additional corrective actions taken as a result of the investigation of this event, including an evaluation of the extent of condition will be implemented in accordance with the APS corrective action program. If information is subsequently developed that would significantly affect a reader's understanding or perception of this event, a supplement to this LER will be submitted.
- 8.
PREVIOUS SIMILAR EVENTS
Previous similar events were reported in LER 50-528/2001-005 and LER 50-528/2004-004.