05000387/LER-2002-008, Regarding Unauthorized Change in Mode
| ML040420124 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/02/2004 |
| From: | Richard Anderson Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5706 LER 02-008-00 | |
| Download: ML040420124 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3872002008R00 - NRC Website | |
text
R. L Anderson PPL Susquehanna, LLC Vice President - Nuclear Operations 769 Salem Boulevard I*..
Berwick, PA 18603 Tel. 570.542.3883 Fax 570.542-1504 I
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FEB 0 2 2004 is TM U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPI-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2002-008-00 LICENSE NO. NPF-14 PLA-5706 Docket No. 50-387 Attached is Licensee Event Report 50-387/2002-008-00. This event was determined reportable per 10 CFR 50.73(a)(2)(i)(B) in that during surveillance testing with the applicable Mode 3 Limiting Conditions for Operation (LCO's) not met, Unit 1 average reactor coolant temperature exceeded 200 degrees F. Technical Specification LCO 3.10.1 was entered because it was believed that hydrostatic testing was still in progress when in fact it was not. Applicability of the Mode 3 requirements was therefore not recognized when 200 degrees F was exceeded.
Technical Specification 3.0.4 allows for mode changes provided that the actions for inoperable equipment allow operation for an unlimited period of time in that mode.
Actions for systems (e.g., Primary Containment) that were applicable during Mode 3 operation did not allow operation for an unlimited period of time. As such, this entry into Mode 3 constituted a violation of Technical Specification LCO 3.0.4. There were no actual consequences to the health and safety of the public as a result of this event since the provisions of LCO 3.10.1 were implemented and are adequate to assure safety during the subject testing while above 200 degrees F.
No new regulatory commitments have been created through issuance of this report.
Richard L. Anderson Vice President - Nuclear Operations Attachment Document Control Desk PLA-5706 cc: Mr. H. J. Miller Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. L. Hansell Sr. Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35 Berwick, PA 18603-0035 Mr. R. Osborne Allegheny Electric Cooperative P. 0. Box 1266 Harrisburg, PA 17108-1266 Mr. R. R. Janati Bureau of Radiation Protection Rachel Carson State Office Building P. 0. Box 8469 Harrisburg, PA 17105-8469
Abstract
At 01:45 on April 2, 2002 with Unit 1 in Mode 4 at 0% power and scram time testing in progress following the completion of the ASME Class 1 hydrostatic test, reactor coolant temperature exceeded 200 degrees F.
With reactor coolant temperature greater than 200 degrees F (202 degrees F was reached), the temperature requirements for Mode 4 were no longer met and Mode 3 requirements became applicable.
The cause has been determined to be a lack of adequate procedure steps that assure recognition as to when the hydrostatic test portion of the test evolution is completed. Once Technical Specification LCO 3.10.1 was entered at 01:45, actions to depressurize and lower the reactor temperature below 200 degrees F were taken. The coolant temperature was reported to be 195 degrees F at 03:12 on April 2, 2002. The following corrective actions have been completed: 1) Surveillance Procedures SE-100(200)-002 have been clarified to define the end of the hydro test; and 2) Surveillance Procedures SE-100(200)-002 have been clarified to state that Technical Specification 3.10.1 only applies to the operational hydrostatic test. Technical Specification 3.0.4 allows for mode changes provided that the actions for inoperable equipment allow operation for an unlimited period of time in that mode. Actions for systems (e.g., Primary Containment) that were applicable during Mode 3 operation did not allow operation for an unlimited period of time. As such, this entry into Mode 3 constituted a violation of Technical Specification 3.0.4. Thus this event is reportable as a condition prohibited by the Technical Specifications in accordance with 10 CFR 50.73(a)(2)(i)(B). The increase in reactor coolant temperature to 202 degrees F did not have any actual consequences to the health and safety of the public.
NRC FORM 366 (7 2001)
(f 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)
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