ENS 46421
ENS Event | |
|---|---|
05:01 Nov 16, 2010 | |
| Title | Control Room Envelope Inoperable Due to Excessive Emergency Core Cooling System Relief Valve Leakage During Eccs Pump Surveillance Testing |
| Event Description | {{#Wiki_filter:The Licensee identified that Emergency Core Cooling System (ECCS) leakage exceeded the allowable limit as described in the Updated Final Safety Analysis Report (UFSAR). This is being reported as an Unanalyzed Condition in accordance with 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v)� Control of Rad Release.
The leakage from the Low Head Safety Injection discharge relief valve occurred during Low Head Safety Injection Pump surveillance testing. Efforts to resolve the lifting of the Low Head Safety Injection discharge relief valve are in progress. At 0001 [EST] on 11/16/10, Beaver Valley Power Station Unit 1 determined that leakage from the Low Head Safety Injection system in conjunction with a postulated Design Basis Accident (DBA) Loss Of Coolant Accident (LOCA) with transfer to Safety Injection Recirculation would result in dose exceeding the Dose Analysis for the Exclusion Area Boundary (EAB) and the Control Room. The projected dose would exceed the 10CFR50.67 EAB dose limit, and the 10CFR50 GDC 19 Control Room limit, assuming the leakage continued during the postulated DBA event. Beaver Valley Units 1 & 2 share a common Control Room Envelope, which has been declared inoperable as a result of this condition. Technical Specification Limiting Condition for Operation 3.7.10, Condition B, has been applied. The Senior NRC Resident has been informed of the condition [by the Licensee]. Notified R1DO (Harold Gray).
Actions have been completed to prevent leakage from the degraded Low Head Safety Injection System relief valve at BVPS Unit 1. Following successful completion of the post-maintenance test, the BVPS Unit 1 Low Safety Injection System was declared operable and applicable Technical Specification Actions at both BVPS Units were exited at 1545 hours on 11/16/1010. The Senior NRC Resident Inspector has been notified. Notified R1DO (Gray). }}[[Event description::Description::{{#Regex_clear:The Licensee identified that Emergency Core Cooling System (ECCS) leakage exceeded the allowable limit as described in the Updated Final Safety Analysis Report (UFSAR). This is being reported as an Unanalyzed Condition in accordance with 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v)� Control of Rad Release. The leakage from the Low Head Safety Injection discharge relief valve occurred during Low Head Safety Injection Pump surveillance testing. Efforts to resolve the lifting of the Low Head Safety Injection discharge relief valve are in progress. At 0001 [EST] on 11/16/10, Beaver Valley Power Station Unit 1 determined that leakage from the Low Head Safety Injection system in conjunction with a postulated Design Basis Accident (DBA) Loss Of Coolant Accident (LOCA) with transfer to Safety Injection Recirculation would result in dose exceeding the Dose Analysis for the Exclusion Area Boundary (EAB) and the Control Room. The projected dose would exceed the 10CFR50.67 EAB dose limit, and the 10CFR50 GDC 19 Control Room limit, assuming the leakage continued during the postulated DBA event. Beaver Valley Units 1 & 2 share a common Control Room Envelope, which has been declared inoperable as a result of this condition. Technical Specification Limiting Condition for Operation 3.7.10, Condition B, has been applied. The Senior NRC Resident has been informed of the condition [by the Licensee]. Notified R1DO (Harold Gray).
Actions have been completed to prevent leakage from the degraded Low Head Safety Injection System relief valve at BVPS Unit 1. Following successful completion of the post-maintenance test, the BVPS Unit 1 Low Safety Injection System was declared operable and applicable Technical Specification Actions at both BVPS Units were exited at 1545 hours on 11/16/1010. The Senior NRC Resident Inspector has been notified. Notified R1DO (Gray). }}| ]] |
| Where | |
|---|---|
Beaver Valley  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| LER: | 05000334/LER-2010-003 |
| Time - Person (Reporting Time:+0.78 h0.0325 days <br />0.00464 weeks <br />0.00107 months <br />) | |
| Opened: | Michael Kogelschatz 05:48 Nov 16, 2010 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Nov 17, 2010 |
| 46421 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |