05000387/LER-2007-002, Regarding ESSW Pump House Ventiliation Inoperable-Following Modification
| ML072400342 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/15/2007 |
| From: | Gannon C Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6256 LER 07-002-00 | |
| Download: ML072400342 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 |
| 3872007002R00 - NRC Website | |
text
C. J. Gannon Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3050 Fax 570.542-1504 cjgannon @ pplweb.com T M AUG 15 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPl-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2007-002-00 PLA-6256 Docket Nos. 50-387 and 50-388 Attached is Licensee Event Report 50-387/2007-002-00. This event became reportable as a condition prohibited by Technical Specifications per 10 CFR 50.73(a)(2)(i)(B) when it was determined that a single loop of RHR suppression pool cooling would not have remained operable under certain conditions following installation of a 2002 modification at the Engineered Safeguard Service Water (ESSW) Pump house.
There were no actual consequences to the health and safety of the public as a result of this event.
No new regulatory commitments have been created through issuance of this report.
- - Nuclear Operations Attachment cc:
Mr. R. V. Guzman, NRC Project Manager Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. R. Osborne, Allegheny Electric
", 4fý
NRC FORM 366 U.S. NUCLEAR REGULATORY 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 collection.
- 1. FACILITY NAME Susquehanna Steam Electric Station - Unit 1
- 2. DOCKET NUMBER
- 3. PAGE 05000387 1 OF4 4.'ITLE ESSW Pump house Ventilation Inoperable Following Modification
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV FACILITY NAME DOCKET NUMBER NUMBER NO.
MONTH DAY YEAR Susquehanna Unit 2 05000388 FACILITY NAME DOCKET NUMBER 06 20 2007 2007 002 00 08 15 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 El 20.2201(b)
El 20.2203(a)(3)(i)
[] 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
- 10. POWER LEVEL [E 20.2201(d)
El 20.2203(a)(3)(ii)
[] 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) 1E00%
[: 20.2203(a)(1)
[I 20.2203(a)(4)
[: 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[I 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 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)
E] 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
[] 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
[E OTHER Voluntary Report El 20.2203(a)(2)(vi) 0 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 additiona/ copies of (If more space is required, use additional copies of NRC Form 366A)
CORRECTIVE ACTIONS
Completed Actions:
" Two ESSW pump house dampers have been "gagged" in the open position to ensure circulation cooling in the event of a divisional HVAC failure.
Susquehanna's modification program now requires performance of a failure modes and effects analysis that will help identify potentially adverse consequences created through the implementation of complex modifications.
An impact evaluation process was incorporated into Susquehanna's modification program that strengthens the station's ability to recognize the impacts of engineering changes.
Susquehanna's corrective action program is significantly more robust than it was in the 1990's. Implementation weaknesses existing at that time have been corrected.
Planned Actions:
" A permanent corrective measure will be implemented to ensure that at least one loop of RHR suppression pool cooling remains operable on each Unit during a LOOP event concurrent with an additional random single failure.
The FSAR will be revised to address and recognize any design features or operator actions associated with the permanent resolution.
ADDITIONAL INFORMATION
Failed Components Information:
None Past Similar Events:
None