05000311/LER-2007-001, Regarding Inoperability of the Chilled Water System - (21 and 22 Chillers Inoperable)
| ML071970041 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/29/2007 |
| From: | George Gellrich Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N07-0158 LER 07-001-00 | |
| Download: ML071970041 (6) | |
| 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 |
| 3112007001R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC JUN 2 9 2007 10CFR50.73 LR-N07-0158 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 LER 311/07-001 Salem Nuclear Generating Station Unit 2 Facility Operating License'No. DPR-75 NRC Docket No. 50-311
SUBJECT:
Inoperability of the Chilled Water System - (21 and 22 Chillers Inoperable)
This Licensee Event Report, "Inoperability of the Chilled Water System - (21 and 22 Chillers Inoperable)" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a)(2)(i)(B).
The attached LER contains no commitments. Should you have any questions or comments regarding this submittal, please contact Mr. E. H. Villar at 856-339-5456.
Sincerely, George H. Gellrich Salem - Plant Manager Attachments (1)
ý2-95-2168 REV. 7/99
Document Control Desk Page 2 LR-N07- 0158 cc Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
-'.5 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
- 3. PAGE Salem Generating Station - Unit 2 050003111 1 OF 4
- 4. TITLE Inoperability of the Chilled Water System - (21 and 22 Chillers Inoperable)
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED S
R FACILITY NAME DOCKET NUMBER MOT DY YER YER NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05 01 2007 2007 001 00 06 29 2007 D. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 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)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
C3 50.73(a)(2)(viii)(B)
El 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 El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[] 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
E3 20.2203(a)(2)(iii)
El 50.36(c)(2)
[1 50.73(a)(2)(v)(A)
El 73.71(a)(4) 0l 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B) 0l 73.71(a)(5) 100%
El 20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
[: OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below nr in KlRr. Fnrm rRRA
- 12. LICENSEE CONTACT FOR THIS LER
- ACILITY NAME TELEPHONE NUMBER (Include Area Code)
Enrique Villar, Senior Licensing Engineer 856-339-5456CAUSE SYSTEM COMPONENT MANU-REPORTABLE I
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX X
CHU 33 R244 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION El YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
ED NO DATE 4,BSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
At 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br /> on April 25, 2007, the 22 Chiller was declared inoperable due to emergent maintenance and Technical Specification (TS) 3/4.7.10 "Chilled Water System" Action a was entered.
At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on May 1, 2007, 21 Chiller was declared inoperable because it failed to start with the initiating conditions present. With two chillers inoperable TS 3/4.7.10 Action b requires that the opposite control room Control Room Emergency Air Conditioning System (CREACS) be placed in single train filtration within four (4) hours. Action b requirements were completed within the allowable TS time from 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />. However, further investigation revealed that 21 Chiller had been inoperable since 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on May 1. Therefore, the actions of TS 3/4.7.10 Action b were not performed within the four (4) hour allowable TS time.
The cause for 21 Chiller inoperability was that the key switch was loose in its mounting hole, such that repositioning the switch did not change the state of the internal contacts. Corrective actions included the repair of the faulty switch, and verifying that the switches on the other chillers, including the ones in the opposite unit, were in proper operating condition.
This report is being made in accordance with 10CFR50.73(a)(2)(i)(B), "Operation or Condition Prohibited by Technical Specification."
(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)
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no actual safety consequences associated with this event.
Although the opposite unit CREACS was not placed in single train filtration in accordance with TS for having two inoperable chillers, the ability of the system to perform its safety function was not compromised. Placing the opposite unit CREACS in single train filtration means that the airflow through the affected unit is being circulated with the opposite unit's fans to minimize the heat load in the affected unit.
At the time of the event, some non-essential heat loads had been removed from service as a result of 22 Chiller being inoperable, and the environmental condition (river water temperature) at the beginning of May was not near the 80 OF assumed in the accident analysis. Therefore, the significance of not having placed the CREACS in single train filtration was minimal.
A review of this event determined that a Safety System Functional Failure (SSFF) as defined in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, did not occur. There was no condition that alone could have prevented the fulfillment of a safety function of a system needed to remove residual heat.
CORRECTIVE ACTIONS
- 1. 21 Chiller key switch was repaired and the chiller was returned to operable at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on May 2, 2007. TS 3/4.7.10 Action b was terminated.
- 2. The key switch mountings for all of the chillers on Unit 1 and 2 were verified to be in proper operating condition.
- 3. This event was discussed for lessons learned at Operation's shift briefings.
- 4.
This event and lessons learned will be presented to the training committee for inclusion in the operators' training.
COMMITMENTS
No commitments are made in this LER.