05000443/LER-2004-003, Regarding Fire Scenario Results in Unanalyzed Condition-Potential Loss of Charging
| ML043650319 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/23/2004 |
| From: | Warner M Florida Power & Light Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-04154 LER 04-003-00 | |
| Download: ML043650319 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4432004003R00 - NRC Website | |
text
FPL Energy Seabrook Station FPL Energy Seabrook Station P.O. Box 300 Seabrook, N11 03874 (603) 773-7000 DEC 23 2004 Docket No. 50-443 SBK-L-04154 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 2004-003-00 for Fire Scenario Results in Unanalyzed Condition-Potential Loss of Charging Enclosed is Licensee Event Report (LER) 2004-003-00. This LER reports an event that occurred at Seabrook Station on November 2, 2004.
This event is being reported pursuant to the requirements of 10 CFR 50.73(a)(2)(ii)(B).
Should you require further information regarding this matter, please contact Mr. James M.
Peschel, Regulatory Programs Manager, at (603) 773-7194.
Very truly yours, FPL ENERGY SEABROOK, LLC Mark E. Warner Site Vice President cc:
S. J. Collins, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector z'
ENCLOSURE TO SBK-L-04154
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007
.2004)
, the NRC may for each block) not conduct or sponsor, and a person Is not required to respond to, the digits/characters fo ahbok nfonation cotiection.
- 3. PAGE Seabrook Station 05000 44 1 OF 3
- 4. TITLE Fire Scenario Results in Unanalyzed Condition-Potential Loss of Charging
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNTA{RVFACILITY NAM6E DOCKET NUMBER MONTH DAY YEAR YEAR SENUMBER N
NO.
MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 11 02 2004 2004 - 003 -
00 12 23 2004 N/A 05000
- 9. OPERATING MODE 11 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check al that apply) o 20.2201(b)
El 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
E 50.73(a)(2)(vii) l 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(2)(i)
El 50.36(c)(1)(1)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
O 20.2203(a)(2)(iii)
El 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4)
D 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 100 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below or In NRC Fonn 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Indude Area Code)
James M. Peschel, Regulatory Programs Manager 1603-773-7194CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU_
REPORTABLE I _____FACTURER TO EPIX FACTURER TO EPIX NA NA I NA NA NA NA NA NA NA NA
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSIONI 0 YES (If'yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE NA NA NA ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On November 2, 2004, a review of potential fire scenarios found that fires in four plant areas could disable both charging system trains. A fire could cause a spurious closure of the volume control tank (VCT) outlet valve and cause damage to the operating charging pump. The fire could also damage the cables for the standby charging pump, rendering both charging pumps unavailable. Since the station's design basis is that one train of required systems is free of fire damage, these scenarios result in an unanalyzed condition. The analyses for fire areas, prepared in the mid-1980s, reviewed spurious equipment operation. However, the report failed to consider the unique interaction between the spurious closure of a VCT outlet valve and the operating charging pump in the redundant train. Compensatory actions that were implemented to mitigate the effects of this condition include: establishing an hourly fire patrol in the four fire areas of concern, minimizing combustible materials in the four areas, briefing the operators on this condition, and revising procedures to establish an alternate flow path to the charging pump in response to a fire alarm in any of the four areas. A design change is being planned to correct this condition. The condition resulted in no adverse safety consequences; however, it is of regulatory significance because it represented an unanalyzed condition.
NRC FORM 36 (6-200)
PRINTED ON RECYCLED PAPER
-~~~~.;~ ~
- - t,-
(If more space Is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
IV. Corrective Actions
Following discovery of the condition, the station established the following compensatory actions:
a. An hourly fire watch patrol was established in the four fire areas where cables associated with both the VCT outlet valve and standby-charging pump could be damaged. If fire detection becomes inoperable in these areas, a continuous fire watch will be posted in the affected area.
b.
Existing transient combustible material permits were reviewed for the four fire areas to ensure that the quantity of materials is minimized to that necessary to support current work.
c. The operators were briefed on this condition and the compensatory measures d. The abnormal operating procedure for fire response was revised to establish an alternate suction path to the charging pumps in response to a fire alarm in any of the four fire areas of concern.
The planned corrective action for this condition is to implement a design change, currently under development, that modifies the circuits for the VCT outlet valves. The purpose of the design change will be to eliminate the hot short failure mode in these circuits.
V. Similar Events
None