05000410/LER-2012-003, Regarding Suppression Pool Level Below Technical Specification Limit During Mode Change
| ML12227A356 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/02/2012 |
| From: | Philippon M Constellation Energy Group, Nine Mile Point, EDF Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 12-003-00 | |
| Download: ML12227A356 (7) | |
| 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 |
| 4102012003R00 - NRC Website | |
text
Michel A. Philippon Plant General Manager P.O. Box 63 Lycoming, New York 13093 315.349.5205 315.349.1321 Fax CENG.
a joint venture of Constellation Energy-eDF,.v NINE MILE POINT NUCLEAR STATION August 02, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
SUBJECT:
Document Control Desk Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Licensee Event Report 2012-003, Suppression Specification Limit During Mode Change Pool Level Below Technical In accordance with 10 CFR 50.73(a)(2)(i)(B), please find attached Licensee Event Report 2012-003, Suppression Pool Level Below Technical Specification Limit During Mode Change.
Should you have questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, MAP/KJK
Attachment:
Licensee Event Report 2012-003, Suppression Pool Level Below Technical Specification Limit During Mode Change cc:
NRC Project Manager NRC Resident Inspector NRC Regional Administrator 1+~
ATTACHMENT LICENSEE EVENT REPORT 2012-003 SUPPRESSION POOL LEVEL BELOW TECHNICAL SPECIFICATION LIMIT DURING MODE CHANGE Nine Mile Point Nuclear Station, LLC August 02, 2012
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Nine Mile Point Unit 2 05000410 1 of 5
- 4. TITLE Suppression Pool Level Below Technical Specification Limit During Mode Change
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NA NA NUMBER NO.NAA 06 04 2012 2012 003 0
08 02 2012 FACLITYNAM NA DOCKETNUMBERA I
INAA
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
EO 20.2201(b)
[I 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii) 2 El 20.2201(d)
[I 20.2203(a)(3)(ii)
EJ 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[I 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
- 10. POWER LEVEL [l 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
[I 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x) 10 20.2203(a)(2)(iii)
[I 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El 73.71(a)(4) 000 El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[I 73.71(a)(5)
[I 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
E0 OTHER [E
20.2203(a)(2)(vi)
ED 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in 6/4/2012; 0517 -
Reactor mode switch change from Mode 4 to Mode 2.
6/4/2012; 0846 -
The shift checks log identified the suppression pool water level is 199.4 feet. The suppression pool water level is declared not within limits and TS 3.6.2.2, Condition A, Required Action A. 1 is entered to restore suppression pool water level to within limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
6/4/2012; 0906 -
Started 2CSH*P1 (High Pressure Core Spray Pump) to restore suppression pool water level.
6/4/2012; 0926 -
Secured 2CSH*P1 following suppression pool filling. Suppression pool water level is 199.9 feet.
6/4/2012; 0933 -
Declared suppression pool water level within limits and exited TS 3.6.2.2, Condition A.
E. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED
None
F. METHOD OF DISCOVERY
At the time of discovery, June 4, 2012, at 0846, NMP2 was in Mode 2 with the reactor critical, below the point of adding heat, when the shift checks log identified suppression pool water level at 199.4 feet. The low suppression pool water level resulted in an unplanned entry into TS 3.6.2,2 Condition A to restore level within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Based on a review of relevant information using control room logs and the PI system, there is firm evidence that the discrepancy existed before the time of discovery. PI data clearly shows a lowering trend of suppression pool water level for the preceding 4 days and indicates that the suppression pool water level was below 199.5 feet at the time the mode switch was changed from Mode 4 to Mode 2 on June 4, 2012, at 0517.
G. MAJOR OPERATOR ACTION:
Upon discovery of the condition, TS 3.6.2.2 Condition A was entered for suppression pool water level below 199.5 feet. Suppression pool water level was restored at 0926. TS 3.6.2.2 Condition A was exited at 0933.
H. SAFETY SYSTEM RESPONSES:
None. No operational conditions requiring the response of safety systems occurred as a result of this event.
II. CAUSE OF THE EVENT
The cause of this event is a failure to recognize abnormalities. The surveillance performers, reviewers and verifiers failed to recognize that although suppression pool water level was within the required band, an abnormal trend existed based on data collected previously. The operators and control room supervision did not recognize that little margin remained to the TS required lower level for suppression pool water level for operation in Mode 2.
This event was entered into the Nine Mile Point Nuclear Station (NMPNS) corrective action program (CR-2012-005507).
IlI. ANALYSIS OF THE EVENT:
This event is reportable in accordance with 10 CFR 50.73 (a)(2)(i)(B), as an operation or condition which was prohibited by the plant's Technical Specifications.
LCO 3.0.1 requires that LCOs shall be met during the MODES or other specified conditions in the Applicability.
Contrary to the requirements of LCO 3.0.1, LCO 3.6.2.2, was not met on June 4, 2012, at 0517, when NMP2 entered Mode 2 with suppression pool water level below the minimum required level of 199.5 feet.
At the time of discovery on June 4, 2012 at 0846, TS 3.6.2.2, Required Action A. 1 was entered and suppression pool water level was restored at 0926, within the required action completion time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The suppression pool water level was not within limits for 40 minutes from the time of discovery and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 9 minutes from the time that Mode 2 was entered.
After the event, an evaluation of PI data and the shift checks log data was performed to determine suppression pool water level when NMP2 changed from Mode 4 to Mode 2 on June 4, 2012 at 0517. Minimum suppression pool water level for operation in Mode 2 is 199.5 feet. Evaluation of the PI data determined suppression pool water level was at 199.44 feet at the time of mode change. An evaluation of the shift checks log was performed and determined that suppression pool water level was at 199.47 feet at the time of mode change. Both sources of information provide firm evidence that suppression pool water level was below the required minimum limit at the time of mode change.
Per NUREG-1022, Revision 2, Section 3.2.2, an LER is required if a condition existed for a time longer than permitted by the technical specifications even if the condition was not discovered until after the allowable time had elapsed and the condition was rectified immediately upon discovery.
There were no actual safety consequences from this event. For the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 9 minutes that suppression pool water level was below 199.5 feet in Mode 2, reactor coolant system temperature was not above 212 degrees Fahrenheit; thus the pressure suppression capability of the suppression pool would not have been challenged during a Loss of Coolant Accident. Steam was not being generated and a safety relief valve opening would not have challenged the design limit of the suppression pool.
The most probable cause of suppression pool water level lowering from May 31, 2012 to June 4, 2012 is leakage from 2RHS*MOVlB, the Residual Heat Removal (RHR) pump B suction valve from the suppression pool. From May 31, 2012 to June 4, 2012, 2RHS *MOV lB was closed and the RHR B subsystem was operating in the shutdown cooling mode of operation.
2RHS*MOV1B is normally open during Mode 2.
This event does not affect the NRC Regulatory Oversight Process (ROP) Index items.
N
IV. CORRECTIVE ACTIONS
A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
- 1. Restored suppression pool water level to 199.9 feet.
B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
- 1. A communication will be developed for distribution to the NMP1 and NMP2 operating crews. The communication will discuss lessons learned from this event with an emphasis on operator fundamentals of plant parameter monitoring and control. The lessons learned will stress the importance of verifying margin to allowable limits when recording data, and monitoring for evidence of trends, so that preemptive action may be taken to prevent established limits from being exceeded.
- 2. Troubleshooting will be performed during the next outage to determine if leakage past 2RHS*MOV1B is present with the valve in the closed position. This troubleshooting is only able to be performed when the RHR B subsystem is in the shutdown cooling mode of operation.
V. ADDITIONAL INFORMATION
A. FAILED COMPONENTS:
None B. PREVIOUS LERs ON SIMILAR EVENTS:
None C. THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EUS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:
COMPONENT IEEE 803 COMPONENT IDENTIFIER IEEE 805 SYSTEM IDENTIFICATION NA None NA D. SPECIAL COMMENTS:
None