05000423/LER-2011-001, Regarding Failure to Enter Technical Specification Action Statement
| ML11319A144 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/07/2011 |
| From: | Jordan A Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 11-626 LER 11-001-00 | |
| Download: ML11319A144 (4) | |
| 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 |
| LER closed by | |
| IR 05000245/2012005 (16 January 2013) | |
| 4232011001R00 - NRC Website | |
text
z Dominion-Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT 06385 NGV 0 7 2011 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/LES Docket No.
License No.11-626 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2011-001-00 MILLSTONE POWER STATION UNIT 3 FAILURE TO ENTER TECHNICAL SPECIFICATION ACTION STATEMENT This letter forwards Licensee Event Report (LER) 2011-001-00 documenting a condition prohibited by the plant's Technical Specifications at Millstone Power Station Unit 3 on September 10, 2011. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B).
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.
Sincerely, A. J4 Site President - Millstone Attachments: 1 Commitments made in this letter: None
Serial No.11-626 Docket No. 50-423 Licensee Event Report 2011-001-00 Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
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, digits/characters for each block) and a person is not required to respond to, the information collection.
- 3. PAGE Millstone Power Station - Unit 3 05000423 1 OF2
- 4. TITLE Failure to Enter Technical Specification Action Statement
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED M
FACILITY NAME DOCKET NUMBER SEQUENTIAL REV MONTH DAY YEAR 05000 MONTH DAY YEAR YER NM R
NO YER NUMBER NO.05 0
FACILITY NAME DOCKET NUMBER 09 10 2011 2011 -001-00 11 07 2011 05000
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR :(Check all that apply)
- 9. OPERATING MODE 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 100 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in
- 1.
Event Description
On September 10, 2011, while operating in MODE 1 at 100% power, Millstone Power Station Unit 3 (MPS3) identified that a value recorded on August 11, 2011, for the Bandpass Filter Offset Voltage for one channel of MPS3 's Gamma Metrics wide range nuclear instrumentation (3NME*AMPL2) [MON] [IG] was left outside of the acceptance criteria defined in Surveillance Procedure SP3441 E01 after the surveillance was completed. It was assessed at the time of discovery that this resulted in Accident Monitoring Instrumentation Instrument 19 "Neutron Flux" Channel 2 being inoperable per Plant Technical Specification (TS) 3.3.3.6.
The condition was not noted on August 11, 2011, and the action statement was not entered until September 10, 2011.
Action statement 3.3.3.6.a was entered upon discovery at 0025 on September 10, 2011. The surveillance procedure was successfully completed and the equipment was restored to operable status at 0425 on September 10, 2011. TS action statement 3.3.3.6 a (1) requires with less than the required number of channels OPERABLE, restoration of the inoperable channel(s) to OPERABLE status within 7 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications.
- 2.
Cause
The condition of the recorded voltage being outside of the acceptance criteria was not noted until September 10, 2011 due to inadequate review of calculated surveillance results on data sheets.
- 3.
Assessment of Safety Consequences
The safety consequences of this event were very low. Although the acceptance criteria was included in the station's Surveillance Procedure, the monitored parameter was subsequently found unnecessary to assure operability of the nuclear instrumentation.
- 4.
Corrective Action
The surveillance procedure was successfully completed within four hours of identification of the condition, and the equipment was restored to operable status. The surveillance procedure has been revised to specify that measured offset voltage is not a TS acceptance criterion and extent of condition has been addressed.
Human performance aspects of this issue have been addressed through the corrective action program.
Procedure changes being implemented will include independent reviews of calculated results on data sheets from I&C surveillances to ensure acceptance criteria are met prior to returning equipment to service.
Additional corrective actions are being taken in accordance with the station's corrective action program.
- 5.
Previous Occurrences
No previous similar events were identified where the procedure was not followed when a Technical Specification surveillance acceptance criterion was not met, and prompt actions were not taken.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
LNR'C -UORM 366A (10]U-2U0U)