05000305/LER-2006-007, Regarding RCS RTD Cross Calibration Procedure Has the Potential to Exceed the TS LCO Allowed Time Limit
| ML062340330 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 08/11/2006 |
| From: | Hartz L Dominion, Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-666 LER 06-007-00 | |
| Download: ML062340330 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) |
| 3052006007R00 - NRC Website | |
text
+/-ý.ýDminiolif Dominion Energy Kewaunee, Inc.
N490 Highway 42, Kewaunee, WI 54216-9511 AUG 11 2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.06-666 KPS/LIC/RS: RO Docket No.
50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION LICENSEE EVENT REPORT 2006-007-00
Dear Sirs:
Pursuant to 10 CFR 50.73, Dominion Energy Kewaunee, Inc., hereby submits the following Licensee Event Report applicable to Kewaunee Power Station.
Report No. 50-305/2006-007-00 This report has been reviewed by the Plant Operating Review Committee and will be forwarded to the Management Safety Review Committee for its review.
If you have any further questions, please contact Mr. Richard Sattler at (920) 388-8121.
Very truly you Leslie N. Hartz Site Vice President, Kewaunee Power Station Attachment
Serial No.06-666 Page 2 of 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. D. H. Jaffe Project Manager U.S. Nuclear Regulatory Commission Mail Stop O-7-D-1 Washington, D. C. 20555 NRC Senior Resident Inspector Kewaunee Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulat:ry Commission, Washington, DC 20555-0001, or by internet (See reverse for required number of e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, N EOB-10202, (3150-0066), Office of Management and Budget, Washington, DC 20503.
digits/characters for each block)
If a means used to impose an Information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Kewaunee Power Station 05000305 of 3
TITLE (4)
RCS RTD cross calibration procedure has the potential to exceed the TS LCO allowed time limit EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
YERI SEUNIA E
FACILITY NAME DOCKET NUMBER MO DAY YEAR YER NUMBER NO MO DAY YEAR 6
13 2006 2006 -- 007 -- 00 8
11 2006 FACILITY NAME DOCKETNUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (Check all that apply) (11)
MODE (9)
N 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (110) 10 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71(a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or in S20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)Cv)CD) _
20.2203(a)(2)(v)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A)
_"_20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONIE NUMBER (Include Area Code)
Richard Sattler - Licensing 1
(920) 388-8121 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR S_ fyecompleteEXPECTEDSUBMSSIONDATE).
X
_NO__DATE15)
SUBMISSION [YES (If yes, complete EXPECTED SUBMISSION DATE).
X ODATE (15)
I___I I
ABSTRACT On June 13, 2006, with the station at approximately 100% power, it was determined (by procedure review), that surveillance procedure SP-47-31 0, Reactor Coolant System RTD Cross Calibration, has the potential to exceed the 24 hr allowable Limiting Condition for Operation (LCO) of item 2.b of Tech Spec Table 3.5-4 (Instrument Operating Conditions For Isolation Functions).
The surveillance procedure removes all four narrow range channels of RCS temperature from service during plant heatup, thus rendering all channels of Tavg inoperable. Item 2.b of Technical Specification Table 3.5-4 (Instrument Operating Conditions For Isolation Functions), requires at least 1 operable channel for the function (Hi Steam Flow and 2 of 4 Lo-Lo Tavg with Safety Injection). With less than the minimum channels operable, the LCO requires that the plant be placed in HOT SHUTDOWN. If the minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the LCO requires the plant be placed in a COLD SHUTDOWN condition. Therefore, if this surveillance procedure renders Tavg inoperable for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and plant heatup continues, the LCO is not met.
Corrective actions included immediately placing the procedure on Administrative Hold and initiating paperwork to revise the procedure steps and develop additional resources to reduce the time required for performance to within the allowable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This event is deemed to have no safety significance and does not constitule a safety system functional failure.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (L.ER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER ý6 PAGE (3 YEARI SQUENTIAL REVISION Kewaunee Power Station 05000305 Y
NUMBER NUMBER 2 of 3 2006 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
Event Description
On June 13, 2006, with the station at approximately 100% power, it was determined that Surveillance Procedure SP-47-310, Reactor Coolant System RTD Cross Calibration, has the potential to exceed the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowable LCO time.
This surveillance procedure removes all four narrow range channels of RCS [AB] temperature from service during plant heatup, (from approximately 350 degrees F to 500 degrees F), thus rendering all channels of Tavg inoperable. Item 2.b of Technical Specification Table 3.5-4 (Instrument Operating Conditions For Isolation Functions), requires at least 1 operable channel for the function (Hi Steam Flow and 2 of 4 Lo-Lo Tavg with Safety Injection). With less than the minimum channels operable, the LCO requires that the plant be placed in HOT SHUTDOWN. If the minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the LCO requires the plant be placed in a COLD SHUTDOWN condition. Therefore, if this surveillance procedure renders Tavg inoperable for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and plant heatup continues, the LCO is not met.
Historically, performance times for specific steps of SP-47-310 were not recorded, so the precise durations of Tavg inoperability can not be determined. It is conservatively assumed that all previous performances have exceeded the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. Consequently, when SP-47-310 was performed in November of 2004, station Technical Specification 3.5 was not met.
Event Analysis
This event is being reported in accordance with 1 OCFR50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications."
This surveillance procedure removes all four narrow range channels of RCS temperature from service for data collection during a plant heatup at a starting temperature between 350 and 380 degrees F, over a minimum span of 150 degrees F, with at least one data set obtained at hot no-load conditions. During the procedure, the plant is not allowed to exceed Hot Shutdown conditions.
During the last three years this procedure was only performed once (during recovery from a refueling outage on November 23, 2004). For that performance, a precise determination of RTD [TE] (and thus Tavg) inoperability time could not be determined. Since the procedure was in progress for 68.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, (by Control Room log entries), it is assumed that Tavg inoperability exceeded the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. The plant was not placed in COLD SHUTDOWN as required, which is a violation of TS 3.5.
There was no safety system function failure involved in this event.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (L.ER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
I SEQUENTIAL REVISION Kewaunee Power Station 05000305 YEAR SEQ NUMBER 3 of 3 2006 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
Safety Significance
There were no actual nuclear or radiation exposure consequences from this event.
The affected Tech Spec item is associated with the Engineered Safety Feature (ESF) steam line isolation.
The function of the affected portion of steam line isolation is to isolate a faulty steam line during coincident conditions of safety injection signal, low-low Tavg, and high steam flow. Since both steam lines were isolated during the entire 68.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of procedure performance, the function of the affected ESF system had already been met. Therefore, there was no safety significance for this event.
Cause
Previous application of Technical Specification Table 3.5-4 was that Item 2.b did not apply when the ESF function was otherwise disabled. Therefore, since SI is blocked below 2000 psig during a heatup, the ESF function was disabled, and the Technical Specification item did not apply. During procedure review on June 13, 2006, it was determined that the Technical Specification item did apply.
Corrective Actions
- 1. Placed Surveillance Procedure SP-47-310, Reactor Coolant System RTD Cross Calibration, on Administrative Hold until it is corrected.
- 2. The procedure will be revised to assure it is completed within the allowable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Similar Events
None