05000446/LER-2003-002, Re Actuation of Auxiliary Feedwater System
| ML032790169 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/23/2003 |
| From: | Madden F TXU Energy, TXU Generation Co, LP |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200301964, TXX-03131 LER 03-002-00 | |
| Download: ML032790169 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 4462003002R00 - NRC Website | |
text
hTXU TXU Energy Comanche Peak Steam Electric Station P.O. Box 1002 (E01)
Glen RoseTX 76043 Tel: 254 897 8920 fax: 254 897 6652 lance.terry@txu.com C. Lance Terry Senior Vice President &
Principal Nuclear Officer Ref. # 10CFR50.73(a)(2)(iv)(A)
CPSES-200301964 Log# TXX-03131 File # 10200 September 23, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-446 ACTUATION OF AUXILIARY FEEDWATER SYSTEM LICENSEE EVENT REPORT 446/03-002-00 Gentlemen:
Enclosed is Licensee Event Report (LER) 03-002-00 for Comanche Peak Steam Electric Station Unit 2, "Actuation Of Auxiliary Feedwater System Caused by Loss of Main Feedwater Pumps due to Low Suction Pressure."
This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project Wolf Creek
OA TXU 44Vkk
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TXX-03131 Page 2 of 2 Sincerely, TXU Generation Company LP By:
TXU Generation Company LP Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By:
A ld ?/- <,
By red W. Madden Nuclear Licensing Manager CLW:clw Enclosure c-B. S. Mallett, Region IV W. D. Johnson, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES
Enclosure to TXX-03131 NlC FORM 36 U.S. NUCALE RWEULATORY COMMISSION APPROVED BY OMB NO. 3150104 (7-2001)
EXPIRES 7O3M04 Enated brden per repone to eotly with this mandatory infoati colectkn request: 50 hous. Reponed bisons kained we Incorporated Into the lcensing process and fed brck to Industry. Send comments regarding bhrden estirmte lo the Records v orsss t
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DC 20503. If a nan used to Inyose Inbformatin coflection dones not display aarently vaid OME contl enumber.
the NRC may o conduct or rponor. id a neon It not required to respond.the informatkon collection.
Facilky Name (I)
Docket Number (2)
Page (3)
COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 05000446 1OF7 Tide (4)
ACTUATION OF AUXILIARY FEEDWATER SYSTEM Evn Dote tLER Number 6t)
Ret Dote 7)
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Year YaeiNy Name Dock) t Numbers Nuther Ifi Number l
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20.2201(b) 20.2203(aX3)Xi) 50.73(aX2XiXC) 50.73(aX2Xvii)
Levl 20.2201(d) 20.2203(aX3Xii) 50.7X(aX2)QiiXA) 50.73(aX2XviiXA) 1 12 I 25.2263(ax)(_
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SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES This event occurred during secondary plant startup and power escalation in progress following a sixteen day unplanned unit outage.
On July 25, 2003, at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, CPSES Unit 2 entered Mode 1, power operations. At 1317 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.011185e-4 months <br /> the unit was at approximately 12 percent power, Main Feedwater Pump (MFP) 2-B [EIIS: (SJ)(P)] was in service supplying feedwater to all 4 Steam Generators [EUS: (SG)(SB)]. Main Feedwater Pump 2-A was in the tripped condition since it was not required.
On July 25, 2003, at 1318 hours0.0153 days <br />0.366 hours <br />0.00218 weeks <br />5.01499e-4 months <br />, the Reactor Operator (RO) (utility, licensed) established flow through low pressure Feedwater Heaters [EIIS: (SJ) (HX)] 5B and 6B and both Motor Driven Auxiliary Feedwater Pumps [EUS: (BA)(P)]
auto started in response to a low suction pressure trip of the operating Main Feedwater Pump 2-B. The operators manually tripped the Main Turbine [EIIS:
(TA)(TRB)] to minimize steam demand and stabilize the plant, and manually inserted the control rods to reduce reactor power.
NRC IRM 366A (I-2001)
Enclosure to TXX-03131 (If xme qae I requktd. tow eklonal copis of (f irewe isrequred.wadibnl copiesofNRC Form 6A) (17)
(2) Verbal miscommunication during shift turnover. The oncoming shift understood from turnover that flow had been established through FW Heaters 5B and 6B by the previous shift, but the string subsequently isolated again on a FW Heater 6B Hi-Hi level indication. The previous shift had in fact only established flow through FW Heaters SA and 6A and had not attempted to place FW Heaters 5B and 6B in service due to the FW Heater 6B Hi-Hi level indication. This misunderstanding led oncoming shift personnel involved in the event to believe that the "B" string heaters were water solid and therefore, in their judgment, a fill and vent evolution prior to unisolating the string was not required.
(3) Required procedures were not used. Procedure IPO-003B 'Tower Operations,"
step 5.4.34 states : "IF 2-HS-261 1/12, FW HTR 5A & 6A/5B & 6B BYP VLV is OPEN, THEN restore 5/6 Heaters to service per SOP-303B." Procedure SOP-303B "Condensate System" includes provisions for filling/venting a feedwater heater string prior to returning it to service. For this event, procedure IPO-003B was being directly referenced as appropriate. Once the FW Heater 6B Hi-Hi level indication light extinguished, isolated FW Heaters 5B and 6B were returned to service without the use of procedure SOP-303B and without first filling/venting the heater string. Restoration of this heater string without reference to any procedure violated ODA-407 "Guideline on Use of Procedures."
V.
CORRECTIVE ACTIONS
Immediate corrective actions taken for this event include:
- 1.
Filled and vented feedwater heaters 5B and 6B in accordance with the provisions of SOP-303B "Condensate System."
- 2.
Pressurized feedwater heaters 5B and 6B in accordance with SOP-303B to verify no excessive leakage present. No excessive leakage was identified.
- 3.
Performed a Condensate System walkdown for possible water hammer effects.
No system damage was identified.
Enclosure to TXX-03131 NRC POLM 366A US NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
Facilky Name ()
Dce Nunber(6) l Page(3)
Yea wiSequeW v~
n COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 05000446 NurtO7 I
1~~03H002H 00 6OF 7 NARATIVE (Ifm pe qare k.quied.
we usaddtil ciesKNRC Form 366A) (17)
Actions to prevent recurrence of this event, as included in the CPSES Corrective Action Program, are as follows:
I.
A post-job critique has been documented and a Lessons Learned memorandum has been issued.
- 2.
Procedures associated with this event have been revised to ensure that procedures are directly referenced during component manipulations.
- 3.
Management expectations for procedure use, ODA-407, "Guideline on Use of Procedures," and how to handle in-process evolutions at shift turnover are being re-enforced.
TXU Energy is considering other corrective actions, including revising appropriate Nuclear Training Lesson Notes and enhancing Licensed Operator simulator training to further emphasize removing/restoring feedwater heaters from/to service and to provide reference to previous in-house operating experience.
VI.
PREVIOUS SIMILAR EVENTS
There was one previous similar event at CPSES which occurred February 4, 1996 (LER 445/96-003-00). In this previous event, the feedwater heater string was intentionally being drained for the purpose of reducing hotwell level. This draining evolution resulted in a significant void in the heater.
The cause of the 1996 event was lack of procedural guidance for reducing hotwell inventory via draining to the Turbine Building sump such that low pressure feedwater heater strings are properly restored to service (the draining evolution includes the opening of feedwater heater string drain cooler drain valves which allows air to enter the heater strings). Corrective actions included: (a) enhancement to procedures SOP-303A/B "Condensate System" and IPO-003A/B "Power Operations"; and (b) issuance of a Lessons Learned memorandum "Restoring an Isolated Heater String" within the Operations Department. The Lessons Learned memorandum discussed the need to properly fill and vent feedwater heaters in accordance with SOP-303A/B prior to returning them to service in order to prevent a water hammer event.
NRCFORM6&A(I.s201)
Enclosure to T)XX-03131 NRC POILM 366A US. Nl~UCAR RMEULATORY COMMISSION (1-21001)
LICENSEE EVENT REPORT (LER)
Facility Name (1)
Dock Net l
Nme P1Ag3)
YerlSequenil 1
Rei son COMANCHE PEAK STEAM ELECTIC STATION UNIT 2 0500446Nunber Is004 0 3 _
002H_
00I 7OF7 NARRATVE (Ifm space iequked use aditnaIpso(NRCForm366A) (17)
Had the provisions of procedure SOP-303B been followed, this July 25, 2003 event would not have occurred. As discussed above under corrective actions, TXU Energy is considering other corrective actions, including revising appropriate Nuclear Training Lesson Notes and enhancing Licensed Operator simulator training to further emphasize removing/restoring feedwater heaters from/to service and to provide reference to previous in-house operating experience.
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