05000282/LER-2009-002, Regarding Unplanned Safety Related Actuation of 121 Cooling Water Pump
| ML091390396 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/18/2009 |
| From: | Wadley M Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-09-067 LER 09-002-00 | |
| Download: ML091390396 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv), System Actuation |
| 2822009002R00 - NRC Website | |
text
39, qbd. Xcel Energy Prairie Island Nuclear Generating Plant Northern States Power Company, M~nnesota MAY 1 8 2009 L-PI-09-067 10 CFR 50.73 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 1 Docket 50-282 License No. DPR-42 LER 1-09-02, Unplanned Safetv Related Actuation of 121 Coolina Water Pump Northern States Power Company, a Minnesota corporation (NSPM) herewith encloses Licensee Event Report (LER) 1-09-02. The LER describes a condition where the 121 cooling water pump had an unplanned start while aligned as a safeguards pump.
Please contact us if you require additional information related to this event.
Summarv of Commitments This letter contains no new commitments and no changes to existing commitments.
Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Department of Commerce, State of Minnesota 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
ENCLOSURE LICENSEE EVENT REPORT 1-09-02 3 Pages Follow
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digitslcharacters for each block)
- 1. FACILITY NAME Prairie Island Nuclear Generating Plant Unit 1 APPROVED BY OMB NO. 3150-0104 EXPIRES: 0813112010 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated lnto the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIAIPrivacy Service Branch (7-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of lnformat~on and Regulatory Affairs, NEOB-10202, (3150-0066), Office of Management and Budget, Washington, DC 20503. 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.
- 2. DOCKET NUMBER 05000282
- 4. TITLE Unplanned Safety Related Actuation of 121 Cooling Water Pump
- 3. PAGE 1 of3
- 5. EVENT DATE YEAR 2009 MONTH 03
- 6. LER NUMBER
- 12. LICENSEE CONTACT FOR THlS LER
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i)
(7 50.73(a)(2)(i)(C) 50,73(a)(2)(vii) 20.2201(d)
(7 20.2203(a)(3)(ii)
(7 50.73(a)(2)(ii)(A) 50.73(a)(Z)(viii)(A) 20.2203(a)(I)
(7 20.2203(a)(4)
(7 50.73(a)(Z)(ii)(B)
(7 50.73(a)(2)(viii)(B)
(7 20.2203(a)(2)(i)
(7 50.36(c)(l)(i)(A)
(7 50,73(a)(2)(iii)
(7 50,73(a)(2)(ix)(A) 20.2203(a)(Z)(ii) 50,36(c)(l)(ii)(A) a 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
(7 20.2203(a)(2)(iii) 50.36(~)(2) 50,73(a)(2)(v)(A)
(7 73.71(a)(4) 20.2203(a)(2)(iv) 50,46(a)(3)(ii)
(7 50,73(a)(Z)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v)
(7 50,73(a)(Z)(i)(A)
(7 50,73(a)(Z)(v)(C)
OTHER Speclfy In Abstracl below or in
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100 DAY 19 SEQUENTIAL NAME Jorge L. O'Farrill
- 7. REPORT DATE REV TELEPHONE NUMBER (Include Area Code) 651.388.1 121
- 8. OTHER FACILITIES INVOLVED YEAR I NUMBER I NO 2009 - 002 - 00 YEAR 2009 FACILITY NAME FACILITY NAME MONTH 05 DOCKET NUMBER DOCKET NUMBER DAY 18
CAUSE
SYSTEM COMPONENT YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On March 19, 2009, Prairie lsland Nuclear Generating Plant (PINGP) Unit 1 was operating in mode 1 at 100% power. The 121 Motor Driven Cooling Water Pump (MDCLP) was aligned as a safeguard replacement pump per procedure for planned maintenance of the 12 Diesel Driven Cooling Water Pump (DDCLP). Maintenance steps were completed to a point allowing restoration and post maintenance testing (PMT) of 12 DDCLP in accordance with a maintenance procedures. However, required steps in the operation's procedure to align the 121 MDCLP to its normal non-safeguards alignment prior to starting post maintenance testing were not performed. When aligned as a safeguard pump, any unplanned actuation is reportable under 10 CFR 50.73(a)(2)(iv).
121 MDCLP operated normally and there were no adverse plant effects from the transient.
NRC FORM 366 (9-2007)
DAY
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE).
O NO SUBMISSION DATE MANU-FACTURER MONTH REPORTABLE TO EPlX
CAUSE
SYSTEM COMPONENT MANU-FA CTURER REPORTABLE TO EPlX
EVENT DESCRIPTION
- - LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
CONTINUATION SHEET On March 19, 2009, Prairie Island Nuclear Generating Plant (PINGP) Unit 1 was operating in mode 1 at 100°/~ power. The 121 Motor Driven Cooling water' Pump (MDCLP) was aligned as a safeguard replacement pump per procedure for planned maintenance of the 12 Diesel Driven Cooling Water Pump (DDCLP). Maintenance steps were completed to a point allowing restoration and post maintenance testing (PMT) of 12 DDCLP in accordance with maintenance procedures. However, required steps in the operation's procedure to align the 121 MDCLP to its normal non-safeguards alignment prior to starting post maintenance testing were not performed.
- 1. FACILITY NAME Prairie Island Nuclear Generating Plant Unit 1 Permission to perform testing was granted and the 12 DDCLP was started per the maintenance procedure. At 1532, the 12 DDCLP was tripped by procedure from rated speed resulting in a cooling water pressure transient. The momentary drop in pressure was large enough to automatically start the 121 MDCLP while it was aligned for safeguards service. At this point operations personnel realized that the 121 MDCLP had been rendered inoperable by the PMT of the 12 DDCLP and that the required Limiting Condition for Operation (LCO) condition entry had been missed.
Testing of the 12 DDCLP was stopped by issuing a stop work order and Technical Specification (TS)
LC0 3.7.8 Condition A was entered for not having an operable safeguards pump for one train of the CL system. At 1613 the CL system was restored to an operable status by restoring operability of the 121 MDCLP and TS LC0 Condition A was exited. At 1936 the 121 MDCLP was shut down and returned to standby. At this point it was still aligned as the safeguards pump for train 'A'. The following day the stop work order was lifted and work was resumed to realign 121 MDCLP to normal and restore 12 DDCLP activities.
- 2. DOCKET NUMBER 05000282 When aligned as a safeguard pump, any unplanned actuation is reportable under 10 CFR 50.73(a)(2)(iv). This event was previously reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) on March 19, 2009.
EVENT ANALYSIS AND SAFETY SIGNIFICANCE
- 6. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO 2009 -
002
- - 00 The 12 DDCLP was being started and stopped locally for PMT prior to restoration in accordance with preventative maintenance procedures. The 12 DDCLP had been tripped during performance of an overspeed trip test when the automatic start of the 121 MDCLP occurred. It was at this point that it was discovered that the 121 MDCLP had not been restored to its normal non-safeguards lineup and that the required Limiting Condition for Operation (LCO) Condition was not entered prior to commencing PMT and return to service testing (RTST) of the 12 DDCLP.
- 3. PAGE 2 of 3 The significance of this event arises out of the fact that when the automatic start of the 121 MDCLP occurred, PINGP was relying on it as the safeguards pump for the Unit 1 train 'A' CL header because the 12 DDCLP had not yet been returned to service.
Ells System Identifier: BS
This event is considered of low safety significance because PINGP operating procedures direct entry into the appropriate LC0 Condition for not having a CL pump operable for one train. Although the procedural step was missed to enter the condition and realign the 121 MDCLP away from being a safeguards pump, the expected configuration for this PMT was to not have any safeguard CL pumps operable for this train until testing could be completed and the LC0 condition exited. LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
CONTINUATION SHEET
CAUSE
- 1. FACILITY NAME Prairie Island Nuclear Generating Plant Unit 1 The PMT was being performed by following steps located in multiple procedures. The PM activities had been previously included as part of a single procedure, but changes to the PINGP procedure program had the procedure split into separate procedures for operations and maintenance. The apparent cause of the event is attributed to the fact that referencing and branching did not exist between the revised maintenance and operating procedures to ensure operations procedure steps were complete prior to commencing PMT.
CORRECTIVE ACTION
I
- 2. DOCKET NUMBER 05000282 Proposed corrective actions include adding instructions to the maintenance procedure to ensure that it properly references the operations procedure. A review of PM's will also be completed on safety-related components to ensure proper referencing and branching is utilized where a similar unplanned safety system actuation could occur. Additional planned corrective actions include adding a PM coordinator and additional staff to assist with implementation of the procedure-upgrade program, and revising the complex work procedure to contain objective criteria for determination of complex work.
PREVIOUS SIMILAR EVENTS
- 6. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO 2009 -
002
- - 00 There have been several instances of automatic pump starts attributed to procedural inadequacies at PINGP. These include the 121 MDCLP, 121 motor driven fire pump2, and 22 component cooling3 pump. No other instances of the 121 MDCLP auto-starting while aligned as a safeguards pump could be found.
- 3. PAGE 3 of 3 Ells System Identifier: KP Ells System Identifier: CC