05000282/LER-2008-001, Re One Train of Auxiliary Feedwater Inoperable Longer than Allowed by Technical Specifications

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Re One Train of Auxiliary Feedwater Inoperable Longer than Allowed by Technical Specifications
ML081350320
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 05/14/2008
From: Wadley M
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-08-039 LER 08-001-00
Download: ML081350320 (5)
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LER-2008-001, Re One Train of Auxiliary Feedwater Inoperable Longer than Allowed by Technical Specifications
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(v), Loss of Safety Function
2822008001R00 - NRC Website
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text

Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC May 14,2008 L-PI-08-039 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 1-08-01. One Train of Auxiliarv Feedwater (AFW) Svstem Inoperable Longer than Allowed bv Technical Specifications Nuclear Management Company, LLC (NMC) herewith encloses Licensee Event Report (LER) 1-08-01. The LER describes a condition where one train of the ARN system was inoperable longer than allow by Technical Specifications. The condition also includes mode changes made with a train of the AFW system inoperable, which is also in violation of Technical Specifications. Please contact us if you require additional information related to this event.

Summary of Commitments This letter contains no new commitments and no changes to existing commitments.

Michael D. Wadley u

Site Vice President, Prairie lsland Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc:

Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Department of Commerce, State of Minnesota 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121

ENCLOSURE LICENSEE EVENT REPORT 1-08-01 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 Generat~ng Plant Unit 1 APPROVED BY OMB NO 3150-0104 EXPIRES 08/31/2010 Estimated burden per response to comply wlth thls mandatory collectlon 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 Into the llcenslng process and fed back to ~ndustry Send comments regarding burden estlmate to the Records and FOlAlPr~vacy Sewlce Branch (T-5 F52). U S Nuclear Regulatory Commlsslon, Washlngton, DC 20555-0001, or by Internet e-mall to ~nfocollects@nrc gov, and to the Desk Officer, Office of lnforrnatlon and Regulatoly Affalrs, NEOB-10202. (3150-0066), Office of Management and Budget, Washington, DC 20503 If a means used to lmpose an ~nformat~on collection does not display a currently valld OMB control number, the NRC may not conduct or sponsor, and a person 1s not requlred to respond to, the lnformatlon collectlon
2. DOCKET NUMBER 05000282
4. TITLE One Tram of Aux~l~at-y Feedwater Inoperable Longer than Allowed by Technical Specifications
3. PAGE 1 of 3
8. OTHER FACILITIES INVOLVED
5. EVENT DATE
9. OPERATING MODE 3
10. POWER LEVEL 0

FACILITY NAME FAClLllY NAME MONTH 3

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply) 20 2201(b)

[7 20.2203(a)(3)(1) 50 73(a)(2)(1)(C) 50.73(a)(2)(vll) 20 2201(d) 20 2203(a)(3)(11)

I7 50.73(a)(2)(1i)(A) 50 73(a)(2)(v111)(A) 20.2203(a)(1) 20 2203(a)(4)

[7 50,73(a)(2)(il)(B)

[7 50.73(a)(2)(vill)(B) 20 2203(a)(2)(1) 50 36(c)(l )(l)(A) 50 73(a)(2)(i11) 50.73(a)(2)(1x)(A)

[7 20 2203(a)(2)(11) 50 36(c)(l)(r)(A) 50 73(a)(2)(1v)(A)

[7 50 73(a)(2)(x) 20 2203(a)(2)(111)

[7 50 36(c)(2)

[7 50.73(a)(2)(v)(A)

[7 73 71 (a)(4)

[7 20.2203(a)(2)(1v)

[7 50 46(a)(3)(li)

[7 50 73(a)(2)(v)(B)

[7 73 71(a)(5) 20 2203(a)(2)(v) 50 73(a)(2)(l)(A)

[7 50,73(a)(2)(v)(C)

OTHER 20 2203(a)(2)(v1) a 50 73(a)(2)(1)(B) 1 Specify m Abstract below or In DOCKET NUMBER DOCKET NUMBER

6. LER NUMBER
7. REPORT DATE DAY 15 YEAR YEAR 2008
12. LICENSEE CONTACT FOR THlS LER YEAR 2008 2008 0 SEQUENTIAL NUMBER MONTH 05 NAME J e f f Kivi REV NO DAY 14 TELEPHONE NUMBER (Include Area Code) 651.388.1121 MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT FA CTURER TO EPIX

CAUSE

A

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR SUBMISSION 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE).

O NO DATE ABSTRACT (Limit to 1400 spaces, i e, approx~rnately 15 single-spaced typewritten lines)

On March 15, 2008, Prairie Island Nuclear Generating Plant (PINGP) Unit 1 went to Mode 3 at 1059. On March 23, 2008, with Unit 1 in Mode I, Technical Specification (TS) 3.7.5 Condition B was entered to conduct surveillance testing on the 11 turbine-driven auxiliary feedwater pump (TDAFWP). The test was stopped before it could be completed due to high temperature on the outboard turbine bearing. An evaluation concluded the 11 TDAFWP had been inoperable since before the plant entered Mode 3. The 11 TDAFWP is required per TS 3.7.5 to be operable when the unit reaches Mode 3. TS 3.7.5 Condition B requires the inoperable auxiliary feedwater (ARN) train be restored to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If Condition B is not met, Condition C allows six hours to get to Mode 3 and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to get to Mode 4. Since Unit 1 was determined to be inoperable as a result of surveillance testing, and was in Mode 3 and was not brought to Mode 4 after 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in Condition B as required by TS 3.7.5 Condition C, this event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. In addition, Unit 1 went from Mode 4 to Mode 1 with the 11 TDAFWP inoperable, which is also prohibited by TS.

After troubleshooting, the pump was restored to operable status by adjusting the insulation on the turbine and nearby hot components and then successfully passed the surveillance test.

NRC FORM 366 (9-2007)

SYSTEM B A COMPONENT P

MANU-FACTURER TI47 REPORTABLE TO EPIX Y

EVENT DESCRIPTION

NRC FORM 36644 LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION (9-2007)

CONTINUATION SHEET On March 15, 2008, Prairie Island Nuclear Generating Plant (PINGP) Unit 1 went to Mode 3 at 1059.

On March 23, 2008, with Unit 1 in Mode I, Technical Specification (TS) 3.7.5 Condition B was entered to conduct surveillance testing on the 11 turbine1-driven auxiliary feedwate? pump3 (TDAFWP). The test was stopped before it could be completed due to high temperature on the outboard turbine bearing (the procedure requires turbine bearing temperature be maintained less than 220 degrees F). An evaluation concluded the 11 TDAFWP had been inoperable since before the plant entered Mode 3.

EVENT ANALYSIS

3. PAGE 2 of 3
1. FACILITY NAME Prairie Island Nuclear Generating Plant Unit 1 The 11 TDAFWP is required per TS 3.7.5 to be operable when the unit reaches Mode 3. TS 3.7.5 Condition B requires the inoperable auxiliary feedwater (AFW) train be restored to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If Condition B is not met, Condition C allows six hours to get to Mode 3 and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to get to Mode 4. Since Unit 1 was determined to be inoperable as a result of surveillance testing, and was in Mode 3 and was not brought to Mode 4 after 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in Condition B as required by TS 3.7.5 Condition C, this event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. In addition, Unit 1 went from Mode 4 to Mode 3 to Mode 2 to Mode 1 with the 11 TDAFWP inoperable, which is also prohibited by TS.

Impact on Safetv Svstem Functional Failure Performance Indicator

2. DOCKET 05000282 No actual loss of function occurred as a result of this event. The redundant 12 motor4-driven AFW pump was operable while the 11 TDAFWP was inoperable. Thus, this event is not reportable per I

OCFR 50.73(a)(2)(v).

6. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO 2008 -

01

- 0

SAFETY SIGNIFICANCE

This event only affected the 11 TDAFWP and the redundant ARN pump remained operable, so the safety function was not lost. Thus, this event did not affect the health and safety of the public and the safety significance of this event is considered minimal.

CAUSE

Troubleshooting concluded the high outboard turbine bearing temperature for 11 TDAFWP was caused by insulation5 issues after the pump was reassembled during the refueling outage. High 1

2 Ells Component Identifier: TRB 3 Ells System Identifier: BA Ells Component Identifier: P 4 Ells Component Identifier: MO

radiant heat from surrounding components as well as the insulation configuration not allowing heat to dissipate from the turbine casing led to the high temperatures. In addition, the AFW pumps use bypass flow to cool the bearings. However, this bypass flow is not measurable, so to meet full-flow requirements for inservice testing, the cooling water is isolated for portions of the surveillance testing.

This intermittent isolation of cooling water was determined to be a contributing cause. LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION (9-2007)

CONTINUATION SHEET

CORRECTIVE ACTION

Once the high temperature lines and equipment in close proximity to the bearing housing were reinsulated, the outboard turbine bearing temperature was below the 220 degree action range. The 1 1 TDAFWP passed the surveillance following the insulation adjustment.

3. PAGE 3 of 3
1. FACILITY NAME Prairie Island Nuclear Generating Plant Unit 1 Additional corrective actions include:
1. Revise the surveillance procedures to reduce the time that cooling flow is isolated.
2. Develop and install an insulation package that provides protection to the bearing housing yet allows heat from the turbine to be dissipated to the atmosphere for the TDAFWPs.
2. DOCKET NUMBER 05000282

PREVIOUS SIMILAR EVENTS

6. LER NUMBER YEAR SEQUENTIAL REV NUMBER NO 2008 -

01

- 0 Review of Licensee Event Reports for Unit 1 and Unit 2 since 2005 found a similar event reported in Licensee Event Report 1-06-02 where Unit 1 was operated in a condition prohibited by TS due to an inoperable 1 1 TDAFWP.

Ells Component Identifier: ISL

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