05000331/LER-2002-001, Entergy Center, Unplanned Mode Change White Re-Aligning the RHR System from Shutdown Cooling (SDC) Mode to Low Pressure Coolant Injection (LPCI) Standby Readiness During Reactor Startup
| ML021300344 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/25/2002 |
| From: | Richard Anderson Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-02-0344 LER 02-001-00 | |
| Download: ML021300344 (6) | |
| 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)(i)(B), Prohibited by Technical Specifications |
| 3312002001R00 - NRC Website | |
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INMC1 Committed to Nuclear Excellence DAEC Plant Support Center Operated by Nuclear Management Company, LLC April 25, 2002 NG-02-0344 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station 0-P 1-17 Washington, D.C. 20555-0001
Subject:
File:
Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Licensee Event Report #2002-001 -00 A-120
Dear Sirs:
Please find attached the subject Licensee Event Report (LER) submitted in accordance with 1 OCFR50.73. The following commitments have been made for this report:
- 1. An evaluation for a more positive method of preventing nut rotation as an alternative to the setscrew for this type of valve will be performed.
- 2. Follow-up maintenance will be performed as necessary on similar valves to prevent recurrence. The maintenance will include removal of the operator cover and internal inspection that includes the security of the nut and it's setscrew and lubrication of the gears. Security of the valve hand wheel and proper engagement of the cover bolts should also be verified. This will be accomplished during normal, scheduled system windows and during the next refuel outage.
Should you have any questions regarding this report, please contact this office.
Sincerely, Rob Anderson, Plant Manager - Nuclear 3313 DAEC Road
- Palo, Iowa 52324-9646 ilL Telephone: 319.851.7611
April 25, 2002 NG-02-0344 cc:
Mr. James Dyer Regional Administrator, Region III U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532 NRC Resident Inspector - DAEC DOCU
NRC FORM 366 U.S. NUCLEAR REGULAT APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 (1-2001)
, 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) lPAGE (3)
Duane Arnold Energy Center 05000331 1 of 4 TITLE (4)
Unplanned Mode Change While Re-Aligning the RHR System from Shutdown Cooling (SDC) Mode to Low Pressure Coolant Injection (LPCI) Stand by Readiness During Reactor Startup EVENT DATE (6)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR FACILITY NAME DOCKET NUMBER MO AY YEAMYAREORAYNEA FACILITY NAME DOCKET NUMBER 03 08 2002 2002 001 00 04 25 2002 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (11)
MODE (9) 4
=
20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 000 20.2201(dl 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (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 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) or in =
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
V. Additional Information
V-19-0048 Maintenance History:
A review of maintenance history revealed that the last work performed on the operating mechanism of VI 9-0048 was in May 1985 when the stem was replaced. The valve was disassembled to correct a seat leakage problem in July 1985. In both of these cases the operator would have been disassembled. Neither of these work orders contains any instructions regarding the setscrew or any mention of problems with the setscrew. The Anchor Darling vendor manual for the valve and operator contains no mention of the locking device for the yoke stem nut in either the disassembly or assembly instructions. The setscrew does appear on the vendor drawing. One other related work order was the replacement of two socket head cap screws that hold the stem housing in place.
Anchor Darling has employed a number of methods to prevent loosening of the yoke sleeve nut. The setscrew as in VI 9-0048 is an early design that was later changed to staking the yoke sleeve nut to the yoke sleeve. Later still, the nut and bevel gear were drilled and a roll pin installed. They were not aware of cases in which the setscrew design actually failed to retain the yoke sleeve nut.
EIIS SVstem and Component Codes:
Low Pressure Coolant Injection System: BO V19-0048 RHR Crosstie Valve, Anchor Darling Valve Company (A391), Model 1889-3 This report is being submitted pursuant to 1 OCFR50.73(a)(2)(i)(B).