05000220/LER-2003-001, From Nine Mile Point, Unit 1 Regarding TS Cooldown Rate Exceeded During Required Cooldown for a Failed Solenoid Actuated Pressure
| ML031880016 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/23/2003 |
| From: | Hopkins L Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMPIL 1742 LER 03-001-00 | |
| Download: ML031880016 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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 |
| 2202003001R00 - NRC Website | |
text
P.O. Box 63 Lycoming, New York 13093 Constella on Energy Group Nine Mile Point Nudear Station June 23, 2003 NMP1L 1742 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Nine Mile Point Unit 1 Docket No. 50-220 License No. DPR-63 Licensee Event Report 03-001, "Technical Specification Cooldown Rate Exceeded During Required Cooldown for a Failed Solenoid Actuated Pressure Relief Valve" Gentlemen:
In accordance with 10 CFR 50.73(a)(2)(iXA) and 10 CFR 50.73(a)(2Xi)(B), we are submitting Licensee Event Report (LER)03-001, "Technical Specification Cooldown Rate Exceeded During Required Cooldown for a Failed Solenoid Actuated Pressure Relief Valve."
Very truly yours, LawrenceA. Hopkins Plant General Manager LAHAKLEJm Attachment cc:
Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 741-2004 (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)
PAGE (
Nine Mile Point, Unit 1 05000220 I OF 4
TITLE (4)
Technical Specification Cooldown Rate Exceeded During Required Cooldown for a Failed Solenoid Actuated Pressure Relief Valve EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR SEQUENiALREV MO DAY YEAR M
ACLITY NAME DOCKET NUMBER NUMBER NO 1
1 1_
j 05000 04 22 2003 2003 -
001 -
00 06 23 2003 FACILTY NAME DOCKET NUMBER OPERATIN THIS REPORT IS 1
05000 OPERATING THtS REPORTfiSUBMItEDPURSUANT TO THE REQUIREMENTS OF 10 ClFR : (Check all that pply) (1t)
MODE (9) 1 20.2201 (b) 202203(a)(3)(Ii) 50.73(a)(2)(iD(B) 50.73(a)(2)(bo)(A)
POWER LEVEL (10) 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iIl) 50.73(a)(2)(x) 000 023 20.2203(a)(1) 50.36(c)(1)Q)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4)
.20.22'(a)(2)l) 250.36(c)(1)Ol(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)(lI) 50.73(a)(2)(v)(C)
Specify In Abstract below or In 20.2203(a)(2)(iv)
X 50.73(a)(2X)((A) 50.73(a)(2)(v)(D)
(If n7mre space Is required, use aditional copies of (If more space Is required, use addional copdes of NRC Form 366A) (17)
IV. Corrective Actions
- 1. Replaced the SOV for ERV-1 11.
- 2.
Measured cut-out switch contact resistance and Inspected contact coating for the remaining five ERVs and cleaned contacts as necessary.
- 3.
The ERV preventive maintenance procedure was revised to include contact resistance measurement.
- 4.
Revised procedure N1-OP-43C, Plant Shutdown, to provide additional guidance for securing steam loads to control cooldown rate.
- 5. Operator training will be provided on this event, Including actions to address excessive cooldown
- 6.
Initiatives are underway to Improve the effectiveness of the corrective action program, as a result of previously identified weaknesses In the corrective action program
V. Additional Information
- 1. Failed Components:
SOV-01-102A Model CR9503-213C Manufacturer General Electric
- 2.
Previous similar events
Licensee Event Report (LER)00-005 discusses a loss of secondary containment due to an inadequate procedure for checking track bay doors closed. The corrective actions are specific to the event. LER 00-002 discusses an instance In which a service water check valve failed a surveillance test due to inadequate preventive maintenance. The corrective actions were specific to check valves. The corrective actions for the events discussed above would not have prevented the ERV-1 11 failure or exceeding the TS allowed maximum cooldown of 100 degrees F In one hour.
- 3.
Identification of components referred to In this Licensee Event Report:
Components IEEE 805 System ID IEEE 803A Function Core Spray BM N/A Automatic Depressurization System SB N/A Reactor Coolant System AD N/A Main Steam System SB N/A Vessel AD RPV Valve SB V, RV Solenoid SB SOL Coil SB CL Switch SB NWA Contacts SB N/A NRC FORM 388A (1.2001)