05000410/LER-2001-001-01, Reactor Scram Due to Relay Failure in Electro Hydraulic Control Systems

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Reactor Scram Due to Relay Failure in Electro Hydraulic Control Systems
ML021580419
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/02/2002
From: Peckham M
Constellation Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L 2056 LER 01-001-01
Download: ML021580419 (5)


LER-2001-001, Reactor Scram Due to Relay Failure in Electro Hydraulic Control Systems
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation

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)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
4102001001R01 - NRC Website

text

P.O. Box 63 Lycoming, New York 13093 Constellation Nuclear Nine Mile Point Nuclear Station A Member of the May 2, 2002 Constellation Energy Group NMP2L 2056 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:

Nine Mile Point Unit 2 Docket No. 50-410 NPF-69

Subject:

Licensee Event Report 01-001, "Reactor Scram Due to Relay Failure in Electro Hydraulic Control System" Gentlemen:

In accordance with 1 OCFR50.73(a)(2)(iv)(A), we are submitting Supplement 1 to Licensee Event Report (LER)01-001, "Reactor Scram Due to Relay Failure in Electro Hydraulic Control System," dated July 17, 2001. Supplement 1 revises item 2 of Section IV, titled "Corrective Actions," of LER 01-001. This revision reflects a change in the commitment to add parallel contacts for relay KT106 by the end of refueling outage number 8 (RFO8). Instead of adding parallel contacts to the existing relay, a relay with contacts of an alternate, more reliable design was installed during RFO8.

Very truly yours, Mci F. Peckham Unit 2 Plant General Manager MFP/IAAijm Attachment cc:

Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Records Management

NRC FC'M 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31504104 EXPIRES 630-2001 (1-2001)

, the NRC may not conduct or sponsor, digits/characters for each block) and a person is not required to respond to, the information collection.

FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Nine Mile Point, Unit 2 05000410 IOF 4 TITLE (4)

Reactor Scram Due to Relay Failure in Electro Hydraulic Control System EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR ACILITY NAME DOCKET NUMBER NUMBER NO 05000 05 16 2001 2001 -

001 -

01 05 02 2002 ACILITY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply) (11)

MODE(9) 1 20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)

POWER 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL (10) 090 20.2203(a)(1) 50.36(c)(1)(i)(A)

X 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)

'3N0'_ W

_ 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)

OTHER

.~i' N

'N~'m~q~specify in Abstract below 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 Fom, 366A) (17)

V. Additional Information

1.

Failed Components Relay KT1 06, Agastat 125VDC relay, Manufactured by Agastat, Part Number 117D9900G0001

2.

Previous similar events

None

3.

Identification of components referred to in this Licensee Event Report Components IEEE 805 System ID IEEE 803A Function Recirculation System AD N/A Reactor Protection System JC N/A Feedwater System SJ N/A Electro Hydraulic Control System TG N/A Main Steam System SB N/A Containment Isolation System JM N/A Turbine Bypass Control System JIl N/A Emergency Core Cooling Systems BG,BM,BO N/A Residual Heat Removal System BO N/A Isolation Cooling System BN N/A Control Rod Drive System AA N/A Valve AD,SB FCV Valve SJ LCV Valve BO SMV Valve SB,JI ISV, RV Relay TG RLY Contact TG N/A Pump SJ P

Control Rod AC ROD I