ML20080K811

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Submits Annual Rept of Challenges to Pressurizer Power Operated Relief or Safety Valves,In Accordance W/Ts 6.9.1.4 & 6.9.1.5.b.One Challenge to Pressurizer PORVs Occurred at BVPS Unit 1 During Period of Jan-Dec 1994
ML20080K811
Person / Time
Site: Beaver Valley
Issue date: 02/17/1995
From: George Thomas
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9503010320
Download: ML20080K811 (2)


Text

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.._f Beaver Valley Power Station Shippingport. PA 15077-0004 i

(412) 393-5206 (412) 643-8069 FAX GEORGE S. THOMAS Division Vice President nuctear services February 17, 1995 Nuclear Power Divisnan U.

S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Annual Report of All Challenges to the Pressurizer Power Operated Relief or Safety Valves This report is submitted in accordance with the Beaver Valley Power Station Unit Nos. 1 and 2 Technical Specifications 6.9.1.4 and 6.9.1.5.b.

Unit 1:

There was one challenge to the pressurizer power operated relief valves (PORVs) at Unit 1

during the period of January 1, 1994, to December 31, 1994.

Date:

July 28, 1994 Plant Conditions:

Mode 4,

Reactor Coolant System (RCS) pressure was indicating 370 psig from pressure transmitter PT-RC-402 and 400 psig on PT-RC-403.

The overpressure protection system (OPPS) was in service.

A cooldown to Mode 5 was in progress.

Summary:

Pressurizer power operated relief

valvo, PCV-RC-455C, with a

nominal OPPS relief setpoint of 405

psig, momentarily opened during start of the "A"

residual heat removal pump due to a

pressure increase following the pump start.

The pressure transmitter which supplies the OPPS signal was within 5 psi of the setpoint'and upon the start of the pump, the pressure increase was sufficient to cause opening of PCV-RC-455C.

There were no challenges to the pressurizer safety valves during the period.

9503010320 950217 PDR ADOCK 05000334 fk 9

R PDR

F ~

_f B50 ar Valley Powsr Station, Unit No. 1 and No.

2.

' Annual Report of All Challenges to the Pressurizer' Power F

Operated Relief or' Safety Valves Page 2 Unit 2:

There were no challenges to the pressurizer safety or power operated relief. valves at Unit 2

during 'the period of January 1, 1994, to j

December 31, 1994.

Sincerely, i

f qcd ey George S. Thomas-t cc:

Mr.

L. W.

Rossbach, Sr. Resident Inspector Mr.

T. T. Martin, NRC Region I Administrator l

Mr.

G.

E.

Edison, Project Manager r

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