ML20149L237

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Correction to Amend 215 to License DPR-62.Incorrect Value Was Introduced Into TS by Typo in Subj Amend.Ts 4.5.1.b Was Not Subj of Amend
ML20149L237
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 07/29/1997
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20149L241 List:
References
NUDOCS 9707310215
Download: ML20149L237 (1)


Text

' '". EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked sealed, or otherwise secured in position. is in its correct position.

b.

At least once per 92 days, by verifying that the system develops a flow of at least 4250 gpm for a system head corresponding to a reactor pressure = 1000 psig when steam is being supplied to the turbine at 1000. +20. -80, psig.

c.

At least once per 18 months by:

1.

Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency o>erating sequence and verifying that each automatic valve in tie flow path actuates to its correct position. Actual injection of coolant into the reactor vessel is excluded from this test.

~

2.

Verifying that the system develops a flow of at least 4250 gpm for a system head corresponding to c reactor pressure of = 165 psig when steam is being supplied to the turbine at 165.

15.

psig.

3.

Verifying that the suction for the HPCI system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank low water level signal or suppression pool high water level signal.

4.

Verifying that the ECCS RESPONSE TIME for the HPCI system is within its limit.'

' Instrumentation response time may be assumed to be the design instrumentation response time.

9707310215 970729 DR ADOCK 050 34 BRUNSWICK - UNIT 2 3/4 5-2 Amendment No. 215 l

REVISED BY NRC LETTER DATED JULY 29, 1997 L