ML20062B178

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Forwards Responses to Questions Re Proposed Changes to Tech Specs Submitted on 780322
ML20062B178
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/10/1978
From: Gilleland J
TENNESSEE VALLEY AUTHORITY
To: Ippolito T
Office of Nuclear Reactor Regulation
References
NUDOCS 7810230244
Download: ML20062B178 (6)


Text

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T:D!ilESSIE ' it.' E'/ AUT HC R ;'.^f c; m mom Tcv 4 r2,c:: 37e 830 Power Building OCI10jg7,3 Director of Nucicar Reactor Regulation

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At.tention:

Mr. Thomas A. Ippolito, C' t..f Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Comnission Washington, DC 20555

Dear Mr. Ippolito:

In the Matter of the

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Docket Nos. 50-259 Tennessee Valley Authority

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50-260 50-296 This is in response to verbal questions from your staff concerning proposed changes to the technical specifications of Browns Ferry Nuclear Plant units 1, 2, and 3 sutenitted by a letter from James P. Darling to Edson C. Casa dated March 22,1978 (TVA EFNP TS 107).

Our response to those verbal questions is provided as an enclosure to this letter.

Very truly yours,

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/J.E.C111 eland Assistant Manager of Power Subscribed,and sworn to before me this >Lidayof(' /(

1978.

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Y Rotary Public v

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My Consnission Expires 8/ J ~--

Enclosures cc (Enciesures):

Mr. Charles R. Christopher Chairman, Limestone County Connaission P.O. Box 188 Athens, Alabama 35611 Dr. Ira L. Myers State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 lI/O%30 EW t.

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ENCLOSURE Attachments:

1.

CE f[ementary Diagram 730E928 Sheet 2 (in part).

2.

Results of STI Program - HPCI Testing 3.

Results of STI Program - 1;CIC Testing NRC Roestion Document the three second time delay in the HPCI high steam flow isolation logic.

TVA Response browns Ferry FSAR Figure 7.4-la shows the flow instrumentation

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dPIO-23-76 and dPIS-23-77.

GE elementary diagram 730E928, sheet 2 (Attachment 1) shows that the high differential pressure signal must go through time delay relay 23A-K53, which is set at three seconds.

c This relay energizes the necessary contacts to cause valve motors to l

close the valves.

NRC Question Determine whether the steam throttle valve goes wide open during MPCI i

startup.

TVA Response The steam throttle valve does not fully open during HPCI startup.

During the first twelve seconds the valve is gradually opened at a controlled ramp increase to the anticipated nornal operating position.

At this point automatic flow control takes over, but since flow is near the rated flow at that time, the valve will not spring wide open.

NRC Question Verify that TVA has tested the worst case in which steam flow would reach its highest possible value.

l TVA Rcsponse The Startup Test Instruction (STI) program used to test the HPCI and RCIC systens was developed by General Electric and was intended to cover all I

expected operational modes and was approved by the then AEC. The various startup conditions that were covered are outlined in STI numbers 14 l

and 15, sections 6.1.1, 6.1.2, 6.1.3, 6.1.4, and 6.2.

The various possibilities for encountering a high steam flow were thus considered to be adequately covered. Test 6.2 was found to be the worst case for HPCI startup, and tests 6.1.3 and 6.1.4 seem to be the worst case for RCIC.

For t ehulation of actual steam flow rate values, see Attachmerts 2 and 3.

NRC Question Determine how close the steam flow came to the setpoint during this Worst Case.

TV) Response Attachments 2 and 3 are a summary of startup test data on HPCI and RCIC.

Included in this data is the worst case for steam flow. One may compare the llPCI setpoint of 90 psid and the RCIC setpoint of 442 inches of water pressure differential to the data to see how far the systems operate from these setpoints. The values of cone.irn Sere are the steady state steam flow values. In the case of !!PCI, the peak steam flow rate may exceed the setpoint, but initiation is prevented by the 3-second time delay.

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