ML19211A222

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Response to Fifth Set of Interrogatories.Submits Info Re Cost/Benefit of Const Crossing at Allens Creek & Use of High Flux Signal Rather than High Pressure Signal for Initiating Reactor Scram
ML19211A222
Person / Time
Site: Allens Creek File:Houston Lighting and Power Company icon.png
Issue date: 12/06/1979
From: Sohinki S
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Doherty J
AFFILIATION NOT ASSIGNED
Shared Package
ML19211A217 List:
References
NUDOCS 7912170215
Download: ML19211A222 (3)


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UNITED STATES OF AMERICA 12/6/79 NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD, In the Matter of HOUSTON LIGHTING & POWER COMPANY Docket No. 50-466 (Allens Creek Nuclear Generating

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Station, Unit 1)

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NRC STAFF'S RESPONSES TO JOHN F. DOHERTY'S FIFTH SET OF INTERROGATORIES The NRC Staff responds as follows to the fifth set of interrogatories pro-pounded by John F. Doherty to the Staff in the captioned proceeding:

1.

(With regard to Interrogatory #1 of rqy Third Set), that said:

In the event Applicant is granted a pemit to construct two pemanent box culverts and a temporary low water crossing approximately 3 miles northeast from Wallis, Texas, by the U.S. Amy Corps of Engineers, will the money expended on the project be credited toward the cost-benefit when the final siting determination is made?

The Corps of Engineers erred:

the crossing is approximately 3 miles north-west from Wallis. The crossing is of Allens Creek and the purpose of this is a construction access road, as can be seen from the attached sheet, which is from Applicant's application to the Corps of Engineers of Galveston.

Response

The construction activity described, a construction road / railroad crossing of Allens Creek, requires Corps of Engineers approval, and it is nomal for an applicant to obtain permits of this type in advance of final NRC action.

Actual construction of this crossing would not be permitted (see 10 CFR Part 50.10) until such time as a Limited Work Authorization or Construction Permit were issued by the Commission. Consequently, no money will be expended 7912170j /5 1591 062

. by the Applicant on this construction activity until after a final deter-

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mination as to site suitability has been made.

2.

Is Applicant required to put amendments No. 37 and No. 50 in the copy of the Preliminary Safety Analysis Report (PSAR) with the copy of the PSAR in the Houston Public Library? Currently these are not located there, but they are mentioned in Supplement No. 2 of the SER?

Response

No. However amendments No. 37 and No. 50 should be in the NRC's Local Public Document Room, Sealy Public Library, 415 Main Street, Sealy, Texas 77474.

3.

Referring to Sec. 5.2.2(2)(2) on p. 5-3 of Supplement No. 2 of the SER, does the Staff maintain a high flux signal rather than a high pressure signal is superior for initiating reactor SCRAM? If so, why is it superior in these circumstances? If not superior, what dictates its use instead of a high pressure signal?

Response

No.

Instead of relying on one signal which is the "best," or " superior "

page 5-2 of Supplement No. 2 to the SER indicates that scrams from valve position, neutron flux and high pressure signals are provided. As stated on page 5-3 the Applicant has not confirmed that the pressure signal scram will limit the pressure to less than 110 percent of the design pressure for an overpressure transient event starting from an operating pressure of 1G45 pounds per square inch gauge. As stated there, even if confirmation is not forthcoming, the overpressure protection system is still acceptable because either of other two diverse signals, i.e., valve position and flux signals, will limit the pressure to less than 110 percent of operating 1591 063

. pressure assuming both the high pressure and the other diverse signal do not function.

If the pressure signal is later confirmed to provide the requisite protection, all three signals would each individually be capable of providing the requisite protection.

4.

What required the reduction in number of pressure relief valves since Supplement No. 1 of the SER?

Response

There has been no reduction in the number of safety relief valves since Supplement No.1 to the SER as is demonstrated by a comparison of Section 5.2.2 of Supplement No. 2 with Section 5.2.2 of Supplement No.1.

The earlier reduction from 22 to 19 was, as is stated in Section 5.2.2 of Supplement No.1, for Applicant optimization of space utilization within the drywell and was not required by licensing considerations.

1591 064 Dated at Bethesda, Maryland, this 6th day of December,1979.

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