ML18030B321

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Forwards Response to 860310 Request for Addl Info Re Hydrogen Recombiner Capability.Mod Planned to Provide Alternate Supply of Nitrogen to Drywell Control Air Sys,Per Generic Ltr 84-09
ML18030B321
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/13/1986
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To: Muller D
Office of Nuclear Reactor Regulation
References
GL-84-09, GL-84-9, TAC-55953, TAC-55954, TAC-55955, NUDOCS 8605200258
Download: ML18030B321 (8)


Text

ACCESSION NBR:

FACIL'0-259 50-260 50-296 AUTH. NAl'lE GRXDLEY> R. L.

RECIP. NAME MULLER>D. R.

REGULA Y INFORMATION'ISTRIBUTI SYSTEM (RXDS) 8605200258 DQC. DATE: 86/05/13 NOTARIZED:

NO DOC)(ET 4 Browns Ferry Nuclear Power Stati on> Unit i. Tennessee 05000259 Browns Ferry Nuclear Power Station>

Unit 2>

Tennessee 05000260 Browns Ferry Nuclear Power Station>

Unit 3>

Tennessee 05000296 AUTHOR AFFILIATION Tennessee Valley Authority RECIPXENT AFFILIATION BWR Prospect Directorate 2

SUBJECT:

Forwards response to 860310 request for addi info re hydrogen rec omb incr capab i 1 itg. Mod planned

.to provi de alternate supply of nitrogen to drgwell control air sos> per Generic Ltr 84-09.

DISTRIBUTION CODE:

A001D COPXES RECEIVED: LTR ENCL SX ZE:

TITLE:

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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place May 13, 1986 Director of Nuclear Reactor Regulation Attention:

Mr. D. R. Huller, Project Director BWR Project Directorate No.

2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Muller:

In the Matter of the Tennessee Valley Authority Docket Nos.

50-259 50-260 50-296 By letter from M. Grotenhuis (NRC) to S. A. White dated March 10,

1986, we received a request for additional information regarding hydrogen recombiner capability at the Browns Ferry Nuclear Plant.

Our response to that request is enclosed.

If you have any questions, please get in touch with us through the Browns Ferry Project Manager.

Very truly yours, TENNESSEE VALLEY AUTHORITY Enclosure cc (Enclosure):

Hr. R. J. Clark U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue

Bethesda, Maryland 20814 R. L. Gridley, Director Nuclear Safe y and Licensing U.S. Nuclear Regulatory Commission Region II ATTN:

Dr. J.

Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 860gppo~

.P OCg D~ap I DR gg 8 8605g3 PbR t,,'l An Equal Opportunity Employer

(,o~

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ENCLOSURE

Response

to Request for Additional Information Hydrogen Recombiner Relief Browns Ferry Nuclear Plant (BFN)

Units 1, 2, and 3

Item 1 Based on your July 2, 1984 reply to Generic Letter 84-09, the possibility exists that valve 32-332 (Ref:

FSAR Fig. 10.14-4),

backup air supply cutout valve, might be open during the course of a LOCA.

This could occur as"a result of'having been left open following a prior maintenance procedure or as a result of a deliberate action due to a loss of drywell air compressor operability.

Describe any administrative controls, presently in effect, or planned, which assures that when 32-332 is open, and primary containment integrity is

required, the control room operators will close this valve in the event of a LOCA.

Verify whether this valve can be closed from the control room or locally.

Include in your response a discussion of the anticipated timing of the necessary operator actions.

R~es esse A modification is planned which will provide an alternate supply of nitrogen to the drywell control air system.

This modification will eliminate the need to use air as a pneumatic supply when primary containment integrity is required and will obviate the above concern.

The modification is required to meet 10 CFR 50, Appendix R and will be completed on each unit prior to startup.

Item 2

The control nitrogen system, which supplies systems inside containment, utilizes recycled containment atmosphere during normal operation.

However, an air supply system is used as a backup to the control nitrogen system.

Additionally, the isolation provisions (penetration X-22) used for the normal nitrogen supply and the backup air supply systems consist of two check valves, one located on each side of the containment.

This arrangement does not comply with the 10 CFR 50, Appendix A, GDC 56, requirements (i.e. sole use of vacuum breakers for isolation).

Provide the following information:

a.

The procedures and instrumentation available to the operators to be used to meet the intent of Criterion 3 of Generic Letter 84-09 if the backup air supply is in use when the LOCA occurs.

b.

The means by which the operator would become aware that operation of the backup air system may have filled the accumulators with air.

C.

The philosophy used to demonstrate compliance with the requirements for use of vacuum breakers as isolation valves contained in 10 CFR 50, Appendix A, GDC 56.

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Upon completion of the modification discussed in response to Item 1, Browns Ferry will be in compliance with Criterion 3 of Generic Letter 84-09.

b.

The volume of the accumulators relative to that of containment is small enough such that even if they were completely filled with air their contribution to de-inerting the containment is insignificant.

Co The licensing basis for BFN, as reflected in the FSAR, does not prohibit the use of two check valves as automatic isolation valves.

The requirements for containment isolation valves are described in section 5.2.3 of the FSAR.

Also, Appendix A of the FSAR compares BFN's design basis-to the proposed AEC design criteria which existed at the time of our application for license.

These criteria did not prohibit the use of check valves as automatic isolation valves.

The use of check valves to isolate influent lines is common practice throughout the industry and is within BFN's licensing basis.

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