ML19290B864

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Responds to Re Containment Purging & Venting During Normal Operation.Forwards Commitment to Operate in Conformance W/Nrc Interim Position for Containment Purge & Vent Valve Operation
ML19290B864
Person / Time
Site: Browns Ferry  
Issue date: 12/10/1979
From: Cross J
TENNESSEE VALLEY AUTHORITY
To: Harold Denton, Ippolito T
Office of Nuclear Reactor Regulation
References
NUDOCS 7912140273
Download: ML19290B864 (5)


Text

a TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 500A Chestnut Street Tower II DEC 101979 Director of Nuclear Reactor Regulation Attentiout Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555 Dear Mr. Ippolitot In the Matter of the

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Docket Nos. 50-259 Tennessee Valley Authority

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50-260 50-296 In response to your letter dated October 22, 1979, to H. G. Parris regarding containment purging and venting during normal operation, we are submitting our comitment to operate the Browns Ferry Nuclear Plant units 1, 2, and 3 in conformance with the interim position provided as an enclosure to your letter. In addition, we are reevaluating purge valve operability and studying our valves using the guidance provided as the enclosure to the September 27, 1979, letter from D. G. Eisenhut to All Light Water Reactors regarding containment purging and venting during normal operation-guidelines for valve operability. Information regarding the necessity for limited purge capability during hot conditions and our analytical basis for satisfactory valve performance under DBA-LOCA conditions was presented in our letters dated March 1, 1979, and June 12, 1979, and during our meeting with the NRC staff and consultants on June 1, 1979.

Based on our enclosed comitment to operate in conformance with the NRC's interim position, continued operation of the Browns Ferry Nuclear Plant is justified and the operating licenses for Browns Ferry units 1, 2, and 3 should not be modified, suspended, or revoked.

Very truly yours, TENNESSEE VALLEY AUTHORITY 5 tw

'1 immy ross Executive Assistant to the Manager of Power Subscribed and sworn to before me this, /fl day of f )(6 1979.

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b 2f3 Enclosure v 912140 An Equal Opportunity Employe

ENCLOSURE COMMITMENT TO OPERATE IN CONFORMANCE WITH INTERIM POSITION FOR CONTAINMENT PURGE AND VENT VALVE OPERATION BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, 50-260, 50-296) 1.

NRC POSITION Whenever the containment integrity is required, emphasis should be placed on operating the containment in a passive mode as much as possible and on limiting all purging and venting times to as low as achievable.

To justify venting or purging, there must be an established need to improve working conditions to perform a safety related surveillance or safety related maintenance procedure.

(Examples of improved working conditions would include deinerting, reducing temperature, humidity, and airborne activity sufficiently to permit efficient performance or to significantly reduce occupational radiation exposures.)

TVA RESPONSE Whenever containment integrity is required, TVA will emphasize the need to minimize purging operations.

Our present technical specifi-cations already restrain purge operations to a large extent. Purging will be performed only to provide a suitable atmosphere for personnel engaged in safety-related activities or maintenance in the containment.

At Browns Ferry Nuclear Plant there are no routine surveillance tests that require containment entry. Normally, all containment entries during hot reactor conditions are performed for safety-related maintenance, or in the support of safety activities. Following entries, the containment must be reinerted as required by technical specifications.

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2.

NRC POSITION Maintain the containment purge and vent isolation valves closed whenever the reactor is not in the cold shutdown or refueling mode until such time as you can show that:

a.

All isolation valves greater than 3" nominal diameter used for containment purge and venting operations are operable under the most severe design basis accident flow condition loading and can close within the time 'imit stated in your Technical Specifications, design criteria or operating procedures. The operability of butterfly valves may, on an interim basis, be demonstrated by limiting the valve to be no more than 30*

to 50* open (90" being full open). The maximum opening shall be determined in consultation with the valve supplier.

The valve opening must be such that the critical valve parts will not be damaged by DBA-LOCA loads and that the valve will tend to close when the fluid dynamic forces are introduced.

TVA RESPONSE TVA will limit the disc opening of the containment purge valves greater than 3" diameter to 50* open, pending resolution of the generic operability issue. We expect to complete the modification on all three units by May 1, 1980. We are also reevaluating the operability analysis with the additional emphasis placed on considerations stated in NRC's September 27, 1979, letter.

The manufacturer of the Browns Ferry valves was Rockwell-Edwards.

Rockwell no longer manufactures butterfly valves, and the engineering sections associated with the butterfly valves were disbanded. TVA has held consultations with several valve vendors to determine the effects of dynamic torques on our valves.

Based on these discussions, particularly with Henry Pratt and Continental Fisher Valve Companies, TVA still firmly believes that our symmetric disc butterfly valves do not experience torque reversal during valve closure that can be found with offset disc valves.

TVA also believes that the valves are structurally adequate to withstand closing loads produced by DBA 1579 I37

. fluid flow regardless of initial disc angle.

Nonetheless, for the sake.of conservatism, TVA will modify the subject valves to be no more than 50* open. This angular setting is acceptable based on the above-mentioned discussions with valve vendors.

NRC POSITION b.

Modifications, as necessary, have been made to segregate the containment ventilation isolation signals to ensure that, as a minimum,at least one of the automatic safety '7jection actuation signals is uninhibited and operable to initiate valve closure when any other isolation signal may be blocked, reset, or overridden.

TVA POSITION A review of Browns Ferry containment ventilation systems indicates that there is only one case involving the Containment Atmosphere Dilution (CAD) system post-LOCA controls where our design deviates from the above position.

The CAD system is designed to permit the operator to vent containment atmosphere through a 2" line to standby gas treatment systcm after a LOCA.

In the event of failure of the preferred vent line, a secondary backup 2" path can be established by opening an inboard containment ventilation isolation valve and a downstream valve in a second 2" line. This safety system is designed to provide long-term post-LOCA venting of the containment to prevent overpressurization and for combustible gas control.

It is imperative that these CAD controls be operable even in the simultaneous presence of all PCIS trip signals.

The CAD switches are keylock type, and their use is administrative 1y restricted, being used briefly for required monthly surveillance testing of the CAD system. Note that the main containment purge outboard i579 138

valves cannot be opened using the CAD switches.

TVA, in response to NRC concerns stated during the June 1, 1979, meeting concerning testing of the CAD switches during operation, has submitted a proposed technical specification change to limit testing of the CAD override switches to cold conditions. We understand that this change has recently been approved.

The CAD system performs a primary safety function after a LOCA. The modifications proposed by the NRC reduce the reliability of the system to perform its function and increase the number of actions an operator must take to initiate CAD system operations. TVA believes that making this change will not enhance public safety during normal operation, but rather reduces the plant's ability to cope with a LOCA and is, therefore, detrimental to safety.

We ask that NRC consider the CAD system logic design as a necessary exception to the 2.b. interin position.

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