ML20070D253

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Forwards Addl Info Re Equipment Survivability Per 821209 Telcon Request,Revising 821129 Submittal.Core Exit Thermocouples Located within Pressure Vessel & Not Exposed to Hydrogen Burning
ML20070D253
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/09/1982
From: Kammer D
TENNESSEE VALLEY AUTHORITY
To: Adensam E
Office of Nuclear Reactor Regulation
References
NUDOCS 8212150010
Download: ML20070D253 (2)


Text

r e-4 TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 3'rJo1 400 Chestnut Street Tower II December 9,1982 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Ms. Adensam:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley Authority

)

50-328 In response to a verbal request from Carl Stahle of your staff in a December 9,1982 telephone conversation, enclosed is additional infomation regarding equipment survivability at the Sequoyah Nuclear Plant. This information is being provided to revise the infomation provided in L. M. Mills' November 29, 1982 letter to you.

If you have any questions concerning this matter, please get in touch with Jerry Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY DS W D. S. Kammer 5'uclear Engineer Sworng^pnd subscrMd before me

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Enclosure oc:

U.S. Nuclear Regulatory Commission (Enclosure)

Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 i

8212150010 821209 PDR ADOCK 05000327 P

PDR An Equal Opportunity Employer

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_r ENCLOSURE

- c RESPONSE TO NOVEMBER 19, 1982 VERBAL RFAUEST FOR ADDITIONAL INFORMATION ON BQUIPMENT SURVIVABILITY l

1 This response provides additional information regarding equipment survivability at the Sequoyah Nuclear Plant and is intended to supplement the information provided in the Tennessee Valley Authority's November 1,1982 submittal on the same subject. As agreed per our November 19, 1982 tele phone conversation, clarification of the f ollowing items'is provided; (1) hydrogen recombiners; (2) Barton transmitters; (3) core exit thermocouples; (4) H sample flow control valves; and (5) bounding conditions. Hydrogenrecom$1ners and reactor coolant pressure transmitters will be included as essential equipment required f or the hydrogen burn event based on NRC requirements.

Hydrogen Recombiners:

Survivability of the hydrogen recombiners is discussed in supplement 5 to the Sequoyah Saf ety Evaluation Report (NUREG-0011). The recombiners are included in the NUREG-0588 qualification program and have been qualified to 3098F. The Summary Component Evaluation Worksheets (SCEWs) for the hydrogen recombiners are provided on page 13 of table 3.11-4 in TVA's Electrical Equipment Qualification Report f or unit I at Sequoyah.

Barton Level and Pressure Transmitters:

Barton transmitters are utilized to determine the pressure of the Reactor Coolant System (RCS) and are utilized for level transmitters LT 63-176 through 63-179.

There are different lots of barton transmitters in use at the Sequoyah Nuclear Plant and all have been qualified to temperatures in excess of those anticipated due to hydrogen combustion. Lot 1 transmitters have been qualified to 280'F and are scheduled for replacement by the second refueling outage on each unit. Lot 3 and 4 transmitters are fully qualified for the Sequoyah NUREG-0588 program. All level and pressure transmitters on the list of equipment required to mitigate hydrogen burns are also included in the Sequoyah NUREG-0588 program.

Core Exit Thermocouples:

The core exit thermocouples are located entirely within the pressure vessel and are not exposed to hydrogen burning. An electrical penetration in the pressure vessel head is provided f or the wiring.

1 H2 S*mPlc Flow Control Valves:

Flow control valves FCV 43-201, 202, 207, and 208 have been qualified to 340*F.

Bounding Conditions:

A listing of the equipment which must survive a hydrogen burn and the references for individual SCEWs required in the BQ response to NUREG-0588 was provided in the response to question 1 on TVA's November 1,1982 submittal.

The temperatures listed on the NUREG-0588 SCEWs (with the exception of the RTD and thermocouple cable temperatures) will bound equipment temperatures during hydrogen combustion for the events analyzed. TVA has reviewed the equipment qualification test program, and tho tests are conducted for extended periods of t ime.

Equilibrium surf ace temperatures of equipment tested achieve thermal equilibrium with the test chamber during the test.

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