ML20151Y715

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Forwards List of 10CFR50.62 Design Changes & Addl Info as Requested by Nrc.Specific Info Discussed During Telcon in May 1988
ML20151Y715
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/23/1988
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808290011
Download: ML20151Y715 (4)


Text

.* s e-TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place AUB 231988 U.S. Puclear Regulatory Contnission ATTN: Document Control Desk Washington, D.C. 20555 centlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAll NUCLEAR PLANT (SQN) - 10 CFR 50.62 DESIGN CitANCES

References:

1. Letter from TVA to B. J. Youngblood, NRC, dated February 17, 1987, "Sequoyah Nuclear Plant - 10 CFR 50.52 -

Plant-Specific Details"

2. Letter from TVA to NRC dated July 6, 1988, "Sequoyah Nuclear Plant (SQN) - 10 CFR 50.62 - Schedule For Compliance"
3. Letter from C. E. Rossi, NRC, to L. D. Butterfield, ATWS Subcommittee, dated July 7, 1986, "Acceptance for Referencing of Licensing Topical Report" TVA previously provided NRC with plant-specific details regarding compliance with 10 CFR 50.62 (reference 1). The schedule for compliance with 10 CFR 50.62 was provided in reference 2. The plant-specific design information was discussed with NRC in a telephone confe ence call held in May of this year. NRC requested additional information to complete the review of the SQN design. Enclosure 1 contains the additional information requested by HRC for all items except the qualification of safety-related to non-safety-related interfaces.

NRC requested that TVA provide identification of all class 1E to non-class IE interfaces from the sensor outputs to the final actuation devices. Furthermore, NRC requested that TVA identify the specific methods used for isolation in the anticipated transient without scram mitigation system actuation circuits (AMSAC) design and to establish that these isolators conform to the requirements of isolation devices as specified in appendix A of reference 3. 1towever, because of extensive contract file research and coordination with vendors required to adequately address this item TVA will supply this information to NRC by September 30, 1988.

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An Equal Opportunity Employer

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. U.S. Nuclear Regulatory Commission

/\ 8 231988 Summary statements of commitments contained in this submittal are provided in enclosure 2. Please direct questions concerning this issue to B. A. Kimsey at (615) 870-6847.

Very truly yours, TENN 'E V AUTHORITY R. Cridley, Man ger Nuclear Licenslig and Regulatory Affairs Enclosures cc (Enclosures?.:

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 i

, f ENCLOSURE 1 SQN 10 CFR 50.62 DESIGN CHANGES

1. Logic power supplies - The AMSAC design will be revised to provide a logic power supply that is independent of reactor protection system (RPS) power. The power supply will be derived from an uninterruptible non-class

'- IE source.

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2. Operating bypass - The C-20 permissive will have no interface with the - --

(%j RPS. The C-20 setpoint of 360 seconds and associated time delay specified

-J in WCAP-10858P-A, revision 1, will be used. It will be armed at 40 g

. percent of nominal power and above (in accordance with revision 1 of gyp WCAP-10858P-A) rather than 70 percent as specified in revision 0 of

(}JT S;l WCAP-10858P-A.

'M Means for bypassing - Whereas the AMSAC design employs the use of

'hl9% 3.

< 9 maintenance bypass test switches, it will not ba necessary to lift leads,

. (C pull fuses, trip breakers, or physically block relays to achieve required maintenance. Maintenance and testing will be acedmplished utilizing petv.anently mounted handswitches.

4. Electrical independence - This item requires identification of all class IE to non-class 1E interfaces from sensor outputs to final actuation devices. The specific methods for isolation must be identified, and conformance to appendix A of the NRC safety evaluation report (SER)

(reference 2) established.

Note: Because of extensive contract file research and vendor coordination required to address this item TVA's input will be provided to URC September 30, 1988.

5. Safety-related interface - Electrical interfaces will be reviewed to identify all class 1E to non-class 1E interfaces. The class IE to non-clacs 1E isolators will be reviewed to verify their qualification according to AKSAC SER requirements. l l
6. Testability at power - Sensor to output testing will be required to be perforced af ter installation and overy refueling outage. The AMSAC control circuitry will be tested up to and including the associated actuation relays. Existing test procedures will be used to test associated turbine trip circuits and auxiliary feedwater start circuits.
7. Loop accuracy calculations will be prepared for determination of required ARSAC setpoints. This documentation will establish any calibration frequency requirements of less than 18 months.

.  ? ENCLOSURP 2 COMMITMENT LIST

1. TVA will revise its AMSAC design to provide a logic power supply that is independent of the RPS. The power supply will be revised to be from an uninterruptible non-class 1E' source.
2. TVA will identify all class 1E to non-class IE interfaces from the sensor outputs to the final actuation devices in the SQN AMSAC design. TVA will - -~

also identify the specific methods used for providing isolation between the class 1E and non-class 1E interfaces and verify that these isolation devices conform to the requirements provided in appendix A of the NRC SER regarding the W AMSAC generic design package. This information will be provided to NRC by September 30, 1988.

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