ML20205F082
| ML20205F082 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/29/1985 |
| From: | Wisenburg M HOUSTON LIGHTING & POWER CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205F085 | List: |
| References | |
| CON-#485-016, CON-#485-16 OL, ST-HL-AE-1486, NUDOCS 8511040333 | |
| Download: ML20205F082 (8) | |
Text
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The Light Company n-u a%mm m m,x noo n-mxanoi m3>m.mn s
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October 29, 1985 ST-HL-AE-1486 File No.: G9.17 Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Responses to DSER/FSAR Items Renarding Ouestion 32.31
Dear Mr. Knighton:
The attachments enclosed provide STP's response to Draft Safety Evaluation Report (DSER) or Final Safety Analysis Report (FSAR) items.
The item numbers listed below correspond to those assigned on STP's internal list of items for completion which includes open and confirmatory DSER items, STP FSAR open items and open NRC questions.
This list was given to your Mr. N. Prasad Kadambi on October 8, 1985 by our Mr. M. E.
Powell.
The attachments include mark-ups of FSAR pages which will be incorporated in a future FSAR amendment unless otherwise noted below.
The items which are attached to this letter are:
Attachment Item No.*
Subject 1
QO32.031-1 Detailed cable routing diagrams Note:
These drawings vill not be incorporated into the FSAR.
8511CMO33G 851029 PDR ADOCK 050 8
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- Legend g
D - DSER Open Item C - DSER Confirmatory Item i
F - FSAR Open Item Q - FSAR Question Response Item
{ (9 Ll/DSER/aay i
Houston Lighting & Power Company ST-HL-AE-1486 File No.: C9.17 Page 2 If you should have any questions concerning this matter, please contact Mr. Powell at (713) 993-1328.
Very truly yours, A
M. R. Vi burg Manager, Nuclear Lice}s; Lng s
CAA/bl Attachments:
See above L1/DSER/aay
ST-HL-AE-1486 File No.: C9.17 Page 3 cc:
Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Division of Licensing Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 Robert D. Martin Lanny A. Sinkin Regional Administrator, Region IV 3022 Porter Street, N.W. #304 Nuclear Regulatory Commission Washington, DC 20008 611 Ryan Plaza Drive, Suite 1000 i
Arlington, TX 76011 Oreste R. Pirfo, Esquire Hearing Attorney N.'Prasad Kadambi, Project Manager Office of the Executive Legal Director U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission l
7920 Norfolk Avenue Washington, DC 20555 Bethesda, MD 20814 Charles Bechhoefer, Esquire i
Claude E. Johnson Chairman, Atomic Safety &
Senior Resident Inspector /STP Licensing Board c/o U.S. Nuclear Regulatory.
U.S. Nuclear Regulatory Commission Commission Washington, DC 20555 P.O. Box 910 Bay City, TX 77414 Dr. James C. Lamb, III 313 Woodhaven Road M.D. Schwarz, Jr., Esquire Chapel Hill, NC 27514 i
Baker & Botts One Shell Plaza Judge Frederick J. Shon Houston, TX 77002 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission J.R. Newman, Esquire Washington, DC 20555 Newman & Holtzinger, P.C.
1615 L Street, N.W.
Mr. Ray Goldstein, Esquire Washington, DC 20036 1001 Vaughn Building 807 Brazos Director, Office of Inspection Austin, TX 78701 and Enforcement U.S. Nuclear Regulatory Commission Citizens for Equitable Utilities, Inc.
Washington, DC 20555 c/o Ms. Peggy Buchorn Route 1, Box 1684 E.R. Brooks /R.L. Range Brazoria, TX 77422 Central-Power & Light Company P.O. Box'2121
- Docketing & Service Section Corpus Christi, TX 78403 office of the Secretary i
U.S. Nuclear Regulatory Commission H.L. Peterson/G. Pokorny Washington, DC 20555 City of Austin (3 Copies)
.P.O. Box 1088 Austin, TX 78767 Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission J.B. Poston/A. vonRosenberg 1717 H Street City Public Service Board Washington, DC 20555 P.O. Box 1771 San Antonio, TX 78296 Revised 9/25/85 All without attachments, except as Ll/ DEER /asy noted by *
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ATTACHMENT I ST-HL-AE-gf6 AGE I iq STP FSAR
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Question 032.31 Describe the design basis, and separation and isolation for -
(a) Reactor Trip on Turbine Trip circuitry. Also, provide detailed cable routing diagrams for this trip circuitry from the sensor in the turbine build-ing to the final actuation located in the Reactor Trip System.
(b) The circuitries from Reactor Trip System to the BOP devices in the Tur-bLne/ Auxiliary Building.
Response
Part a) 43 The reactor trip on turbine trip is an " anticipatory trip".
The reactor trip on turbine trip provides additional protection and conserva-tism beyond that required for the health and safety of the public.
The signal is derived from redundant limit switches on each turbine steam stop 26 valve and from redundant controls on three pressure switches that monitor the turbine emergency trip fluid pressure.
Figure 7.2-17 shows the functional diagram and Section 7.2.1.1.3, item 6 describes the design basis for this reactor trip. The limit switches and pressure switches identified above are purchased as Class 1E qualified equipment.
l43 These limit switches and pressure switches are located in the nonseismically qualified Turbine Generator Building (TCB).
Seismic qualification is limited to the mounting of the components at their respective localities, the mounting 26 supports for the rigid steel conduits, and to the components themselves.
Wiring from these devices, located in the TCB, to the Solid-State Protection system (SSPS) cabinets, located in the Mechanical Electrical Auxiliary Build-ing is routed in accordance with the same separation criteria applicable to 43 Protection Channels, I, II, III and IV (as discussed in Section 7.1.2.2 and 8.3.1.4), and is in rigid steel conduit dedicated exclusively for these sig-
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26 Part b)
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The circuitry from the Reactor Trip System to balance-of-plant (BOP) devices in the TCB is limited to the turbine trip on reactor trip.
The turbine trip on reactor trip circuitry is implemented in accordance with 43 IEEE 279 with the following exceptions:
1.
The circuitry is routed through a nonseismic structure.
Q&R 7.2-5 Amendment 49
ATTACHMENI I b
STP FSAR ST HL AE WJ PAGE 1 OFl")
2.
The turbine trip equipment supplied by the turbine manufacturer, although of appropriate high quality, is not seismically or environ-mentally qualified to nuclear qualification standards.
3.
The turbine solenoids are non-Class IE and are powered by highly reliable non-Class 1E power sources.
The circuit design, up to and including the turbine trip solenoids, conforms to those sections of IEEE 279 concerning single failure (Section 4.2), quality (Section 4.3), channel integrity (Section 4.5 excluding seismic), channel independence (Section 4.6), and testability (Section 4.10), so ac to assure 43 adequate reliability.
The turbine trip solenoids are implemented so that the turbine is tripped on loss of control power. Wiring from the SSPS cabinet (located in the Mechanical-Electrical Auxiliary Building (MEAB)) t.o the turbine trip solenoids (located in the TGB) is routed in accordance with the same separation criteria applicable to Class 1E circuits (see Sections 7.1.2.2 and 8.3.1.4) and are in rigid steel conduit dedicated exclusively for these signals to maintain the integrity of the individual radundant trains.
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