ML20207C908
| ML20207C908 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/26/1986 |
| From: | Wisenburg M HOUSTON LIGHTING & POWER CO. |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| ST-HL-AE-1826, NUDOCS 8612300276 | |
| Download: ML20207C908 (10) | |
Text
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The Light ShE Uf Ilouston 1.igliting & l'ower l'O. Ilox 1700 llousion,'lexas,4001 (713) 228-921I l
December 26 1986 ST-HL-AE-18$6 File No.: G9.17 Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Revisions to Seismic Category 1 Equipment Qualification Procedure (NSSS Scope)
Dear Mr. Noonan:
I Enclosed is FSAR Table 3.9-10, Safety-Related Seismic Category 1 Equipment Qualification Procedure (NSSS Scope) which has been annotated to reflect changes to the program. The attached pages will be incorporated into a future amendment to the FSAR and are being provided now for the staff's immediate use.
If you should have any questions on this matter, please contact Mr.
M. E. Powell at (713) 993-1328.
Very trul yours, M. k. Wis burg Deputy Pro ect Manage REP /yd
Attachment:
Annotated FSAR pages 3.9-124 through 3.9-129 with inserts.
8612300276 861226 PDR ADOCK 0500 B
A ON L1/NRC/kb i'
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ST-HL-AE-1826
- I 0'*l Ilouston 1.ighting & Power Company cc:
Hugh L. Thompson, Jr., Director T.V. Shockley/R.L. Range Division of PWR Licensing - A Central Power & Light Company Office of Nuclear Reactor Regulation P.O. Box 2121 U.S. Nuclear Regulatory Commission Corpus Christi, TX 78403 Washington, DC 20555 O. Backus/J. E. Malaski Robert D. Martin City of Austin Regional Administrator, Region IV P.O. Box 1088 Nuclear Regulatory Commission Austin, TX 78767 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 J. B. Poston/A. vonRosenberg City Public Service Board N. Prasad Kadambi, Project Manager P.O. Box 1771 U.S. Nuclear Regulatory Commission San Antonio, TX 78296 7920 Norfolk Avenue Bethesda, MD 20814 Brian E. Berwick, Esquire Assistant Attorney General for Robert L. Perch, Project Manager the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station 7920 Norfolk Avenue Austin, TX 78711 Bethesda, MD 20814 Lanny A. Sinkin Dan R. Carpenter Christic Institute Senior Resident Inspector / Operations 1324 North Capitol Street c/o U.S. Nuclear Regulatory Washington, D.C.
20002 Commission P.O. Box 910 Oreste R. Pirfo, Esquire Bay City, TX 77414 Hearing Attorney Office of the Executive Legal Director Claude E. Johnson U.S. Nuclear Regulatory Commission Senior Resident Inspector /STP Washington, DC 20555 c/o U.S. Nuclear Regulatory Commission Citizens for Equitable Utilitiss, Inc.
P.O. Box 910 c/o Ms. Peggy Buchorn Bay City, TX 77414 Route 1, Box 1684 Brazoria, TX 77422 M.D. Schwarz, Jr., Esquire Baker & Botts Docketing & Service Section One Shell Plaza Office of the Secretary Houston, TX 77002 U.S. Nuclear Regulatory Commission Washington, DC 20555 J.R. Newman, Esquire (3 Copies)
Newman & Holtzinger, P.C.
1615 L Street, N.W.
Advisory Committee on Reactor Safeguards Washington, DC 20036 U.S. Nuclear Regulatory Commission 1717 H Street Director, Office of Inspection Washington, DC 20555 and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Ll/NRC/kt.
Revised 12/22/86
ATTACHMENT STP FSAR ST HL AE /fAJe PAGE / OF F TABLE 3.9-10 SAFETY-RELATED SEISMIC 10 CATECORY I EQUIPMENT QUALIFICATION PROCEDURE (NSSS SCOPE)
Safety Seismic Qualification Component Class Procedure Remarks Reactor Coolant System Reactor Vessel 1
Analysis CRDM "
.,i..;a ASSSrwbliOS 1
Analysis 30 CRDM Head Adapter Plugs 1
Analysis Steam Generators (tube side) 1 Analysis (shell side) 2 Analysis Pressurizer 1
Analysis Reactor Coolant Hot and Cold Leg Piping, Supports, Fittings - ' rai.
moilm..
1 Analysis Surge Pipe, Supports, Fittings ;r.d r;L.i a:ima 1
Analysis 30 Crossover Leg Piping, Fittings cr.d F:Erierti;r 1
Analysis RTD "cpass Mar.i.';1i-4-
-A..oly.1.
Pressurizer Safety Valves 1
Analysfs4TCSt Pressurizer Power-operated 30 Relief Valves i
Analysis (Te54 l
Valves of Safety 1 to Safety 2 Interf ace 1
Analysis (TcSI j
Reactor Coolant Pump RCP Casing 1
Analysis Main Flange 1
Analysis Thermal Barrier 1
Analysis Thermal Barrier HX 1
Analysis l 41 l
l
- 1 Seal Housing i
Analysis 3.9-124 Amendment 41
ATTACHMENT ST-HL AE-It STP FSAR PAGE A.0F TABLE 3.9-10 (Continued) 18 SAFETY-RELATED SEISMIC CATEGORY I EQUIPMENT QUALIFICATION PROCEDURE (NSSS SCOPE)
Safety Seismic Qualification Component Class Procedure Remarks Reactor Coolant System (Continued)
- 2 Seal Housing 2
Analysis O
Pressure-Retaining 1
Analysis Bolting 41 RCP Motor Rotor 2
Analysis RCP Motor Shaft and Coupling 2
Analysis Spool Piece 2
Analysis Armature 2
Analysis Flywheel 2
Analysis Motor Bolting 2
Analysis Applies only to bolting involved with coastdown function Motor Stand 2
Analysis 41 Motor Frame 2
Analysis Bearings (upper thrust) 2 Analysis Upper Oil Cooler Reservoir (tube side) 3 Analysis (shell side) 3 Analysis Lower Oil Cooler Reservoir 30 (tube side) 3 Analysis (shell side) 3 Analysis Oil Cooler Piping 3
Analysis 55 I
3.9-125 Amerdment 55
ATTACHMENT STP FSAR ST-HL-AE 18 Alo PAGEg OF F TABLE 3.9-10 (Continued)
SAFETY-RELATED SEISMIC 18 CATEGORY I EQUIPMENT OUALIFICATION PROCEDURE (NSSS SCOPE)
Safety Seismic Qualification Component Class Procedure Remarks Reactor Coolant System (Continued)
Motor Air Coolers 3
Analysis Applies only to portions containing 30 component cooling water lQ6k l Chemical and Volume Control System Regenerative HX 2
Analysis Letdown HX (tube side) 2 Analysis (shell side) 3 Analysis Reactor Coolant Filter 2
Analysis Volume Control Tank 2
Analysis Centrifugal Charging Pump 2
Analysis C&disfuga1 Charging Pum p Hofer 7,st-Positive Displacement Pu.rnf 2
Onalysis A Semp-Einse DisplaceW FWr Nodor 2
Tesf-Reactor Coolante (Purificatinn Pump) 3 Analysis Feat.ftr CootaM Pu/ificAfiM fomp %v 3 Test Seal Water l
2 Analysis i
Injection Filter Letdown Orifices 2
Analysis Excess Letdown HX (tube side) 2 Analysis (shell side) 2 Analysis Seal Water Return Filter 2
Analysis I
Seal Water HX (tube side) 2 Analysis (shell side) 3 Analysis Boric Acid Transfer Pump 3
Analysis Scric. Add Transke (b.p bhv 8
Test i
Boric Acid Filter 3
Analysis Amendment 41 3.9-126
1 ATTACHMENT ST HL E /6B.6 PAGE OF f Insert 1 Reactor Coolant System Safety Seismic Component
. Class Qualification Procedure Thermocouple Column 1
Analysis Seal Assembly Analysis (*)
Thimble Guide Tubing 1
Seal Table & Parts 1
Analysis-Flux Thimble Assembly 1
Analysis RCS Components Supports 1
Analysis Hydraulic Shock Suppressor 1
Analysis Pressurizer Safety & Relief 1
Analysis Valve Piping and Supports Missile Shield 1
Analysis R.V. Head Lift Rods 1
Analysis (portions that support RDM's)
RV Shoes and Shims 1
Analysis 4
a Ll/NRC/kb
ATTACHMENT STP FSAR ST HL AE- /FJL(,
PAGE 5 OF F TABLE 3.9-10 (Continued)
SAFETY-RELATED SEISMIC 18 CATEGORY I EQUIPMENT QUALIFICATION PROCEDURE (NSSS SCOPE)
Safety Seismic Qualification Class Procedure Remarks Component e
Chemical and Volume Control System (Continued)
Reactor Coolant Pump Seal Bypass Orifices 1
Analysis t$el2r 2 30 Boron Thermal Regeneration Subsystem Letdown Reheat HX (tube side) 2 Analysis 24 Emergency Core Cooling System Accunulators 2
Analysis 2
Analysis HHSI Pumps 2
Tcsk IHW1 %mp Molak 2
Analysis LHSI Pumps A
TOE (
U4ST R>mg W Residual Heat Removal System Residual Heat Keroval 9e f 2
e-Analysis L.,-
2 T8SI Reddval Hool feneutt] h %
Residual HX (tube side) 2 Analysis (shell side) 3 Analysis Spent Fuel Pool Cooling and Cleanup System Spent Fuel Pool Heat 30 Exchanger (tube side) 3 Analysis I
(shell side) 3 Analysis Spent Fuel Pool Pumps 3
Analysis cpt Ebel hot fbmp Moky 3
p,st Reft ling Water PurificationR>y B g
lysis Ana 7
'I Reluch@ (A%krbikcAnon &mps Molty 3 Test Main Eteam System Main Steam Isolation Valves 2
Analysis ( Ted Steam Power Operated Relicf Valves 2
Analysis (Test 3.9-127 Amendment 41 i
ATTACHMENT ST-HL-AE-/8 ?J.
PAGE /o OF f Insert 2 Chemical Volume and Control System Safety Seismic Componert Class Qualification Procedure Mixed Bed Demineralizer 3
Analysis Cation Bed Demineralizer 3
Analysis Letdown Filter 3
Analysis Ll/NRC/kb i
ATTACHMENT STP FSAR ST HL AE- /r PAGE r/ OF TABLE 3.9-10 (Continued)
SAFETY-RELATED SEISMIC CATEGORY I EQUIPMENT QUALIFICATION PROCEDURE 18 (NSSS SCOPE)
Safety Seismic Qualification Component Class Procedure Remarks
-l41 Fuel Handling System l46 Fuel Handling Machine 3
Analysis 30 Telescoping Fuel-Handling Tool 3
Analysis &Tc5f 41 Arw1 th 4 Test spent reel MI'gs emTool s
3 Fuel Transfer Sy 30 Fuel Transfer Tube and Flange 2
Analysis Cur. ;: c-c"-t r ud C: trele
.'.;;1 :i 7
New Fuel Racks 3
Analysis 30 Spent Fuel Racks 3
Analysis Neutron Detector Positioners 2
Test 41 "myid Lfoeling :;losue snield
-t-
.'n:1 ci:
j Containment Spray System Spray Additive Tanks 3
Analysis 3.9-128 Amendment 46
- ~
ATTACHMENT STP FSAR ST HL AE- /#.t.4 PAGE F OF F TABLE 3.9-10 (Continued)
SAFETY-RELATED SEISMIC CATEGORY I EQUIPMENT QUALIFICATION PROCEDURE 18 (NSSS SCOPE)
Safety Seismic Qualification Component Class Procedure Remarks Containment Spray System (Continued)
Containment Spray Pump 2
Analysis brdothmord 5pWty lbmr nob" Z
IIII' Containment Spray Eductor 2
Analysis Containment Spray Nozzles 2
Analysis Reactor Vessel or Core Related
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41
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z q p n r:,
In-CCl-30
-;;.p ;n...,
Irradiation Sample Holder 2
Analysis 41 C"2:. L L...i; Cuegun "loifuia -
,.nclyci; "ymiml-m e,, n -
part for M
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Ju rin t-30 OGC ma GGE--
CRDM Seismic Support Tie Rod Assemblies 1
Analysis Reactor Vessel Internals 2
Analysis (TcS}-
41 Control Rod Clusters 2
Analysis Containment Combustible Gas Control System 30 Electric Hydrogen Recombiner 2
Test & Analysis 41 h Aymlpis pbr(ved % bhcr of Plut.
3.9-129 Amendment 41 t