ML20235G428
| ML20235G428 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/08/1987 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#387-3980 OL, NUDOCS 8707140253 | |
| Download: ML20235G428 (48) | |
Text
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357#d C'A S E (CITIZENS ASSN. FOR SOUND ENERGY.)
==.
P_14/946-9hk6 m
'87 JUL 10 P12:40 July 8, 1987 LEb my ,
l Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom U. S. Nuclear Regulatory Commission 1107 West Knapp Street Atomic Safety & Licensing Board Stillwater, Oklahoma 74075 Washington, D.C. 20555 l
Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830
Dear Administrative Judges:
Subject:
In the Matter of Texas Utilities Electric Company, et al.
Application for an Operating License l
Comanche Peak Steam Electric Station Units 1 and 2 Docket Nos. 50-445 and 50-446 - O b Potential 10 CFR 50.55(e) Items j l
To assist the Board in its desire to be kept up-to-date on matters of ,
) potential significance, CASE is attaching copies of the potential 50.55(e) {
l items (SDAR's, or Significant Deficiency Analysis Reports) which we have i received since we provided the Board with such items on June 10, 1987.
It is our intention to periodically continue to provide these SDAR's unless the Board indicates otherwise.
Respectfully submitted, CASE (Citizens Association for Sound Energy) rs.) Juanita Ellis l President l
l cc: Service List, with Attachments l
8707140253 070708 PDR ADOCK 05000445 G PDR
) 60 3
SDAR INDEX--06-30-87 NO. SbBJECT DETERM. STATUS 1975 REACTOR BUILDING EXCAVATION R TXX-1264 1975 REACTOR CAVITY MAT R TXX-1198 l 1976 UNIT NO. 1 CONTAINMENT BASE MAT R TXX-1754 1976 SSI DAM FILTER "A" MATERIAL R TXX-20G9 )
77-A POLAR CRANE SUPPORT GIRDER NR NONE 77-B FUEL BLDG. DESIGN DISCREPANCY R TXX-2G09 3
l 77-C FAILURE OF WESTINGHOUSE AR/ARLA LATCHING RELAYS R TXX-2465 I 77-D POTENTIAL PROBLEM WITH OPERATION OF SAFEGUARDS j ACTUATION BLOCK / RESET CIRCUITRY R TXX-6381 1 77-E SPECIFICATION NONCONFORMANCE WITH THE PSAR NR NONE 77-F STATOR WINDING DEFECT DELEVAL DG NR NONE 77-1 FALSIFICATION OF CONCRETE AIR ENTRAINMENT RECORDS NR TXX-2266 77-2 CONCRETE CURING BLANKET FIRE NR TXX-2265
~
77-3 INSTALLATION OF PIPE WHIP RESTRAINT ANCHOR BOLTS, NUTS, & PLATES NR TXX-2474 77-4 POLAR CRANE SUPPORT BRACKETS R TXX-2395 77-5 OMISSION OF BORON RECYCLE EVAPORATOR PACKAGE FOUNDATION ANCHOR BOLTS NR NONE 77-6 OMISSION OF REINFORCING STEEL FROM CONCRETE POUR IN RX. BLDG. NO. 1 NR NONE 77-7 POLAR BRANE GIRDER UPLIFT RESTRAINTS NR TXX-2464 77-8 INSTALLATION OF PIPE WHIP REATRAIN ANCHOR BOLTS, NUTS, & PLATES NR TXX-2474 77-9 3 INCH DIAMETER HOLES DRILLED IN R.B. NO. 1 NR NONE 77-10 OMISSION OF REINFORCING STEEL FROM R.B.1 & A.B.1 NR NONE 77-11 OMISSION OF REINFORCING STEEL FORM R.B.1 & SG.B.1 NR NONE 77-12 l ORIENTATION OF CADWELD SLEEVES NR TXX-2678 1977 CADWELD TEST SPECIMEN REBAR FAILURE NR TXX-2269 78-A DAMAGE'TO DELAVAL DIESEL GENERATOR CONTROL PANEL NR NONE 78-B MISCLASSIFICATION OF SAFETY RELATED EQUIPMENT NR TXX-2867 78-C SERVICE WATER INTAKE PUMP SEISMIC RESTRAINT NR TXX-2905 78-1 SERVICE WATER PUMP SUPPORTS NR NONE 78-2 CATALYTIC HYDROGEN RECOMBINERS NR NONE 78-3 CANCELLED 78-4 ANCHOR. BOLTS-MISCLASSIFICATION. NR SEE 78-B 78-5 ANCHOR PLATE WASHERS MISCLASSIFICATION NR SEE 78-B 78-6 DEFECTIVE CADWELDING NR TXX-2896 78-7 WELDING ACTIVITIES FOR UNIT 1 RCS LOOP PIPING NR TXX-2926 1975-1978: 8 REPORTABLE SDARS
~
.SDAR INDEX-06-30-87 NO. 5 SpBJECT DETERM. STATUS 79-01 EXPANSION JOINT-DECONTAMINATION ROOM NR TXX-2952 79-02 INSTALLATION OF PIPE ELBOWS IN SG LOOP PIPING NR TXX-2907 79-03 REACTOR VESSEL N0ZZLE BASE METAL DEFECTS NR TXX-3007 79-04 PIPE SUPPORTS NR TXX-3036 79-05 PIPE WALL THICKNESS R TXX-3138 79A PRESSURE TRANSMITTERS NR TXX-3003 79B POSSIBLE COOLING PROBLEM WITH DIESEL GENERATORS NR TXX-3054 79-06 ELECTRICAL CABLE TRAY HANGERS-PARTI AL WELDS R TXX-3067 79-07 REACTOR CONTAINMENT NR 10/29/79 79-08 INSTALLATION OF DRILLED-IN EXPANSION ANCHORS R* TXX-3125 79-09 WELDED CONDUIT SUPPORTS R TXX-3173 79-10 CLASSiV PIPING SUPPORTS R TXX-3195 79-11 REACTOR COOLANT NR 12/29/79 79-12 FILTER INTERNALS NR 01/12/80 79-13 CONCRETE HONEYCOMBING-UNIT 2 SG COMPARTMENT R TXX-3124 1979: 15 TOTA $SDARS--6 REPORTABLE 80-01 SERVI E WATER PUMPS NR 01/17/80
~
80-02 SERVICE WATER CONTROL VALVES R TXX-3114 80-03 CONTROL DOARD WELDING CONNECTIONS R TXX-3131 80-04 REACTOR VESSEL N0ZZLE SAFE-ENDS NR TXX-3154 80-05 USE OF ARCHITECTURAL CONCRETE IN FLOOR SLABS R TXX-3247 80-06 UPPER: INTERNALS ROTO-LOCK INSERT NR TXX-3217 80-07 PLASCITE 7122 COATING JGl TXX-3229 80-08 THREAD ENGAGEMENT OF SWAY STRUTS NR TXX-3219 80-09 DIESEd GENERATOR PIPE SUPPORTS R* TXX-3415 -
80-10 HILTI-KWIK CONCRETE ANCHOR BOLTS R* TXX -3442 80-11 CANCELLED 80-12 PULL-0UT PERFORMANCE OF HILTI-KWIK BOLT ANCHORS NR TXX-3398 1980: 11 TOTAL SDARS--5 REPORTABLE 1
81-01 PIPE SUPPORT BASEPLATE GROUTING MATERIAL NR TXX-3279 81-02 ELECTRICAL CABLE LUBRICANT NR TXX-3357 81-A WESTINGHOUSE GATE VALVES R TXX-3409 81-B BAHNSON HVAC ANCHOR BOLTS R TXX-3329 81-03 HVAC COOLING SYSTEM R TXX-3349 81-04 FAILURE OF 6.9KV CIRCUIT BREAKER NR TXX-3313 81-C VOLUME CONTROL TANK LEVEL CONTROL SYSTEM NR TXX-3311 81-05 PIPE SPOOL FLANGE MATERIAL NR TXX-3356 81-06 SEISMIC INSTRUMENT TUBING SUPPORT R TXX-3358 81-07 ORIFICE PLATES SUPPLIED OUTSIDE OF TOLERANCE R TXX-3527 81-08 UNDERSPECIFIED AFW VALVES NR TXX-3487 1981: 11 TOTAL' SDARS--5 REPORTABLE l
l l
l c_______--___-_-_-___-_---_.
SDAR INDEX-06-30-87 !
NO. 3 SUBJECT
, DETESS.. STATUS-82-A INSTALLED BORG WARNER VALVES R TXX-3495 82-01 MATERIAL PROCURED BY AFC0 STEEL NR TXX-3480 82-02 DESIGN OF HORIZONTAL FIRE DAMPERS R* TXX-3523 l 82-03 W RCS WIDE RANGE PRESSURE MEASUREMENTS NR TXX-3571 82 04 PACIFIC PUMP MULTI-VANE DIFFUSER CRACKING NR TXX-3634 :
B2-05 UNIT 2 SG COMPARTMENT WALL-CONCRETE VOID NR TXX-3549 82-06 AUXILIARY SKID UNIT 2 R* TXX-4095 i 82-07 DEFECTIVE C0VERNOR DRIVE COUPLINGS R* TXX-3567 82-08 DEFECTIVE LIMITORQUE PINION KEYS NR TXX-3580 82-09 SSPS UNDETECTABLE FAILURE R* TXX-3589 82-10 j REINSPECTION OF CONDUIT SUPPORTS NR TXX-3583 '
S2-ll OVERTORQUING OF SAFETY RELIEF VALVES NR TXX-3594 82-12 PIPE-WHIP RESTRAINT WELD INDICATIONS NR TXX-3604 82-13 VOID IN AUX. BLDG. CONCRETE FLOOR SLABS NR TXX-3589 82-14 REACTOR COOLANT PRESSURIZER SURGE LINE NR TXX-3592 82-15 DEFECTIVE PISTON SKIRT CASTINGS R* TXX-4101 1982: 16 TOTAI,SDARS--6 REPORTABLE l -
l 83-01 BORG-WARNER CHECK VALVE MALFUNCTION R TXX-3623 l
83 02 EMD VALVE POSITION INDICATION R TXX-3633 83-03 NON-METALLIC INSULATION NR TXX-3624 83-04 RADIATION MONITORING SYSTEM (RM-23) NR TXX-3635 83-05 VOIDED 83-06 VENDOR (BAHNSON) INSTALLED HVAC SYSTEM .NR TXX-4016 83-07 NEW FUEL STORAGE RACKS R TXX-3677 83-08 CONTROL, VALVE BRACKETS WELDING 'R* TXX-3657 83-09 WESTINGHOUSE DS416 REACTOR TRIP SWITCHGEAR R* W REPORTED l 83-10 LETDOWN HEAT EXCHANGER ANCHORS R TXX-4001 83-11 CCW CL, ASS V PIPING R* TXX-3690 83-12 CLASS 1 MA1ERIAL DEFICIENCIES NR TXX-3691 83-13 STRUT JAMMING DEVICES NR TXX-3692 83-14 WESTINGHOUSE NLP PRINTED CIRCUIT CARDS NR TXX-3693 83-15 CABLE TRAY CLAMPS R* TXX-4005 83-16 WELDED ATTACHMENTS TO PIPING AFTER HYDROSTATIC ,
TESTING NR' TXX-4012 1 83-17 INADEQUATE OVERPRESSURE PROTECTION FOR SPENT FUEL POOL COOLING HEAT EXCHANGERS CCW RELIEF VALVES R TXX-4043 83-18 CONTAINMENT BLDG. COOLING R TXX- 4043 83-19 SERVICE WATER SYSTEM VALVES NR TXX-4064 83-20 DEFECTIVE BREAKER SUPPORT DRACKETS R TXX-4078 83-21 TRANSMITTER CALIBRATIONS R TXX-4091 83-22 CHLORINE DETECTION AND CONTROL ROOM HVAC 3
R TXX-4098 1983: 21 TOTAL SDARS--13 REPORTABLE e
?
SDAR INDEX-06/30/87 NO. i SpBJECT DETERM. STATUS 84-01 CABLE TRAY SUPPORT COLUMN (CABLE SPREAD ROOM) NR TXX-4154 84-02 DIESEL GENERATORS DEFECTIVE PUSH RODS R* TXX-4108 84-03 IWS*IRUMENT TUBING NR TYX-4110 I 84-04 FERRORESONANT TRANSFORMERS R TXX-4109 84-05 PROTECTIVE COATINGS ADHESION TESTER NR TXX-4218 84-06 PIPE SUPPORT DESIGN ERROR NR TXX-4107 84-07 DEFICIENT LUG CRIMPING H TXX-4135 84 -08 THERMAL EXPANSION OF CURTAIN FIRE DAMPERS R* TXX-4257 j l 81-09 THRUST EEARING LUBRICATION NR TXX-4227 '
l 84-A INSPECTOR EYE EXAMINATION RECORDS NR TXX- 4204 84-10 RODENT DAMAGE TO CLASS 1E CABLES NR TXX-4175 1 84--11 UNAUTHORIZED THERMOLAG INSULATION NR TXX-4178 84-12 IMPACT OF HELB TEMPERATURES ON OUALIFIED EQUIPMENT OUTSIDE CONTAINMENT P* 07/28/87 84 13 FSAR AND TECHNICAL SPECIFICATION CONSISTENCY NR TXX-4213 84-14 ROCKBESTOS CABLE DEFICIENCY NR TXX-4214 84-15 INDETERMIN. FLORIDE CONTENT-MANVILLE INSULATION NR TXX-4221 84-16 QUALIFICATION OF MAIN STEAM RELIEF VALVES NR TXX-4330 84-17 FLOODING CONCERNS R* TXX-4263 84-18 UNQUALIFIED LIMITORQUE ELECTRIC MOTORS R TXX- 4308 84-19 DG MATERIAL DEFECT (VALVE SPRINGS) NR TXX-4270 84-20 DG MATERIAL DEFECT (DELIVERY VALVE HOLDER) NR TXX-4309 84-21 UT REQUIREMENTS: CLASS 1 PIPING NR TXX-4292 84-22 CCW SYSTEM DESIGN CONCERN NR TXX-4351 84-23 CONAX PENETRATION CONNECTORS NR TXX-4375 84-24 PREOPERATIONAL TESTING ACTIVITIES ,NR TXX-4372 84-25 AIR-OPERATED DIAPHRAGM VALVES NR TXX-4318 l i
84-26 NSSS AUXILIARY RELAY RACKS NR TXX-4317 84-27 VENTILATION EXHAUST DAMPERS R* TXX-4409 84-28 ROSEMOUNT TRANSMITTERS LEAKAGE R* TXX-4364 j 84-29 SAFE SHUTDOWN CAPABILITY FOR FIRE-C.R. HVAC R* TXX-4350 ;
84-30 SAFETY CLASS DESIGNATION OF INSTRUMENTS LINES NR TXX-4362 l 84-31 CONTROL ROOM SEPARATION WALL R* TXX-4349 l 84-32 CLASS lE BARTON PRESSURE SWITCHES-PART 21 NR TXX-4363 84- 33 RELAYS OUTSIDE SPECIFICATION NR TXX-4376 84-34 UNIT 2 STRUCTURAL EMBED WELDING NR TXX-4433 1984: 35 TOTAL SDARS-10 REPORTABLE, 1 POTENTIAL 1
SDAR INDEX-0G/30/87 NO. SUBJECT DETERM. STATUS 85-01 MAIN CONTROL BOARD CADLE SEPARATION VIOLATION NR TXX-4411 85-02 f CABLE SPREAD ROOM FIRE PROTECTION-3 HR BARRIER NR TXX-4410 85-03 STEAM GENERATOR UPPER LATERAL SUPPORT BEAMS R* TXX-4415 85-04 CONTAINMENT SPRAY HEADER ISOLATION VALVES R* TXX-4437 85-05 DG ENGINE CONTROL PANEL AIR FILTER BOWLS R TXX-4428 85-06 ERF COMPUTER TERMINATION POINTS NR TXX-4447 j
B5-07 ELECTRICAL CABLE BUTT SPLICES NR TXX-4490 1 85-08 SUMP ISOLATION VALVE MOTORS NH TXX-4481 "
85-09 VALVE WEIGHT DISCREPANCIES NR TXX-4473 85-10 RELIANCE CONTROL BOARD EQ DOCUMENTATION NR TXX-4523 >
85-11 INSTRUMENTATION TUBE FITTING LOCATIONS R* TXX-4454 j 85-12 AFW PRESSURE CONTROL-FEED WATER LOW FLOW TO S/G R* TXX-4456 85-13 j UNDETECTED FAILURE IN SAFETY FEATURES ACT.SYS. R* TXX-4457 4 85-14 UNAUTHORIZED SUPPORT REPAIRS R* TXX-4465 85-15 {
EQUIPMENT HATCH UNIT 1 UNEVAL. BEARING FORCES NR TXX-4460 85-16 PHOENIX STEEL-PART 21 WALL THICKNESS QUESTION NR TXX-4505 85-17 PART 21-CORE EXIT TEMPERATURE MONITORING ERRORS NR TXX-4485 85-18 SPECIFIC CRITERIA FOR CONCRETE ANCHORS IN THE PROXIMITY OF EMBEDDED ANGLED NOT DEFINED R* TXX-4492 85-19 CONDUIT SUPPORT SPANS R* 08/12/87 85-20 WHIP INTERACTION POSSIBLE-FW BREAK /CS HEADERS R* TXX-4516 * ~
85-21 DG POTENTIAL CONTROL PANEL OVERHEATING NR TXX-4493 85-22 CONTAINMENT ISOLATION VALVES NR TXX-4575 4
85-23 CONTAINMENT SPRAY PUMP
)
NR TXX-4563 )
85-24 TERMINATION OF FIRE DETECTION DETECTORS NR TXX-4533 I 85-25 SEQUENCING FIRE PROT. COMPONENTS FOR HVAC/CCW NR TXX-4578 85-26 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN .NR TXX-6132 85-27 SEISMIC GAP LESS THAN DESIGN-CPRT ITEM II.C R* TXX-4650 85-28 PIPE SUPPORTS hTLD LENGTH ANALYSES NR TXX-4550 85-29 DESIGN OF ARCHITECTURAL FEATURES R* TXX-4552 85-30 SWITHGEAR CABINET VENDOR TERMINATION NR TXX-4598 85-31 ELECTRICAL RACEWAY SUPPORT SYSTEM DESIGN R* 08/28/87 !
85-32 FEEDWATER REG VALVE SINGLE POWER SUPPLY NR TXX-4600 85-33 NON-SEISMIC TO SEISMIC INTERACTION NR TXX-4577 85-34 CONDUIT SUPPORT SYSTEM i
R* 02/01/88 85-35 CABLE TRAY HANGER DESIGN R*
85-36 07/06/87 TRAIN 'C' CONDUIT SUPPORTS P*
85-37 07/08/87 -
QUALIFICATION / CERTIFICATION OF INSPECTORS R* TXX-4569 85-38 CONTROL BOARD SEPARATION MATERIAL NR TXX-4715 85-39 EQUIPMENT CONDUIT INTERFACE P*
85-40 09/15/87 FLUX MAPPING SEAL TABLE RESTRAINTS R* TXX-4633 85-41 COMPUTER PROGRAM ERRORS NR TXX-4716 85-42 CONDUIT LOADING BY THERMOLAG R* 07/31/87 85-43 QUALIFICATION OF PLANT TEMPERATURES R* TXX-4659 85-44 QUALIFICATION OF 480V SWITCHGEAR NR TXX-4918 85-45 REBAR DAMAGE NR TXX-4761 85-46 DAMAGE STUDY EVAL. OF W ANALYZED PIPING R* TXX-4658 85-47 USE OF'AMPTECTOR IIA RELAYS NR TXX-4682 85-48 DG INTAKE SILENCER INTERNALS NR TXX-4683 85-49 MAIN STEAM LINE FLUID TRANSIENT R* TXX-4656 85-50 CABLE TRAY TEE FITTINGS P*
85-51 09/30/87 APPLICATION OF LOW SULPHUR CONTENT A588 STEEL NR TXX-4722 85-52 CABLE TRAY HANGER REVERIFICATION PROGRAM R* TXX-4657 85-53 SEISMIC CATEGORY I PLATFORMS P*
85-54 12/20/86 SEISMIC QUALIFICATION OF HVAC SUPPORTS R TXX-6460 1985: 54 TOTAL SD ARS--23 REPORTABLE, 4 POTENTI AL
SDAR INDEX-0G/30/87 N.O . SUBJECT DETEIN. STATUS 86-01 WEIDMULLER TERMINAL BLOCKS NR TXX-4712 86-02 TURBINE-DRIVEN AFW PUMP PERFORMANCE NH TXX-4723 8G-03 CLASS lE INSTRUMENT TECHNIQUES R* TXX-4692 86-04 RICHMOND INSERTS TO EMBEDDED PLATE R* 08/01/87 8G-05 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NSS EMBEDDED PLATE NH TXX -4776 BG-06 PUMP AND DRIVER DOWELING NR TXX-4704 8G-07 SERVICE WATER SYSTEM LEAKAGE R* 07/15/87 86-08 SUPER lif LTI-KWIK BOLT INSTALLATIONS P* 07/22/87 86-09 DG INLET / EXHAUST VALVE SPRINGS NR TXX-4724 86-10 ELECTRICAL PENETRATION ASSEMBLIES R* 12/18/87 86-11 PUMP IMPELLER LINEAR INDICATIONS R* 09/04/87 86-12 COMMODITY INSTALLATIONS AT SEC. WALL DESIGN GAP P* 12/18/87 8G-13 JET IMPINGEMENT LOAD REVIEW P* 08/19/87 86-14 6.9KV SWITCHGEAR BREAKER WELD FAILURE R TXX-6341 '
86-15 DIESEL GENERATOR CONTROLS NR TXX-G002 86-16 FIRE EFFECTS ON INSTRUMENT TUBING R TXX-6230 86-17 MINIMUM CONCRETE COVERAGE NR TXX-6180 86-18 SAFETY CHILLED WATER CHILLER UNITS R* 12/18/87 86-19 INSTRUMENTATION INSTALLATIONS R* 07/31/87 8G-20 WFI NUCLEAR PRODUCTS NR TXX-4870 86-21 QUALIFICATION OF RAYCHEM KIT NPKS-02-01 NR TXX-5046 86-22 SG'S AREA FAN COOLERS P* 07/08/87 86-23 P-10 PERMISSIVE R* TXX-4835 86-24 SPACE AND MOTOR HEATERS NR TXX-6083 80-25 BREAKER / FUSE COORDINATION NR TXX-4904 86-26 CONTAINMENT SPRAY SYSTEM PIPING .NR TXX-4799 86-27 CCW RADIATION DETECTORS NR TXX-4800 86-28 SERVICE WATER SYSTEM DISCHARGE NR TXX-4801 86-29 ACCEPTANCE TEST OF AIR OPERATED VALVES NR TXX-4802 86-30 UPS INVERTERS NR TXX-4965 8G-31 DG LUBE OIL SUMP TANK FOOT VALVES R* 07/13/87 80-32 THRU-WALL EBMEDDED CONDUIT SLEEVES P* 10/30/87 8G-33 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS R TXX-6025 80-34 DEFECTIVE FIRE STOP INSTALLATIONS NR TXX-4906 80-35 MOTOR OPERATORS FOR MANUAL VALVES R* 08/04/87 86-3G LARGE BORE PIPING AND SUPPORTS R* 08/20/87 86-37 )
CLASS 1E BATTERY CHARGER COMPONENTS P* 07/24/87 !
8G-38 TRACEABILITY OF lE PIGTAIL EXTENSIONS P* 10/05/87 i 86-39 CABLE TRAY "C-TYPE" CLAMP SHIM DIMENSIONS NR TXX-6403 l 86-40 APPLICATION OF NON-QUALIFIED AGASTAT RELAYS R* 10/09/87 86-41 SMALL LOCA MODE 4 OPERATION l P* 02/29/88 '
86-42 I&C CABINET POWER SUPPLY BREAKERS NR TXX-4993 8G-43 ITT BARTON MODEL 580 SERIES SWITCHES NR TXX-5047 86-44 WELDED ATTACINENTS TO EMBEDDEf: STRIP PLATES R TXX-62G1 86-45 SEISMIC CATEGORY II SYSTEMS & COMPONENTS P* 09/11/87 86-46 GOULD BATTERY RACKS TRANSVERSE BRAING R TXX-6427 86-47 FIRE PENETRATION SEAL DESIGN NR TXX-499G 80-48 ADEQUACY OF NONCONFOINANCE DISPOSITIONS P* 07/15/87 86-49 CONAX ADAPTOR MODULES & ELECTRICAL PENETRATIONS R* 01/20/88 86-50 UNISTRUT SPRING NUTS ON INSTRUMENT SUPPORTS R TXX-0292 8G-51 ANCHOR BOLTS SUPPLIED BY HILTI P* 07/08/87 8G-52 CABLE TRAY SPLICES / CONNECTIONS R* 08/03/87 -
80-53 SEISMIC DESIGN OF CONDUIT R* 09/21/87 8G-54 ORIGINAL DESIGN OF CONTROL ROOM CEILING R* 07/21/87 86-55 )
SEISMIC AIR GAP DESIGN ADEQUACY P* 07/08/87 86-56 DG ENGINE CONNECTING ROD ASSEMBLY NR TXX-5025 86-57 REINFORCING STEEL IN UNIT 1 RX CAVITY WALL NH TXX-6028 86-58 DRILLING / CUTTING OF REINFOR. STEEL IN FUEL BLDG NR TXX-6029 80-59 SUPPORT INSTALLATIONS-SPACING VIOLATIONS R TXX-6450
SDAR INDEX-0G/30/87 NO. SUBJECT DETERM. 3TATUS BG-t 0 POLAR CifANE GIRDER AND GIRDER SUPPORT SHIM GAPS NR TXX-6544 BG- 61 POLAR CRANE RESTRAINTS NR TXX-6092 86-62 POLAR CRANE SUPPORT STRUCTURE R* 09/25/87 HG- 63 PIPE SUPPORT INSTALLATIONS R* 07/20/87 8G-G4 COATINGS FOR DIESEL FUEL OIL TANKS NR TXX-64G1 BG-G5 UNCONSOLIDATED CONCRETE-UNIT 2 RCB EXT. WALL NR TXX-6330 86-GG NON-CONTACT LAP SPLICES IN AUX.BLDC. NR TXX-G282 86-67 PRE-OP VIBRATION TEST CRITERIA R* 10/22/87 GG-G8 WEATi!ER PROTECTION FOR CLASS 1E COMPONENTS P* 07/24/87 HG-69 SUPPollT OF CLASS lE WIRING NR TXX-64G4 i 86-70 ELEV. TEMP. EFFECTS ON INSTRUMENT SUPPTS& TUBING R TXX-6220 BG-71 CABLE PULLING TENSION P* 08/21/87 HG-72 SMALL BORE PIPING AND SUPPORTS R* 08/20/87 8G-73 ASMR SNUBBER ATTACHMENT BRACKETS R* 09/18/87 )
8G-74 ROCKWELL TERMINAL BOXES NR TXX-6372 l BG-75 ASCO SOLENOID VALVES IN PISTON AIR ACTUATORS OF PAPCO DAMPERS NR TXX-6287 BG- 7G DEVIATIONS IN GOULD BATTERY RACK DIMENSIONS P* 08/10/87 8G-77 INSTRUMENT TUBING MINIMUM WALL REQUIREMENTS R TXX-6228 86-78 STRUCTURAL STEEL BOLTING IN CABLE SPREAD ROOM P* 12/15/87 86-79 OVERTORQUED WESTINGHOUSE. AR RELAYS NT TXX-6533 1 86-80 TOROUE VALUES FOR J.C WWITE TUBING RESTRAINTS NR TXX-6140 8G-81 BOP INSTRUMENT SETPOINT ERRORS P* 07/29/87 86-82 CTH WELDS USED TO SPLICE CHANNEL SECTIONS R* 07/17/87 1 86-83 SBM ON POWER CABLES AND POWER RACEWAYS P* 08/28/87 l l
198G: 83 TOTAL SDA1S--31 REPORTABLE, 18 POTENTIAL l
.. *=
0 SDAH INDEX-06/30/87 NO. SUR.TECT DETEIN. STATUS 87-01 STATIC COMPUTER MODEL FOR SG BLDG P* 07/29/87 87-02 FISHER CONTROL VALVES NR TXX-6316 87-03 6.9 KV SWITCHGEAR INSTALLATIONS R TXX-6334 87-04 PLUG WELDING ON EMBEDDED CHANNEL R TXX-6538 87-05 EQ OF CABLE TO POST-LOCA HRRM P* 07/21/87 87-0G SQ OF AS-BUILT 480 VOLT POWER CENTERS P* 09/04/87 l 87-07 PROCUREMENT OF SPARE PARTS W/0 QUAL.RE0TS. P* 02/19/88 87 08 CAL. ACCURACY OF PRES.STD. DEAD WEIGHT TESTER P* 07/21/87 87-09 TERMINAL STUDS IN PK-2 TEST BLOCKS P* 08/07/87 87-10 CONTROL OF DESIGN MODIFICATIONS P* 08/28/87 87-11 DEFECTIVE CIRCUIT CARDS IN BATTERY CHARGERS P* 08/14/87 j l 87-12 CONTAINMENT P/T ANALYSIS COMPUTER ERROR P* 08/05/87 l 87-13 CLASS lE SEPARATION VIOLATIONS P* 02/19/8P 87-14 SYSTEM OPERABILITY DURING TESTING P* 08/12/87 i 87-15 AIR ACCUMULATORS FOR CONTROL VALVES P4 08/22/87 l 87-16 LIMIT SWITCH WIRING P* 07/01/87 i 87-17 VALIDYNE 15V POWER SUPPLY P* 07/08/87 87- 18 SQ OF'CCW HX IN UNIT 1 P* 07/08/87 87-19 AMBIENT TEMPERATURE AFFECTS ON MSIV ACTUATORS P* 07/10/87 87-20 CRACKED PORCELAIN CONNECTORS ON 6.9KV TRNSFMRS P* 07/17/87 87-21 AFFECTS OF THERM 0 LAG ON DERATING FACTORS P* 07/17/87 -
~
87-22 IMPACT TESTING FOR CONTAINMENT LINER ATTACHMENTS P* 07/17/87 87-23 LOOSE CONDUIT UNIONS P* 07/26/87 87-24 CONTAINMENT LINER NELSON STUD BENDING P* 07/29/87 87-25 DG FUEL OIL TANK VENT MISSILE PROTECTION P* 07/23/87 i 87-26 DG FUEL OIL TRANSFER PUMP SUCTION LIFT P* 07/29/87 I 87-27 GALVANIC CORROSION IN CCW AND SW SYSTEMS ,P* 07/29/87 87-28 CONDENSATE STORAGE TANK OVERPRESSURIZATION P* 07/29/87 87-29 CCW ISOLATION AFTER RCP THERMAL BARRIER RUPTURE P* 07/29/87 1987: 29 TOTAL SDARS-- 2 REPORTABLE, 2G POTENTIAL m .
File # 10110
, 907.3
= = Ref # 10CFR50.55(e) 1UELECTRIC wmiam c. camsa uly , 1 87 Executwe Vwe Presutent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CONTROL VALVE BRACKETS SDAR: CP-83-08 (INTERIM REPORT)
Gentlemen: -
On March 24, 1983, we verbally notified your Mr. R. G. Taylor of a potentially reportable item involving welding of brackets on vendor supplied valves. This item was determined to be reportable via TXX-3657, dated April 21, 1983. Our latest reports were logged TXX-6222, TXX-6324, and TXX-6435, dated February 18, 1987, March 27, 1987, and May 13, 1987, respectively. These last two ,
reports address this issue as related to a deviation (445/8607-D-01) identified in the NRC Inspection Report Nos. 50-445/86-07 and 50-446/86-05.
Our report dated April 21, 1983, identified two deficient items. The first item dealt with the issue of the code boundary of the brackets welded to the !
valve operators. We previously stated that the brackets were considered to be l an integral part of an intervening element in which the pressure boundary {
integrity must be assured. '
Subsequent evaluations indicate the seismic restraints do not provide support for the ASME III Piping System. The purpose of these supports is to restrain the seismic motion of the valve operators. Although the restraints are ASME-NF certified, it is not required by design that they be part of the ASME III Certified System. As the valve skirt and clip are not part of the NPV-1 component certified by Fisher Control, the restraints are r.ot to be included in the ASME N-5 certified boundary.
The second item dealt with the quality of the bracket-to-actuator barrel weld with regard to the component pressure boundary integrity. As the boundary -
i definition above places the brackets' weld outside the component pressure '
boundary the question dealing with the lack of documentation regarding weld acceptability can be addressed by the following explanation.
400 North Olive Street LB BI Dallas, Texas 75201
D o
TXX-6526 July 1, 1987 Page 2 of 2 The clip material was procured by Fisher Control in accordance with their QA Program. The welding of the clips to the skirt was performed by qualified welders to qualified welding procedures, with qualified filler material and in accordance with the Fisher Control QA Program (for ASME Section IX). The welds were inspected per the Fisher Control QA Program and released under the Vendor Control Program. Compliance with the requirements of the component design specification, and seismic qualification was certified by Fisher Control.
A seismic event would not affect the integrity of the ASME piping system since the brackets' welds are certified to be adequate under seismic design loads as documented in Fisher's seismic qualification report.
Based on the above, we are re-evaluating our commitment to replace the subject brackets. To ensure the brackets' welds are acceptable we have decided.to -
review Fisher Control's Certificates of Conformance (C of C's) and inspectL the bracket attachment welds in accordance with the visual weld acceptance criteria (VWAC) and the weld sizes as depicted on the vendor's design drawings.
We will submit our next report by January 14, 1988.
Very truly yours, ,
W.G.younsil By: , , . // -
G. S. Keeley '
Manager, Nuclear Lice sing JCH/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l
l
M Log # TXX-6534
==
- - File # 10110
- 903.9
= = Ref # 10CFR50.55(e) illELECTRIC William G. Counsil Esecutne 6ce hcudent U. S. Nuclear Regulatory Commission ATTN: Document Control Desk
, Washington, D.C. 20555 1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446-ELECRICAL RACEWAY SUPPORT SYSTEM SDAR: CP-85-31 (INTERIM REPORT)
Gentlemen:
On December 5,1986 we notified you by our letter logged TXX-6138 of a deficiency involving the Unit 1 Class IE Electrical Raceway Support System which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective actions implemented to date.
Our latest report, logged TXX-6319 was submitted March 6,1987.
This deficiency involves the installation of Separation Barrier Material (SBM)-
and Radiant Energy Shield-(RES) material on Unit 1 Class IE Electrical Conduit Raceways without engineering interdisciplinary design review of the proposed change.
As a result of the completed evaluation of conduit installations affected by the RES, twenty (20) supports will be modified and fifteen'-(15) new supports will be added. Design change authorizations and travelers have been approved and issued for all modified and new supports. Physical work started in January 1987 and is currently 40% complete. .
j New and/or additional conduit installations requiring RES have been identified j and are being evaluated in accordance with the revised interdiscipline procedural program. .
l After completion of the program to determine the effects of the installation 1 of RES on the Raceway Support System, a similar program will be conducted to !
determine the effects of the installation of SBM. 4 Our next report will be submitted by August 28, 1987.
l Very truly yours,f
/ l 7?&c.
W. G. Counsil DAR/mgt c - Mr. R. D. Martin, Region IV I Resident Inspectors, CPSES (3) )
MK) Nonh Ohve Street LB 81 Dallas, Texas 73.'01
~
M Log # TXX-6521 '
F9 File # 10110
_. 903.10 r = Ref # 10CFR50.55(e)
TUELECTRIC wimam c. counsu June 19, 1987 Executuve %ce Preudem
- U. S. Nuclear Regulatory Commission Attn
- Document Control Desk l Washington, DC 20555 l >
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 EQUIPMENT CONDUIT INTERFACE !
SDAR: CP-85-39 (INTERIM REPORT) i Gentlemen:
4 On September 18, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving conduit which was not installed in accordance with design documents. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our most recent interim report was logged TXX-6438, dated May 12, 1987.
As previously reported, the program to evaluate this condition consists of the following three issues:
- 1) Cable slack adequacy.
- 2) Conduit-to-equipment interfaces outside the vendor approved area.
- 3) Conduit orientation within the vendor approved entry area (Complete per interim report logged TXX-6165).
The cable slack adequacy issue final report was issued as scheduled on May 14, 1987, and is presently undergoing third party review. This review is scheduled for completion by June 19, 1997.
The issue date of the report on the Unit I conduit-to-equipment interface issue has been rescheduled from June 1, to June 19, 1987.
After finalization of these reports, a complete evaluation will be performed to determine the effects of this issue on the safety of plant operations and deportability under the provisions of 10CFR50.55(e).
M)O North Ohve Street LB 61 DaHas. Texas 75201
TXX-6521 June 19, 1987 Page 2 of 2 We will submit our next report on this issue no later than September 15, 1987.
Very truly yours, THE I W. G. Counsil RSB/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l
l
- 6
-M Log # TXX-6509 3 :l IEEE - File # 10110 l
- . .: 908.3
- :: Ref # 10CFR50.55(e) illELECTRIC wimam c. counsu June 12, 1987 Esecutsve Vwe Presuknt U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CABLE TRAY TEE FITTINGS SDAR: CP-85-50 (INTERIM REPORT)
Gentlemen:
1 On December 6,1985, we verbally notified your Mr. H. S. Phillips of a l
deficiency involving the use of improper welding processes in the manufacturing of cable tray tee fittings which could affect the equipment qualification. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest report, logged TXX-6413,-
was submitted April 28, 1987.
As stated in previous reports, a testing program is being conducted to complete our assessment of this issue. To establish and demonstrate ruinimum weld requirements and to determine whether weld conditions of installed ;
components are acceptable, we have initiated the following steps.
- 1) The minimum weld that is considered acceptable, based on calculation, for each " Tee" fitting configuration (size) has been identified on drawings. A model representing the minimum weld requirements has been tested and the results are currently being evaluated.
- 2) A field survey is currently underway to determine existing weld conditions, with respect to " Minimum Weld Requirements" specified in step 1. " Tee" sections installed in the field which are found to have insufficient or deficient welds, (i.e., not in accordance with calculations above) will be repaired. Final acceptance of the repairs is contingent upon the test results evaluation above.
There are a total of two hundred twenty (220) " Tee" fittings in Unit 1 and one hundred twelve (112) " Tee" fittings in Unit 2, which are affected by this issue. A fraction of the two hundred twenty (220) fittings in Unit I were covered by thermolag and the thermolag was removed to permit access for inspection and repair-of welds as necessary.
n v.n o>,c c. . i n e, n.n, rn ,, ,,n ,
TXX-6509 Jtae 12, 1987 P6ge 2 of 2 The work has not been completed yet, however, repair of " Tee" fitting welds has been accomplished for one hundred (100) of the two hundred twenty.(220) Unit I fittings and twenty-eight (28) of I the one hundred twelve (112) Unit 2 fittings.
We had previously stated that the field survey would identify " Tee" sections with " worst" case weld conditions to be tested. Considering the extensive effort required, we have decided not to test a " worst" case model. Our deportability assessment will evaluate those existing " Tee"' sections which'do not meet the requirements specified in step 1.
In addition, installation of additional " Tees" has been deferred until our evaluation of this issue is complete. Any " Tees" installed in the future will be required to meet established weld requirements.
We will submit our next report by September 30, 1987.
Very truly yours,
/ V'M
/
W. G. Counsil RSB/gj c - R. D. Martin, Region IV Resident Inspectors, CPSES (3)
I
i l
1 l
l
== Log # TXX-6524
- -- ---- File # 10110 !
_ _ 903.8 ;
r r Ref # 10CFR50.55(e) j TUELECTRIC j i
William G. Counsil '
Lwcutm Vwe Vrruacm i
U. S. Nuclear Regulatory Commission Attn: Document Control Desk l Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N0. 50-445 {
s SEISMIC CATEGORY I PLATFORMS SDAR: CP-85-53 (INTERIM REPORT) i l
Gentlemen:
/!
On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving Seismic Category 11 platforms. This is an interim report of a s j
i potentially reportable item under the provisions of 10CFR50.55(e). Our last {
interim report, logged TXX-6408, was submitted April 27, 1987. j l
Subsequent to our last report, we have determined that the issue involves only 1 Unit 1. A document search has indicated similar conditions do not exist in
{
Unit 2. Additionally, we have determined that the original platform
{
identified as a Category II platform has been misidentified and is, in fact, a :
l Category I platform. Thus, we have changed the title of this issue to j
correctly reflect the scope of the deficiency. ,
1 l At this point, the affected platforms have been identified. The documentation I for these installations is under review for completeness and acceptability by !
Quality Engineering. Deficiency documents (NCRs/DRs) will be issued for those
{
platforms which are determined to be discrepant. Rework or reinspection will be performed as appropriate after which our evaluation will be completed to i determine the effect of this issue on the safety of plant operations had it remained uncorrected. i Our next report will be submitted no later than December 20, 1987. '
Very truly yours, I tlMy W. G. Counsil JCH/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3)
.@ Wh C s Street LB St Daks. Texas 75201 L_ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - - _- - - - - _ - - - - - - - - - - - -
File # 10110 l
. 903.I1 l
= = Ref. # 10CFR50.55(e) j 1UELECTRIC June 12, 1987 William G, Counsil Enecutwe hw Presudent U. S. Nuclear Regulatory Commission '
i ATTN: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 (INTERIli REPORT)
Gentlemen:
On March 5, .1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report :P 2 potentially reportable item under the provisions of 10CFR50.55(e).
Our last interim report, logged TXX-6379, was submitted on April 3,1987.
The schedule for the completion of our review and the issuance of'a final Engineering Evaluation Report has been revised to July 22, 1987. Our next report will be submitted no later than August 19, 1987.
1 Very truly yours, '
OT W. G. Counsil BSD/gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 Nonh Olive 5ttret LB 81 Dallas, Texas 75201
~
Log 0 TXX-6506' E
P9 File # 10110 903.9 r Ref. # 10CFR50.55(e)
1EIELECTRIC June 12, 1987 William G. Counsil Executsve Vwe Presodent i U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 00CKETS NOS. 50-445 AND 50-446 LARGE BORE PIPING AND SUPPORTS SDAR: CP-86-36 (INTERIM REPORT)
Gentlemen: I On June 9,1986, we verbally notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). Our latest interim report logged TXX-6358 was submitted on March 27, 1987.
The continuing engineering evaluation has not identified any additional instances-which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications issued to date. The evaluation is continuing and we anticipate submitting our next report by August 20, 1987.
Very truly yours,
' 71 W. G. Counsil BSD/amb Attachment c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 400 Nonh Obve Street LB BI Dallas, Texas 73201 l
~
Attachment to TXX-6505
. June 12, 1987 Page,1 of 1 4
l ATTACHMENT l LARGE BORE PIPE SUPPORT MODIFICATIONS Number of Unit Cateaory Modifications
- 1 Prudent 861 Recent Industry Practice 1346 Adjustment 990 Cumulative Effects 1558 l
2 Prudent 1004 Recent Industry Practice 380 Adjustment 363 Cumulative Effects 622
- I l
Changes in these figures from the last report represent not only identification '
of further modifications but a recategorization of certain supports.
I l
l l
l l
1 I
o ,
F=mm. Log # TXX-6543
==
File # 10110
- J 908.3 E E Ref # 10CFR50.55(e) 1UELECTRIC June 26, 1987 William G. Counsil Eaccmove %ce Presoaent U. S. Nuclear Regulatory Commission Attn: Document Control Desk-Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CLASS 1E BATTERY CHARGER COMP 0NENTS SDAR: CP-86-37 (INTERIM REPORT)
Gentlemen:
On May 14, 1986, we verbally notified your Mr. I. Barnes of a deficiency -
involving firing board assemblies and amplifier boards used in Class IE battery chargers that do not conform to vendor assembly drawings. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report.was logged TXX-6437, dated May 8, 1987.
Our review of the Class 1E procurement processes and affected hardware adequacy is complete. We are currently assessing the safety significance' of this issue.
We expect to submit our next report by July 24, 1987.
Very truly yours, C 7144 W..G. Counsil WJH/gj c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 North Ohve Street LB 81 Dallas. Texas 75201
. . _ J
I Log 0 TXX-6511
, = = = = = =
File # 10110 915.6
?E
~ Ref #10CFR50.55(e)
Z r Z 7UELECTRIC June 12, 1987 William G. Counsil Enecuene Vwe Preudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk l Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 00CKETS NOS. 50-445 AND 50-446 SMALL BREAK LOCA MODE 4 OPERATION SDAR: CP-86-41 (INTERIM REPORT)
Gentlemen:
On May 28, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving small break LOCA evaluations regarding the effects of the operational status of plant equipment during Mode 4 operation. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-6062, dated 3
)
October 29, 1986.
At this time', the issue of Small Break LOCA in Mode 4 has not been resolved by the Westinghouse Owners Group (WOG). The WOG met with the NRC staff on :
November 6,1985, in Bethesda to discuss the WOG's plans for resolving the issue. As a result of questions arising from that meeting, the WOG sent a letter to the NRC dated January 8, 1987, (0G-209) which discussed the feasibility of applying Leak-Before-Break Technology in the resolution of this issue. l All WOG activities have been on hold pending word from the NRC, with the exception of the Operations Subcommittee's effort to prepare procedural guidance which will help operators deal with a LOCA in the shutdown modes.
This interim guidance was sent to WOG representatives in WOG-87-102 dated May 12, 1987, and it is being evaluated by TV Electric.
We anticipate submitting our next report on this issue by February 29, 1988.
Very truly yours, 3 f fiffl?
JCH/gj W. G. Counsil c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) i 400 Nonh Ohve Street LB 81 Dahas. Texas 73201 s
File # 10110
-,_. 909.1 r .= Ref: 10CFR50.55(e) nlELECTRIC William G. Coumu '
a m m weernwem V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CONAX ADAPT 0R MODULES AND ELECTRICAL PENETRATIONS SDAR: CP-86-49 (INTERIM REPORT)
Gentlemen:
On October 10, 1986, we notified you by our letter logged TXX-6018 of a deficiency involving the effects of polar-organic solvents on the sealants of Conax adaptor modules and electrical penetrations which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date. Our most recent interim report was logged TXX-6254 dated January 30, 1987. '
j Of the 11 modules with end sealant crazing, 7 modules were .in Unit 1 and 4 modules were in Unit 2. Nine replacement modules have been received at-CPSES.
The two Heated Junction Thermocouple modules for Unit 2 remain in fabrication at Conax Corporation, awaiting receipt of special Litton Corporation connectors. The Unit I modules have been installed-completing the Unit 1 portion of this issue. The four remaining Unit 2 modules are scheduled for completion by November 30, 1987. We anticipate completion of the final report by December 20, 1987.
We will submit our next report on this issue no later than January 20, 1988. j Very truly yours, ,
/}fNOluts W. G. Counsil JDS/mlh c - Mr. R. D. Martin, Region IV CPSES Resident Inspectors - 3 copies I
l l
400 Nonh Obve Street LB 81 Dallas, Texas 73201 l
M Log # TXX-6434 FE File # 10110
,,_ 903.8
= = Ref. # 10CFR50.55(e) illELECTRIC wimm c. counsii June 17, 1987 Esecutnve Voce Prendent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS SDAR: CP-86-60 (INTERIM REPORT)
Gentlemen:
On September 4,1986 we verbally notified your Mr. I. Barnes of a deficiency
) involving gaps between the polar crane girder support brackets. This is an j
interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted previous interim reports logged TXX-6181, l TXX-6283, and TXX-6434 dated December 18, 1986, February 13, 1987, and May 6, 1987, respectively.
Our response to this issue is not complete at this time. Our next report on this issue will be submitted no later than June 29, 1987.
Very truly yours, O.G. cd W. G. Counsil By:
- D. R. Woodlan Supervisor, Docket Licensing l
l RWH/gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l
, .IDO Nonh Olive Street LB 81 Dallas. Texas 7520I l
r A
M~ Loa # TXX-6434a
,---- % Fiie # 10110
._, ..-- 903.8 '
= = Ref. # 10CFR50.55(e) 1UELECTRIC William G. Counsil '
Enecurne Vice Presnient U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS !
SDAR: CP-86-60 (INTERIM REPORT)
Gentlemen: -
On September 4,1986 we verbally notified your Mr. I. Barnes.of a deficiency involving gaps between the polar crane girder support brackets. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted previous interim reports logged TXX-6181,.
TXX-6283, and TXX-6434 dated December 18, 1986, February 13, 1987, and May 6, 1987, respectively.
Our response to this-issue is not complete at this time. Our next report on this issue will be submitted no later than June 29, 1987.
Very truly yours, O,b.
W. G. Counsil By:
D. R. Woodlan Supervisor, Docket Licensing RWH/gj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 North Olive Street LB 81 Dallas, Tetas 7201 \
.J
- 4 .'
ERRATA SHEET ..
1 Attached is letter TXX-6434a dated June 17, 1987. This letter is being transmitted as a replacement to letter TXX-6434 dated June 17, 1987. (The two letters have the same content.)
Please note that a letter TXX-6434 dated May 6,1987 was previously transmitted, and its content is different from the letters above, i
l 1
1 l
I l
_ _ . _ _ .___________-_-_______._____________________-_3
-M Log # TXX-6544
[~ _-- 9 File # 10110 903.8 r = Ref # 10CFR50.55(e) nlELECTRIC wmim c. counsu une 29, 1987 1
l Emutove Voce Presuknt U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS SDAR: CP-86-60 (FINAL REPORT) ;
1 Gentlemen:
On September 4,1986 we verbally notified your Mr. I. Barnes of a deficiency ;
involving gaps between the polar crane girder and girder support brackets. j This is a final report of a potentially reportable item under the provisions '
of 10CFR50.55(e). Our last interim report logged was TXX-6434a, dated June 17, 1987.
As a result of an observation that gaps between the polar crane girder and girder support brackets for Unit I appeared excessive, an investigation was initiated to assure the design adequacy of girder supports. This evaluation indicated the allowable gap tolerance in the girder seat connection was not addressed in project specifications. Guidance originally documented by Gibbs ,
& Hill letter GHF-2207, dated November 28, 1977, indicated that the seated connection will not require shimming since the load bearing area is at_least the width of the bottom flange of the crane girder. Nine girders were observed with gaps extending under the bottom flange which reduced the load bearing surface to less than the 20 inch flange width.
To assess this issue, engineering performed field verifications of all Unit I runway girder seismic support brackets (28 brackets with 56 runway girder beam ends). Field measurements of gap heights and gap depth were acquired. This resulted in the identification of four worst case beam end seat installations.
A map of the actual load bearing area (including amount and location) was prepared from the field measurements and compared to the calculated load bearing area requirements. All four of the worst case installations were within the calculated requirements and do not exceed code allowables.
We have concluded that the polar crane girders for Unit I are adequately supported without additional shimming. Field verification results and the adequacy of the load bearing surface are documented by analysis and calculations.
400 Nonh Ohve Street LB 81 Dallas. Texas 75201 l j j
' June 29, 1987 Page 2 of 2 The design review performed for Unit I need not be applied to Unit 2. A design change had been issued for Unit 2 which required shimming, thereby eliminating any excessive gaps between the girders and the girder support brackets.
This issue is not reportable under the provisions of 10CFR50.55(e). Records supporting our position are available for your inspectors to review at the CPSES site.
Very truly yours,
, tnd W. G. Counsil By: M.
G. S. Keeley e 4/
4-Manager, Nucleari[icensing RWH/gj l
c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l
l l
l i
I
._.____....___.---_h--
, l Log # TXX-6493 File # 10110
- = = = 903.8 FE Ref # 10CFR50.55(e)
_ _~
r =
TUELECTRIC June 8, 1987 William G. Counsil Eaecutive Dce Prrudem U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS.50-44b AND 50-446 POLAR CRANE SUPPORT STRUCTURE SDAR: CP-86-62 (INTERIM REPORT) l Gentlemen:
On October 3,1986, we notified you by our letter logged TXX-6011 of a deficiency involving a misinterpretation of the polar crane load cases which we deemed reportable under the provisions of 10CFR50.55(e). Our latest interim report logged was TXX-6346 dated March 23, 1987. This is an interim report submitted to status corrective action implemented to date.
In previous reports, we concluded that reduced loading exists for the polar crane support structure. An analysis of the acceptability of the crane rail structure for these reduced loads is continuing.
We will submit our next report no later than September 25, 1987.
Very truly yours, a
) l'Nb W. G. Counsil RWH/gj c - R. D. Martin - Region IV CPSES Resident Inspector - 3 copies 400 sorth onve screet LB 81 Dallas, Texas 75201
I N Log # TXX-6530 FE File # 10110
._ 908.3 l r = Ref # 10CFR50.55(e) I t
TUELECTRIC '
wmiam c. counsa U""* 19' 1987 Esecurne Vice Preudem V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 00CKET NOS. 50-445 AND 50-446 CABLE PULLING TENSION SDAR: CP-86-71 (INTERIM REPORT)
Gentlemen:
On October 2,1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding electrical cable pulling. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-6288, dated February 25, 1987.
As stated in our previous report, our evaluation involves a comprehensive review of vertical cable pulls and subsequent pulls into conduits with previously pulled cables.
The formal calculations for allowable cable tension for vertical cable pulls are in the final stages of review. The field verification effort to obtain cable data for comparison with the revised cable pulling charts is complete.
We are currently evaluating the field data using the revised cable pulling charts derived from the above calculations. Final acceptance of the field data is contingent upon approval of the calculations.
A representative sample of conduits will be selected for testing. These tests will be used to evaluate the issue regarding subsequent pulls into conduits with previously pulled cables.
Upon completion of these activities, our assessment of the technical significance of this issue can be completed. Our next report on this issue will be submitted no later than August 21, 1987.
Very truly yours,
/ 9 W. G. Counsil WJH/dl c - R. D. Martin, Region IV Resident inspectors, CPSES (3) l 400 North Ohve Street LB 81 Dallas, Texas 73201
_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _J
D Log #.TXX-6507 E
y9 File # 10110 903.9
- . Ref. # 10CFR50.55(e) r =
RIELECTRIC June 12, 1987 l William G. Counsil Executsve %ce Prcsodent i
U. S. Nuclear Regulatory Commission f ATTN: Document Control Desk I Washington, DC 20555 !
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 SMALL BORE PIPING AND SUPPORTS SDAR: CP-86-72 (INTERIM REPORT)
Gentlemen:
On June 9,1986, we verbally notified you of a reportable item involving the scope of plant modifications resulting from the. project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item t under provisions of 10CFR50.55(e). Our latest interim report logged TXX-6359 was i submitted on March 27, 1987. j The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications issued to date. The evaluation is continuing and we anticipate submitting our next report by August 20, 1987.
q t
Very truly yours, C
W. G. Counsil BSD/amb Attachment c - Mr. R. O. Martin, Region IV Resident Inspectors, CPSES (3) i I
i 400 North Olive Street LB 81 Da!!as. Texas 73201
..__-__ 2
,, Attachment to TXX-6507 June 12, 1987 Page,1 of 1 ATTACHMENT ,
SMALL BORE PIPE SUPPORT MODIFICATIONS Number of pnit Cateoorv Modifications
- 1 Prudent 62 Recent Industry Practice 256 Adjustment 264 Cumulative Effects 375 2 Prudent 14 Recent Industry Practice 52 Adjustment 68 Cumulative Effects 82
- Changes in these figures from the last report represent not only identification of further modifications but a recategorization of certain supports.
I i
l
l i
~
M Log #.TXX-6497 i == File # 10110 i - j 903.9 r = Ref' # 10CFR50.55(e) 1UELECTRIC wun- c. counsu ""* ' '
uuurm na ercu&na j
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ASME SNVBBER ATTACHMENT BRACKETS SDAR: CP-86-73 (INTERIM REPORT)
Gentlemen:
{
By letter logged TXX-6315, dated March 20, 1987, we notified you of a deficiency involving installation of ASME snubber attachment brackets, which we determined to i be reportable under the provisions of 10CFR50.55(e). This is an interim report provided to status corrective actions.
As previously reported, an evaluation of 165 supports was conducted.in which the predicted pipe movements were compared to the field verified swing Langle data.
The evaluation summary indicated that 18 of these supports were under further evaluation. The evaluation for these supports is complete and a revised summary of the results follows:
- 83 supports were determined to have sufficient field verified swing angle to accommodate the predicted pipe movement.
- 15 supports were determined to be unnecessary in a previously initiated pipe support requalification effort and are being deleted.
- 33 supports are being modified as a result of the pipe support requalification effort (but not as a result of this deficiency).
- 31 supports have been identified as having less available swing angle than required by analysis and are being modified to correct the situation.
- 3 sopports have no safety related function nor impair the safety related function of other components and have therefore been removed from further evaluation.
400 Nonh Ohve Street LH BI Dallas, Texas 75201
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3 TXX-6497 - '
l- June 12, 1987 Page 2 of 2 7
.- 9 l }
Currently, project procedures are under evaluation to determine corrective actions required to prevent recurrence of inadequate swing clearance when a size 3 or 10 snubber is used. As described above, our evaluation of existing installations has identified 31 supports with inadequate swing clearances. Nonconformance reports have been initiated to rework these. supports. This rework is scheduled for completion by January 26, 1988.
We will submit our next report by September 18, 1987.
]
Very truly yours,- j b
W. G. Counsil I By: ,
M[, ' f,/
G. S. Keeley u '-
Manager, Nuclear LicMsing BSD:gj c- Mr. R. D. Martin, Region IV -
i Resident Inspectors, CPSES (3)
I 4
/
M Log # TXX-6494
= "" File # 10110 L :
908.3 E
Ref # 10CFR50.55(e) 1UELECTRIC William G. Counsil June 12, 1987 Executive Voce Presulent
- 9. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 DEVIATIONS IN G0ULD BATTERY RACK DIMENSIONS SDAR: CP-86-76 (INTERIM REPORT)
Gentlemen:
- 0. October 21, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the configuration and dimensions of Gould Battery Racks deviating from drawing requirements. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-6110 and TXX-6407, dated November 20, 1986, and April 29, 1987, respectively. On June 5,1987, we also verbally requested and received from the NRC an extension until June 12,.1987 to respond to this issue.
Class IE battery racks for Trains A and B, which were designed and fabricated by Gould, were found to have configurations and dimensions which deviated from the vendor design drawings. These deviations could result in violation of battery cell spacing. requirements for Class IE batteries. Our review has determined that the conditions are applicable to Units 1 and 2.
Currently our evaluation is in the final stage of review. We are also evaluating the generic '. implications of this issue. Our next report will be submitted by August 10, 1987.
Verytrulyyours,7 l .
. G. Counsil RWH/qj c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 400 Nonh Olive Street LB SI Dallas, Texas 75201 i
'l i
6 Log # TXX-6533 F ~-- File # 10110
.-- 908.3 r r Ref # 10CFR50.55(e)
TUELECTRIC William G. Counsil '
l Eaccume Voce Prcudent l U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 OVER-TORQUED WESTINGHOUSE AR RELAYS SDAR: CP-86-79 (FINAL REPORT)
Gentlemen: '
On November 7,1986, we verbally notified your Mr. T. Westerman of a deficiency involving the possible overtightening of the contact cartridge j terminal screws on the Westinghouse AR Relays. Our last interim report logged was TXX-6363 dated March 30, 1987.
Specifically, the terminal screws had a specified torque requirement of 9.5 0.5 inch-pounds. The torque wrench used at CPSES would have allowed a range of 9.5 1.5 inch-pounds. We have received an evaluation from Westinghouse, l the supplier of the relays, which concludes that a torque range of 8 to 11 inch-pounds is acceptable and will not affect the equipment operability or its qualified life.
! Operability of the installed conditions has been confirmed by the Start-up test group.
l A Design Change Authorization is currently in preparation to increase the !
allowable range to 8 to 11 inch pounds for the subject Westinghouse AR relays.
The change will also be incorporated into site specifications and drawings.
We have concluded that had this condition remained uncorrected, no adverse condition regarding the safety of plant -operations would exist. This issue is not reportable under the provisions of 10CFR50.55(e). .
Documentation supporting this position is available at CPSES for your inspectors review.
Very truly yours, ,
YIXal l W. G. Counsil RDD/dl l
l c - R. D. Martin, Region IV l Resident Inspectors, CPSES (3)
/
l 400 Nonh Olive Street LB 81 Dallas, Texas 75201
-3 Log # TXX-6522 File # 10110 O Ref # 10CFR50.55(e) r =
RIELECTRIC i wmiam c. counsa June 17, 1987 l Esecutwe %cr Presdent U. S. Nuclear Regulatory Commission l Attn: Document Control Desk Washington, DC 20555
SUBJECT:
C0MANCHE PEAK SlEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 PLUG WELDING ON EMBEDDED CHANNELS SDAR:
CP-87-04 (INTERIM REPORT)
Gentlemen:
On March 16, 1987, we verbally notified your Mr. I. 'Barnes of a deficiency involving base metal damage on embedded channels for one of the Unit 2, 6.9Kv switchgear installations. Specifically, cracks have been observed in the plug weld made to repair grout holes in the embedded channels. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Our latest report, logged TXX-6397 was submitted April 15, 1987.
Our response to this issue is not complete at this time. Our next report on this issue will be submitted no later than June 29, 1987.
Very truly yours,
(.J.Co. O l W. G. Counsil By:
D. R. Woodlan Supervisor, Docket Licensing DAR/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3)
I 400 Nonh Olive Street LB 81 Da!!as. Texas 75201
M Log # TXX-6538 22 File # 10110
'.=
_ d
=
Ref # 10CFR50.55(e)
TUELECTRIC Wiuiam G. Coumil '
Execunve %cc Prnvient U. S. Nuclear Regulatory Commission Attn: Document Control Desk j
Washington, DC 20555 l
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 PLUG WELDING ON EMBEDDED CHANNELS SDAR: CP-87-04 (FINAL REPORT)
Gentlemen:
On March 16, 1987, we verbally notified your Mr. I. Barnes of a deficiency involving base metal damage on embedded channels for one of the Unit 2, 6.9Kv switchgear installations. Specifically, cracks have been observed in the weld i
made to repair grout holes in the embedded channels. We have concluded that ~~
this issue is reportable under the provisions of 10CFR50.55(e). The required information follows.
DESCRIPTION The deficiency involves cracked welds found within the embedded channels used for mounting one of the Unit 2, 6.9Kv emergency switchgear installations (Tag No. CP2-EPSWEA-02). In removing seven cabinets in the unit, cracked welds were found on the channels at the point the cabinets were attached. As a result of these conditions, the cabinets were not mounted per design requirements. Nonconformance Report (NCR) CE-87-7-S was issued to document i the deficiency.
1 Review of the attachment detail (Design Change Authorization DCA 20986) indicated that threaded stud and attachment weld locations for equipment were coincidental with grout holes in the embedded channels. The solution provided by the attachment detail specified adding a circular plate of the same 1 l
thickness as the channel, into the hole and welding all around with a partial l penetration weld. Subsequently, the cabinets were attached by filling a hole in the base of the cabinet with weld metal to the added plate.
The cracks observed at the attachment of the cabinets followed the weld of the added plate in approximately a 2-1/2" diameter circle. Since there were no forces acting to propagate the crack into the channel, the worst case would be propagation of the crack in a complete circle. This issue has no technical significance since the structural integrity of the channels would not be affected.
l 400 Nonh Ouve Street LB 81 Dallas. Texas 7320)
1 TXX-6538 June 19, 1987 Page 2 of 2 The design document, DCA 20986, detailing the addition of the circular plate provided inappropriate weld details. The type of weld defined is a partial penetration weld with the depth of the preparation to be the thickness of the base metal (tw is 3/16"). AWS D1.1 states, for joint configuration BTC-P4, base metal thickness shall be' 7/16" minimum. This condition represents a significant deficiency in design which requires repair.
Subsequent cracking occurred because of the type of joint configuration and the increase of heat caused during the welding of the cabinets to the channel.
Failure of this connection between the circular plate and channel would have prevented restraint of the cabinets which could prevent the proper operation of the switchgear equipment.
SAFETY IMPLICATIONS The condition represents a significant deficiency in final design as approved and released for construction. Had the condition remained uncorrected, it could have adversely affected the safety of plant operations.
Failure of the connection between the circular plate and the channel could have prevented restraint of the cabinets during a seismic event and proper operation of the safety related 6.9Kv switchgear.
CORRECTIVE ACTION Attachment of the cabinets in the affected areas (Plug Welds) have been prohibited per design changes which were issued to provide revised details for the installation of the switchgear. For buses IEA1, IEA2, and 2EA2 the DCA's 1
are 31346, 49086, and 28985, respectively. The DCA for bus 2EAl will be issued after switchgear removal and engineering assessment. With the revised installation details, completion of the 6.9Kv switchgear rework activities will be accomplished in accordance with the schedule described for SDAR CP 03. The schedule for completion of activities for Unit 1 is July 17 and Unit 2 is November 27, 1987.
Very truly yours,
/M W. G. Counsil DAR/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3)
c...
M Log # TXX-6508
=M File # 10110 h j 917
= = Ref #.10CFR50.55(e) illELECTRIC William G, Coumil June 9, 1987 Executive Vwe President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 CONTROL OF DESIGN MODIFICATIONS SDAR: C9-87-10 (INTERIM REPORT)
Gentlemen:
On May 11, 1987, we verbally notified your Mr. I. Barnes of_ a deficiency involving design change document control measures which may not have been adequately established prior to the implementation of the current design modification program. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
The scope of this issue affects only Unit 1 Design Modifications issued for systems / subsystems previously turned over to and accepted by CPSES Operations.
The evaluation of this issue with regard to the safety of plant operations has been incorporated into the Corrective Action Program, specifically the Stone and Webster Corrective Action Project. This evaluation is scheduled for completion by July 30, 1987.
We will submit our next report on this issue no later than August 28, 1987.
l l
i Very truly yours, -
5%N W. G. Counsil DAR/gj c - R. D. Martin, Region IV Resident inspectors, CPSES (3) l l ,
i i
400 North Olive Street LB 81 Dallas, Texas 7520) i
4 . . ,
M
"" Log # TXX-6499 )
T: File # 10110
.- 908.3
= = Ref # 10CFR50.55(e) 1UELECTRIC William G. Counsil '
Executive %cr President U. S. Nuclear Regulatory Commission ,
Attn: Document Control Desk '
Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N0. 50-445 DEFECTIVE CIRCUIT CARDS IN BATTERY CHARGERS SDAR: CP-87-11 (INTERIM REPORT)
Gentlemen: !
On May 13, 1987, we verbally. notified your Mr. Ian Barnes of failures experienced in station battery charger circuit cards manufactured by Power Conversion Products, Inc. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). At this point, tne issue is applicable to Unit 1 only.
Specifically,10 failures have occurred in the Unit 1 battery chargers since October 1983, resulting in replacement of 17 circuit cards. The circuit cards in question have been returned to the manufacturer for analysis.
This issue is presently being evaluated for its impact on the safety of plant operations. Our next report will be submitted by August 14, 1987.
Very truly yours, W. G. Counsil
/
! /
G. S. Keeley -
WJH/gj Manager,Nuclearh<ensing c - R. D. Martin, Region IV '
Resident Inspectors, CPSES (3) 400 North Ohve Street LB 81 Dallas, Texas 75201
w.
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"" Log # TXX-6512
-- E File # 10110.
-. _-- 906.2 r = Ref # 10CFR50.55(e) 1UELECTRIC wimun c. counsu ""' ' '
Esecurne %ce Pr=udem V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) 00CKETS NOS. 50-445 AND 50-446 CONTAINMENT P/T ANALYSIS COMPUTER ERROR SDAR: CP-87-12_(INTERIM REPORT)
Gentlemen:
On May 13, 1987, we verbally notified your Mr. Ian Barnes of a deficiency involving,a containment pressure / temperature analysis computer error. We are l reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.
i DESCRIPTION OF PROBLEM During recent validation efforts, an apparent error was observed in the computer program used to analyze containment pressure and temperat'ure l
transients from a spectrum of main steam line breaks (MSLB) as presented in the FSAR table 6.2.1-2. These efforts, conducted as part of the Design Basis Consolidation Program, consist of a comprehensive review of calculation inputs, assumptions, methodology, and results.
The original analysis utilized the computer program CONTEMPT-LT/ MOD 26. The main steam line break of "0.908 ft2 split rupture at 70% power" produced the maximum peak containment temperature of 333 degrees F. Using the same inputs, -
assumptions, and a later version of CONTEMPT-LT/ MOD 26, a peak containment temperature of 366 degrees F (33 degrees F higher) was observed.
Further evaluation initiated to investigate the difference in the peak temperature results revealed that three FORTRAN lines in the HEAT subroutine were left out of the earlier CONTEMPT edition. This error directly affects the results when the Uchida heat transfer option is used.
In order to evaluate the effects of this error, the three FORTRAN Lines were removed from the later edition of CONTEMPT and the "0.908 ft?' main steam line split case was rerun. The results from this operation matched the original results (i.e., peak containment temperature of 333 degrees F). Based on this evaluation, we have concluded that the earlier edition of CONTEMPT LT/ MOD 26, used in the process of establishing current containment pressure I and temperature transients contained the error.
l 400 North Obve Street LB 81 Dallas. Texas 75201
4 .
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TXX-6512 June 12, 1987 Page 2 of 2 The version of CONTEMPT-LT/ MOD 26 used in the earlier analysis was developed by EG&G Idaho, Inc., obtained from the NRC, and used by Gibbs & Hill during the original design phase at CPSES. The application of this computer code in-other nuclear-installation design programs is unknown.
Although our corrective actions are specified below, a preliminary reanalysis has been conducted which indicates the revised peak temperature is actually only 342 degrees F. This peak temperature has been calculated using the LOCTIC computer code (with an 8% revaporization) and revised as-built containment heat sinks.
SAFETY IMPLICATIONS In the event this condition had remained undetected and the original analysis uncorrected, the deficiency could have resulted in the inability of safety-related systems to perform as required following postaccident conditions.
CORRECTIVE ACTION The reanalysis of the main steam line break is scheduled to be completed on July 1, 1987. Upon completion of our evaluation, we will determine corrective actions as required. Our actions will include a proposed revision to Section 6.2.1 of the FSAR after the main steam line break analysis is completed. We will identify all areas / items where the results of the program CONTEMPT-LT/ MOD 26 have been used as a design basis.
We will submit our next report by August 5,1987.
Very truly yours, W. G. Counsil By: .
G. S. Keeley /-
Manager, Nucle y censing JCH/gj c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) i
_______.___u_
M Log # TXX-6519
%9 . - - File # 10110
_ _ 903.9 r = Ref # 10CFR50.55(e) 1UELECTRIC wmiam c. counsu
[ACCUltVC VICC firstdtnf June 15, 1987 U. S. Nuclear Regulatory Commission
' Attn: Document Control Desk j Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CLASS 1E SEPARATION VIOLATIONS SDAR: CP-87-13 (INTERIM REPORT)
Gentlemen:
On May 15, 1987, we verbally notified your Mr. Ian Barnes of a deficiency involving Class IE separation violations resulting from the removal of or modification of non-safety' class cable tray covers after acceptance by QC.
This is an interim report of a potentially. reportable item under the provisions of 10CFR50.55(e).
Our evaluation for possible adverse effects on plant safety and subsequent deportability under the provisions of 10CFR50.55(e) will be performed after analysis of the data obtained during remedial corrective measures relative to the resolution of CAR-064, " Removal of Non-Q Cable Tray Covers".
We anticipate submitting our next report by February 19, 1988.
Very truly yours, ,
9%
W. G. Counsil I
DAR/dl c - R. D." Martin, Region IV Resident Inspectors, CPSES (3)
I l
Am Nonh Olive Stree LR P! Dalle= Tetr '!? "
J
File # 10110 '
_ .- 913.1 r r Ref # 10CFR50.55(e)
TUELECTRIC William G. Coumil '
Execuene voce Preudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 SYSTEM OPERABILITY DURING TESTING SDAR: CP-87-14 (INTERIM REPORT)
Gentlemen: .
On May 20, 1987, we verbally notified your Mr. Ian Barnes of an incident which indicated that administrative controls between Operations and Start-Up personnel were violated. Specifically fire detection alarm systems were rendered inoperative without proper notification of the specified group vested with the responsibility of implementing and maintaining the fire fighting program. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
We are continuing our evaluation and anticipate submitting our next report by August 12, 1987.
Very truly yours, Mtd W. G. Counsil JCH/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 400 Noah Olwe Street LB BI Dallas, Texas 75201 1 i
- =,,
llllllllllllllllllll: Log # TXX-6523
.. 7 --
File # 10110
~__ 903.9 r r Ref # 10CFR50.55(e)
TUELECTRIC wmiam c. counsa June 19, 1987 Execurne %ce Preudem V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 AIR ACCUMULATORS FOR CONTROL VALVES SDAR: CP-87-15 (INTERIM REPORT)
Gentlemen:
On May 20, 1987, we verbally notified your Mr. I. Barnes of a deficiency involving the air accumulators for air operated control valves. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, 22 air accumulators for air operated control valves have been reviewed as a result of installation deficiencies and the lack of removal of desiccant from the accumulator tanks. The installation documents for these accumulators have not been located. Several accumulators in both Units 1 & 2 have been found to contain desiccant although the installations were completed. Also, nonconformance reports have been issued to document these conditions.
Our evaluation of these conditions is scheduled to be completed by July 15, 1987.
Our next report on this issue will be submitted no later than August 22, 1987.
Very truly yours, (L4c W. G. Counsil MCP/dl c - R. D. Martin, Region IV Resident Inspectors, CPSES (3) 4:0 Nonh Olive Street LB SI Da.'las. Texas 73:01 I
- ie M Log # TXX-6549
==
' File'# 10110 l
- 4 907
?~ E Ref: 10CFR50.55(e)
TUELECTRIC wmiam c. counsa "# '
Esecunve %ce Preudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 LIMIT SWITCH WIRING SDAR: CP-87-16 (INTERIM REPORT) .
Gentlemen:
On June 1,1987, we verbally notified your Mr. H. S. Phillips of a deficiency involving conduit and cable which feed safety related valve limit switches and which were not installed in accordance with the wiring drawings. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Our evaluation of this issue is in the final stages of preparation.
Considering the safety functions of the associated valves and components, this issue represents conditions which could adversely affect safe plant operations.
Our next report, providing the results of our evaluation, will be submitted no later than August 7, 1987. .
Very truly yours,
/ PLd4 W. G. Counsil By:. //
G. S. Keeley _ '/ ___
Manager,NuclearLpensing JCH/mlh c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 400 North Olive Street LB 81 Dallas Texas 75201
_