ML15244A610
| ML15244A610 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/19/1990 |
| From: | Wiens L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-89-19, NUDOCS 9004060356 | |
| Download: ML15244A610 (27) | |
Text
March 19, 1990 Dockets Nos. 50-269, 50-270 and 50-287 LICENSEE:
Duke Power Company FACILITY: OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3
SUBJECT:
SUMMARY
OF FEBRUARY 23, 1990 MEETING WITH DUKE POWER CONCERNING GENERIC LETTER 89-19 On February 23, 1990, representatives of Duke Power Company (DPC) made a presen tation to the NRC concerning the DPC response to Generic Letter (GL) 89-19 for the Oconee Nuclear Station (ONS). The meeting was held at DPC's request with an objective of informing the NRC staff of planned modifications at ONS to enhance protection from steam generator (S/G) dryout and overfill.
Comments from the NRC staff on the adequacy of the planned modifications in meeting GL 89-19 requirements were also requested.
The DPC presentation began with an overview of the main and emergency feedwater systems, including the current initiation logic for the emergency feedwater (EFW) pumps. A description of the proposed modification to provide additional protection against S/G dryout was then provided.
This modification consisted of an addition to the existing steam generator level control system (SGLCS) to start the two motor driven EFW pumps on low S/G level. This was followed with a description of a proposed modification to provide additional S/G overfill protection. As described, this modification would provide an additional trip of the main feedwater pump (MFW) turbines on high S/G level.
After the presentations, a discussion of the proposed modifications was held.
Of primary concern to the NRC staff was whether a fire could occur that would disable both the MFW control system and the MFW pump trip on high S/G water level.
DPC responded that they could not rule out any possible fire from disabling both circuits, although it would be extremely unlikely.
If such a situation occurred, DPC felt that operators had adequate guidance to take the correct action. The NRC staff closed by indicating that the DPC submittal should indicate that a credible fire scenario would not result in disabling both over fill protection and S/G water level control.
Meeting attendees are listed in Enclosure 1. Handouts distributed by DPC during c4::
the presentation are provided in Enclosure 2.
IO Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1A.
As stated cc w/enclosures:
DISTRIBUTION See next page See attached page OFC :LA:PDII-3
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- LWiens:bld
- DMatthews DATE :1/01 9
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- 3//90 oICIAL RE OR COPY MA Document Name:
OCONEE MEETING
SUMMARY
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DISTRIBUTION FOR MEETING
SUMMARY
DATED:
March 19, 1990 Facility:
Oconee Nuclear Station, Units 1, 2 and 3*
Dofket Fi le NRC & Local PDRs J. Sniezek, 12/G/18 PDII-3 Reading S. Varga D. Matthews L. Wiens R. Ingram OGC E. Jordan, MNBB-3302 ACRS (10)
R. Borchardt, 17/G/21 S. Newberry S. Rhow J. Mauck OCONEE PLANT File
- Copies sent to persons on facility service list
Oconee Nuclear Station Units Nos. 1, 2 and 3 cc:
Mr. A. V. Carr, Esq.
Mr. Paul Guill Duke Power Company Duke Power Company P. 0. Box 33189 Post Office Box 33189 422 South Church Street 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.
Bishop, Cook, Purcell & Reynolds Mr. Alan R. Herdt, Chief 1400 L Street, N.W.
Project Branch #3 Washington, D.C.
20005 U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Mr. Robert B. Borsum Atlanta, Georgia 30323 Babcock & Wilcox Nuclear Power Division Ms. Karen E. Long Suite 525 Assistant Attorney General 1700 Rockville Pike N. C. Department of Justice Rockville, Maryland 20852 P.O. Box 629 Raleigh, North Carolina 27602 Manager, LIS NUS Corporation Mr. H. B. Tucker, Vice President 2536 Countryside Boulevard Nuclear Production Department Clearwater, Florida 34623-1693 Duke Power Company 422 South Church Street Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County CWalhalla, South Carolina 29621
CL 89-19 MEETING ATTENDEES FEBRUARY 23, 1990 NAMES ORGANIZATION Len Wiens NRR/DRP Scott Newberry NRR/SICB Sang Rhow NRR/SICB Jerry Mauck NRR/SICB Ancelo Mercado BW Nuclear Service Tom Coutu Du ke/0NS Bill Rostron Duke/ONS Phil North Du ke/NPD-GO Mike Miller Duke/Des Engr-GO
OCONEE NUCLEAR STATION PLANNED SYSTEM CHANGES FOR GENERIC LETTER 89-19 FEBRUARY 23, 1990
NRC - DUKE MEETING ON GENERIC LETTER 89-19 FEBRUARY 23, 1990 DUKE POWER COMPANY ATTENDEES NAME TITLE LOCATION TOM COUTU UNIT 1 OPERATIONS MANAGER OCONEE TOM CURTIS OCONEE COMPLIANCE MANAGER OCONEE BILL ROSTRON NUCLEAR PRODUCTION SPECIALIST OCONEE MIKE MILLER SENIOR ENGINEER - PROCESS I&C SYSTEMS DESIGN ENGR. - G.O.
PHIL NORTH ASSOCIATE ENGINEER - REGULATORY COMPLIANCE NUCLEAR PROD. -
G.O.
GENERIC LETTER 89-19 AGENDA INTRODUCTION PHIL NORTH EMERGENCY FEEDWATER TOM COUTU SYSTEM OVERVIEW SG DRYOUT PROTECTION MIKE MILLER SG OVERFILL PROTECTION MIKE MILLER DISCUSSION DUKE & NRC
OBJECTIVE OF MEETING ASSURE DUKE AND THE NRC STAFF HAVE A COMMON UNDERSTANDING OF OCONEE'S PLANNED MODIFICATIONS TO ENHANCE STEAM GENERATOR PROTECTION FROM DRYOUT AND OVERFILL
OCONEE EMERGENCY FEEDWATER SYSTEM OVERVIEW FLOW PATHS
- PRIMARY
- ALTERNATE
- OTHER SOURCES INITIATION -
CONTROL
- MOTOR DRIVEN PUMP INITIATION
- TURBINE DRIVEN PUMP INITIATION
- INITIATION ON LOSS OF ICS POWER
MAIN FEEDWATER FLOWPATH UPPEE S.43 Ewon E
F E
EF CL 314 32 p3 O&FROM A
(UIT2 6FEDWTE ASWE 269I E
(LOW HEAD)
E8 3P1 E
3P C~'
FD FDW 391 FDW EO FDWT STA 4EW E
2S 259 GNRAO EFW PalP C
42SFS TOUNIT3 ATO PLp (HG ED
NORMAL EMERGENCY FEEDWATER FLOWPATH UPPER FWFDW A
3110i STEAM APOO RVN D
O 30l GENERATOR 100 3
b TO&A FROME 576 OTHER UITS lIOTWELL c9 MAIN26 PUMIPS P~
TURBINE DRIVEN q
EFVF P
96 EII 57B D
DNE F W102 44E FN...........
384 s
47 P
FOW FDW 382 3~16 1
B MOTOR DRIVEN EFW PUMP (UNI 2)TO UN4IT 2 SSFASW TOUIT 3 (HIGH HEAD)
ALTERNATE EMERGENCY FEEDWATER FLOWPATH UPPER SURGE E
TANK 372 3
A A MOTOR DRIVEN E
E 36 E
EFW PUMP P
38
-WD E
1 6 F
E 1 0E 33 38 TO 8 FROM E
P c
575OlER LTS E
158 sFD 31 32 HOTWELL E
C4 1A0 E
OA3 EWATER ASW 289 TURBINE DRIVEN E
EFW PUMP FDWE P
E4 B
C DW FDW B
391 E
FSE 42 45 GENERATOR P
38231 B MOTOR DRIVEN EFW PUMP 76~~~~S ASW TOW U
- 3.
(HK33 HEAD)
AUXILIARY SERVICE WATER (LOW HEAD) FLOWPATH TANK3
-sD EFUN E
IWGEEAO E
F W
P L1 54 PT3 8
15 FDWO FDWN E
D FNFW EAO 3731 328 PLAP PUMP 36 TClB FUE (LOW HEAD 1 ~
~
~
F PUM F0EWFV 3
V E
96 RO 39 c
0 4
FDW ST A 46 GENEATO C
42 BMUFODFWE 38c1 (U6f02 TO UNI SSF~~
ASWT TOU3 P
PUMP TURBINE(HIG HEAD)
SSF AUXILIARY SERVICE WATER (HIGH HEAD) FLOWPATH UPPER 31T STEAM A MOTORDRINEN E
374 E
38 ED 38GNEAO EFPPP 38 1
100 36 15F 8 FT FDW I
EE 60 E1 32 PMS UM c
AN<
o E oww 391 FDW 40DWE 41 E
DWSTA B PMO DFWEN 31 EFWNPUMP SS FF WTON3 E
rPUMP (HG ED
OCONEE NUCLEAR STATION MOTOR DRIVEN EMERGENCY FEEDWATER PUMP AUTO START LOGIC "IA" MFWPT HOP "B"e MFWPT HOP O
MDEFTWPs "A"
A MFWPT
<7 50 #
FDP MFWPT FDP HOP =HYDRAULIC OIL PRESSURE FDP =FEEDWATER DISCHARGE PRESSURE
OCONEE NUCLEAR STATION TURBINE DRIVEN EMERGENCY FEEDWATER PUMP AUTO START LOGIC "A"
MFWPT
<75#
HOP OR "A"
MFWPT
<750#
FDP ANDT ERFT MFWPT HOP OR "B"l MFWPT FDP HOP =HYDRAULIC OIL PRESSURE FDP =FEEDWATER DISCHARGE PRESSURE
..................... ~~~................................
..................... ~~~................................
OCONEE NUCLEAR STATION EFW INITIATION ON LOSS OF HAND, AUTO, OR ALL ICS POWER LOSS OF
- HAND, AUTO,0OR ALL ICS POWER ACTIVATE TERMINATE INITIATE SECONDARY STEAM MAIN EMERGENCY SIDE GENE]RATOR FEEDWATER FEEDWATER LINVENTORY HIGH LEVEL FLOW
.FLOW CONTROL Tj RP TRIP THE REACTOR TRIP MAIN TURBINE
OCONEE NUCLEAR STATION STEAM GENERATOR DRYOUT PROTECTION CURRENT STATUS EMERGENCY FEEDWATER INITIATED UPON LOSS OF BOTH MAIN FEEDWATER PUMPS SENSED BY:
LOSS OF HYDRAULIC CONTROL OIL PRESSURE TO STOP VALVES OR LOSS OF FEEDWATER PUMP DISCHARGE PRESSURE EMERGENCY FEEDWATER SYSTEM MEETS REQUIREMENTS OF NUREG 0737
OCONEE NUCLEAR STATION STEAM GENERATOR DRYOUT PROTECTION PROPOSED MODIFICATIONS MODIFY EXISTING STEAM GENERATOR LEVEL CONTROL SYSTEM (SGLCS) TO START THE MOTOR DRIVEN EMERGENCY FEEDWATER PUMPS (MDEFWP) ON LOW STEAM GENERATOR LEVEL USING EXISTING SYSTEM TRANSMITTERS AFTER A SHORT TIME DELAY (APPROX. 30 SECONDS).
START OF EFW WILL BE ON A 2 OUT OF 2 LOW LEVEL IN EITHER S/G. BOTH MDEFWP A AND MDEFWP B WILL START AND BE AUTOMATICALLY CONTROLLED BY THE SGLCS.
TIME DELAY REQUIRED TO OVERCOME POST TRIP LEVEL BOUNCES.
DUKE EFW INITIATION AND SGLCS IS NOT AN EFIC SYSTEM AS INSTALLED ON CRYSTAL RIVER 3 OR ARKANSAS NUCLEAR 1.
OCONEE NUCLEAR STATION STEAM GENERATOR DRYOUT PROTECTION DESIGN CONSIDERATIONS FOR PROPOSED MODIFICATIONS INTERNAL MODIFICATIONS TO THE SGLCS.
DIRECT CABLING TO THE MDEFWP'S TO START ON LOW LEVEL.
THE POWER SOURCES ARE THE EXISTING SUPPLIES TO THE SGLCS WHICH ARE FROM THE TWO VITAL BATTERIES FOR EACH UNIT.
THE SGLCS IS LOCATED IN THE CABLE ROOM WHILE THE ICS IS LOCATED IN THE CONTROL ROOM.
DIFFERENT ELEVATIONS IN THE AUXILIARY BUILDING.
OCONEE NUCLEAR STATION STEAM GENERATOR OVERFILL PROTECTION CURRENT STATUS OVERFILL PROTECTION CURRENTLY PROVIDED THROUGH ICS
+ 2 OUT OF 2 LOGIC TAKEN TWICE (2 TRANSMITTERS PER SG)
+ RELIABLE NON-SAFETY GRADE COMPONENTS EXISTING ICS FUNCTIONS DESIGNED TO LIMIT OVERFILL
+ ICS CONTROLS PUMP SPEED AND VALVE D/P
+ SG LEVEL USED AS INPUT TO FEEDWATER CONTROL LOSS OF EITHER HAND AND/OR AUTO POWER TO THE EXISTING SG OVERFILL PROTECTION CIRCUIT MODULES CAUSES TRIP OF THE MAIN FEEDWATER PUMPS. REACTOR THEN TRIPS VIA ANTICIPATORY REACTOR TRIP SYSTEM (ARTS) CIRCUIT AND EFW INITIATED.
ICS/OPERATOR INTERFACE IMPROVEMENTS AS PART OF SPIP
+ ADDITIONAL ALARMS IN THE CONTROL ROOM TO ALERT THE OPERATOR TO ICS POWER FAILURES
+ ADDITIONAL TRAINING IN THE RECOGNITION AND RESPONSE TO ICS POWER LOSS EVENTS S.
O NEE NUCLEAR STATION,&
STEAM ERATOR OVERFILL PROT ION PRESENT TRIP LOGIC AND POWER SOURCE ARRANGEMENT HI-LO ALARM 6613303-i HI-LO ALARM 6613303-1 RE..s E
A REL. SW EA ALARM Ly ALR LOGIC I
24, LOGIC 1
24 6I 2(s S1 3
j 3
1 62-6 26/-z-iv HI Al HIX NIX HI-LO ALARM 6613303-1 H-LO ALARM 6613303-1 L
4 3
1 L
p p
/
2-8/4-2-12 LOGIC IHIX 4IIX NOTES;
- 1.
MODULES 14-2-6&8 ARE POWERED AUTO POWER.
- 2.
MODULES 14-2-10&12 ARE POWERED FROM HAND POWER.
- 3.
MODULES DE-ENERGIZE TO TRIP.
RELAY. FPTX IS POWERED FROM A SEPARATE SOURCE.
- 4.
FPTX ENERGIZES TO TRIP BOTH MAIN FEEDWATER PUMP TURBINES.
FEEDWATER PUMP TURBINE so
+
TRIP CIRCUIT All Booster Pumps Trip Exhaust Uacuu Low Steam Generator Level High Pump Discharge Press.
Low Pump Suction Press.
Low Ovspeed Oil Tank Level Emerg. Low Tvip Test Bearing Oil Pressure Low Logic Manual Trip (control room)
Manual Trip (local panel>
Thrust Bearing Wear TRIP BUS PS -j.
RESET OIL PRESSURE NORMAL TRIP OUERSPEED SV-12 SOLENOID SU-6 TRIP TEST DC-VALUE SOLENOID UALUE
OCONEE NUCLEAR STATION STEAM GENERATOR OVERFILL PROTECTION PROPOSED MODIFICATIONS
- UTILIZE AN ADDITIONAL EXISTING NON-SAFETY GRADE TRIP DEVICE ON MAIN FEEDWATER PUMP TURBINE TO ASSURE TRIP AND TERMINATION OF FORWARD FEEDWATER FLOW
- .~ *.
. ~.
- .*..~.*
- *.*.* ~
O NEE NUCLEAR STATION STEAM WNERATOR OVERFILL PROT ION PROPOSED MODIFICATIONS SHOWING LOGIC AND POWER SOURCE ARRANGEMENT HI-LO ALARM 663303-1 HI-LO ALARM 63303-1 LOIC 1
34LGC I2 5O SETR 5
EL -
//
4I
///X NIX HI-IO AL 63303-HI-LO ARM 663303-1 LOGIC 24-LOGIC I
24 NOTES:
- 1.
MODULES 14-2-6&8 ARE POWERED AUTO POWER.
- 2.
MODULES 14-2-10&12 ARE POWERED FROM HAND POWER.
IT1~~
- 3.
MODULES DE-ENERGIZE TO TRIP.
RELAY.
FPTX1 IS POWERED FROM A SEPARATE SOURCE FROM FPTX.
- 4.
FPTX1 ENERGIZES TO TRIP BOTH MAIN FEEDWATER PUMP TURBINES THE MAIN TURBINE.
TRIP CIRCUIT All Booster Punps Trip Exhaust Uacuum Low Steam Generator Level High Puup Dischange Press.
Low eOvespeed IGenerator Pump Suction Press. Low Trip Test Oil Tank Level Energ. Low High Level Logic Bearing Oil Pressure Low Manual Trip (control voom)
Manual Trip (local panel)
Thrust Bearing Wear RESET OIL PRESSURE NORMAL:
TRIP BUS L-------------------------
PS-11RESET OIL PRESSURE NORMAL OUERSPEED TRIP TRIP TEST SU-12 SOLENOID SU6SOLENOID DC-UALU.E UALIJE
OCONEE NUCLEAR STATION STEAM GENERATOR OVERFILL PROTECTION 2SE 1I Pao SV6 5V8 SVI2 (0/S EXER)
RE T
(TRIP) t TO TRIP ER C2?C pcL0 LSI7 v,
TR IP ED MANUAL TRIP RESET TRIP PISTON TI EA PTRIP RELAY TRIP MECH.
TRIP VALVE OVERSPEED L13 EXERCISER OVERSPEED OVERSPEED GOVERNOR GOVERNOR SVI f NORMAL (LDCK OUT) 1 NOTES:
c2 1
1.
SV6 & SV12 ARE PART OF THE 200PSIG CONTROL OIL SYSTEM J
LOCKOUT WHICH MAINTAINS THE STEAM STOP VALVES OPEN.
- 2.
WHEN THE TRIP HEADER PRESSURE DROPS TO 75PSIG, EFW WILL BE INITIATED.
- 3.
THE OVERSPEED EXERCISER IS TESTED WEEKLY AS PART OF PUMP TURBINE NORMAL FEEDWATER PUMP TURBINE MAINTENANCE.
- 4.
SV13 IS INTERLOCKED THRU SV12 VIA INTEGRAL N.C. CONTACTS DIARAM SO THAT SV13 CAN'T PREVENT A TRIP. THE ADDITION OF SV6 FOR GL 89-19 ASSURES PUMP TRIP.