ML20137F656
| ML20137F656 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/21/1985 |
| From: | Tourigny E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512020067 | |
| Download: ML20137F656 (39) | |
Text
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N vember 21, 1985 Docket No. 50-285 LICENSEE: Omaha Public Power District (0 PPD)
Facility: Fort Calhoun Station, Unit No. 1
SUBJECT:
SUMMARY
OF NOVEMBER 8, 1985 MEETING WITH OPPD AND NRC STAFF REGARDING THE RELIABILITY OF THE FORT CALHOUN STATION AUXILIARY FEEDWATER SYSTEM INTRODUCTION At the request of the NRC staff, a meeting was held on November 8,1985 at the NRC offices in Bethesda, Maryland, on the above subject. The purpose of the meeting was to exchange information on licensee and staff initiatives as far as auxiliary feedwater (AFW) systems are concerned.
The meeting was chaired by the NRC Project Manager for Fort Calhoun. The agenda for the meeting is contained in Enclosure 1 Enclosure 2 identifies the meeting attendees. A sunnary of the meeting iallows.
SUMMARY
The licensee presented the Fort Calhoun Station AFW System configuration as it is currently set up and how it looked in the late 1970's. Many upgrades were made to the system during this period of time. An overview of a reliability analysis insofar as the current system is concerned was presented The licensee believes that the system currently has an unreliability of 1x10~5 .
The licensee has also discussed the reliability of the main feedwater system.
The main feedwater system has a reliability which has allowed only one challenge of the AFW system in 12 years of operation. Enclosure 3 contains a copy of the slides that the licensee presented.
The staff gave the licensee an overview of the initiatives in this area. The staff is developing a CRgR papeE5to require all PWRs to have system unreliability in the 10- to 10 range. Most of the operating PWRs have this. The staff noted that it is difficult to show a high reliability with a
. two-pump system. The staff also noted that the electric driven auxiliary feedwater pump can only be driven by diesel generator number 1 should a loss of offsite power occur. The licensee acknowledged this problem and will review it.
Future Work The licensee is currently performing upgrades to the main feedwater system and auxiliary feedwater system. One upgrade to the main feedwater system is to automatically close the main feedwater bypass line valves under an 8512020067 851121 PDR P ADOCK 05000285 FDR L
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engineered safety features actuation signal in order to address a single failure concern that was raised. One upgrade to the auxiliary feedwater system is to provide for easy connections from the fire suppression system to l the emergency feedwater storage tank.
The staff will hold similar meetings with other licensees and will continue to draft the CRGR paper for CRGR consideration. If approved, a Generic l Letter will be issued.
1 i
Ed Tourigny, Project Manager Operating Reactors Branch No. 3 civision of Licensing
Enclosures:
As stated
. cc w/ enclosures:
See next page e \
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" V8/85 njs' ,p,-
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4 MEETING SU M RY DISTRIBUTION Licensee: Omaha Public Power Distric
- Copies also sent to those people on service (cc) list for subject plant (s).
NRC PDR L PDR ORBf3 Rdg ETourigny EButcher BGrimes OELD EJordan, IE ACRS-10 NRC Meeting
Participants:
LRubenstein OParr AThadani i
JWermfel Llieder GEdison CMcCracken JRaval AEl-Bassiani D
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l Enclosura 1 l
l TENTATIVE _! .
AGENDA - i i
- Auxiliary Feedwater System Description
- Pre N!!'7EG-0635 *
- Post huREG-0635
- Current -
- Futurc
- Auxiliary Feedwater System Reliability 7~
- Pre NUREG-0635 -
- Post NUREG-0635 .
- Current
- Future __
NRC Staff Initiatives .
- Summary i -
- Generic Evaluation of Feedwater Transients and Small Break Loss of Coolant Accidentsin Combustion Engineering Designed Operating Plants (NUREG-0635) i (January,1980).
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Enclosure 2
- s. FORT CALHOUN STATION
-' AUXILIARY FEEDWATER SYSTEM
,'= MEETING ATTENDANCE LIST e.
, NAME AFFILIATIDN Ed Tourigny NRR/DL/0RB#3/PM Ed Butcher NRR/DL/ Chief /0RB 3 Les Rubenstein NRR/ CPS ,
O. D.' Parr NRR/DSI/ASB Ashok Thadani
- NRR/ DST J. S. Wermiel NRR/DSI/ASB Lynn Lieder -
NRR/DL/0RB 4 Gordan Edison NRR/0RB 4 Jim Kely 0 PPD Kevin Holthaus OPPD J. K. Gasper ' OPPD D. J. Munderloh OPPD R. L. Andrews "
OPPD Conrad MCCracken NRR/DL/ ORB 4 J. H. Raval , NRR/DSI/4$3 Adol El-Bassioni NRR/ DST /RRAB Richard B. Thornton Arkansas Power & Light w
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Enclosure 3 OMAHA PUBLIC PO'lTER DISTRICT FT. CALHOC.V STATIOX AF'lT SYSTEM AGENDA
- 1. INTRODUCTION J.K. GASPER 1
- 2. AFW CONFIGURATION T.L. PATTERSON
- CURRENT SYSTEM if PRE - 1979 SYSTEM
- 3. RELIABILITY ANALYSIS J.D. KECY 0F CURRENT AFW SYSTEM
- 4. OPPD RESPONSES TO D.J. MUNDERLOH NUREG-0635 SHORT AND LONG TERM RECOMMENDATIONS _
AND NUREG-0737 ITEM II.E.1.1
- 5. OPPD RESPONSE TO K.C. HOLTHAUS NUREG-0737 ITEM II.E.1.2 " AUTOMATIC 1 INITIATION OF AFW" !
- CONTROL GRADE SYSTEM
- " SMART" SAFETY GRADE SYSTF:'
- 6. MAIN FEED WATER SYSTEM T.L. PATTERSON RELIABILITY AT FORT ~
CALHOUN STATION
- 7. CONCLUSIONS J.K. GASPER l
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IXTRODUCTl:0X OPPD CONCERN ABOUT AFW AND MFW RELIABILITY
- IDENTIFIED CONCERN OF BREAK IN STEAM LINE SUPPLYING TURBINE DRIVEN AFW PUMP IN LETTER TO REGION IV IN MAY OF 1982
. UNDERTOOK ADDITIONAL SURVEILi ANCE
. PREFERRENTIAL OPERATION OF ELECTRIC DRIVEN AFW PUMP NOT A HIGH ENERGY FLUID SYSTEM PER BTP ASB 3-1
. NOT A SINGLE ACTIVE COMPONENT FAILURE
. LOW PROBABILITY EVENT l
j IMPROVEMENTS HAVE BEEN MADE IN AFW AND MFW SYSTEMS
- RESPONSIVE TO NRC CONCERNS
- OPPD INITIATED IMPROVEMENTS OPPD HAS FULLY COMPLIED WITH APPLICABLE AFW ITEMS OF NUREG-0635 AND NUREG-0737
- SYSTEM SHOWS THE FT. CALHOUN AFW i SYSTEM MEETS THE UNRELIABILITY ACCEPTANCE CRITERIA 0F SRP 10.4.9 HIGH RELIABILITY MFW SYSTEM ALLOWS FEW CHALLENGES TO THE AFW SYSTEM i 4
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COXCLUSIONS FT. CALHOUN AFW SYSTEM COMPLIES WITH ALL APPLICABLE AFW ITEMS OF NUREG-0635 AND NUREG-0737 THE FT. CALHOUN AFW SYSTEM HAS AN UNRELIABILITY OF APPROXIMATELY 1*10-5 WHICH MEETS THE UNRELIABILITY ACCEPTANCE CRITERIA 0F SRP 10.4.9 W
THE FT. CALHOUN MFW SYSTEM HAS A RELIABILITY WHICH HAS ALLOWED ONLY ONE CHALLENGE OF THE AFW SYSTEM IN 12 YEARS OF OPERATION OPPD HAS RESOLVED ITS CONCERNS RELATIVE TO A RUPTURE OF THE STEAM SUPPLY LINE TO THE TURBINE DRIVEN AFW PUMP AND IS CONSIDERING REMOVING SOME OF THE SURVEILLANCES
~
OPPD BELIEVES THE CURRENT AFW SYSTEM AT FT. CALHOUN STATION IS SATISFACTORY
\ _ _ _ _ _ . _ _ .
Fort Calhoun Simplified Auxiliary Feedwater System 4
EMERGENCY FEEDWATER
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STORAGE TANK
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NATIONAL RELIABILITY EVALUATION PROGRAM 1982.
1985 NUREG-5611 l
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- 1 STANDARD REVIEW PLAN 10.4.9 I.17
,1 SYSTEM DOES NOT DEPEND ON INSTRUMENT AIR 1
FAILED COMPONENTS ARE NOT REPAIRED 1
FAILURES ARE AT THE COMPONENT LEVEL SYSTEM FAILURE IS DEFINED AS THE INABILITY TO DELIVER AFW TO EITHER GENERATOR 4
NO OPERATOR ACTION IS NORMALLY l
REQUIRED l UNAVAILABILITY ~
AND RELIABILITY ARE USED INTERCHANGEABLY O
COMMON MODE FAILURES EXAMINED INDIVIDUALLY
4 .
f l INSUFFICIENT R0W TO EITHER S.G.
l INSUFFICIENT INSUFFICIENT NO PUFS R0W NO RDW OR WATER TO AVAILABLE DOWN STREAM R0W PATH PUMPS OF PUMPS TO EITHER S.G.
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DOK:XAXT CUTSETS
- TURBINE DRIVEN PUMP l MOTOR DRIVEN PUMP l
- PAIR OF MANUAL LOCKED l i
OPEN VALVES (SUCTION SIDE OF PUMPS) '
- PAIR OF CHECK VALVES DISCHARGE SIDE OF PUMPS
- PAIR OF VALVES AT OUTLET OF TANK
- * *e we n. m = ,
e
- g COXTI3ET'XG CCS3TS
- A CONTROL VALVE FROM EACH AUX. FEED LINE PLUS THE CHECK VALVE IN LINE TO MAIN FEED PIPING e
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C0YYOX YOJ3 TAILURES I
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- ACTUATION
- FIRE
- STEAM BREAK IN AUX.
- FEED PUMP ROOM l
- MAINTENANCE AND TESTING e
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o 3ESULTS
- AFW SYSTEM 10 4 -
- MAINTENANCE AND TESTING 10-8
- ACTUATION 10 4
- STEAM BREAK PUMP ROOM 10 10 4 l .
COXCLUSIOX:
AFW SYSTEM RELIABILITY IS '
t WITHIN 1 0 1 0 4. RANGE.
l AFW SYSTEMS 1973 TO 1980: MANUALLY INITIATED SYSTEM.
1980 - 1981: AUTO-INITIATION CONTROL GRADE SYSTEM MET SHORT TERM REQUIREMENTS OF NUREG-0578.
- ACTUATED OFF OF S.G. NR LEVELS COMMON TO RPS. -
- TIME DELAY UTILIZED TO MINIMIZE MSLB CONSEQUENCES - BOTH S.G.'s FED.
1981 - PRESENT: AUTO-INITIATION SAFETY GRADE SYSTEM MEETS LONG TERM REQUIREMENTS 0F NUREG-0737, ITEM II.E.1.2.
L M N 6 M N
I DESIGX REQUIREMENTS AND FEATURES OF SAFETY GRADE AFW SYSTEM i -
DESIGNE0 TO SEISMIC CATEGORY I AND SAFETY GRADE REGUIREMENTS.
AUTO-INITIATION SIGNALS AND CIRCUITS DESIGNED TO SINGLE FAILURE PROOF CRITERIA I 0F IEEE STD. 279-1971 DIVERSE ACTUATION CONSISTING OF TWO INDEPENDENT TRAINS, EACH PHYSICALLY AND ELECTRICALLY SEPARATE.
- 2/4 COINCIDENCE LOGIC
- INPUTS OF WR S.G. LEVEL AND PRESSURE
i
- EACH OF 4 CHANNELS ON SEPARATE BUSES.
ALL SIGNALS AND CIRCUITS POWERED FROM 4
EMERGENCY BUSES.
ELECTRIC DRIVEN AFW PUMP (FW-6) POWERED BY 4160V EMERGENCY BUS AS PART OF POST ACCIDENT
! AUTO LOAD SEQUENCING.
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- concurrent Actuation only occurs if low SG 1evel and pressure signals are Figure I AW Steam Generator Actuation
- Logic
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OPPD Aux. Feedwater Actuation System Logic Diagram sisem Sort sis..
A Sest B
f Press A S.S. _ l PressI 4.&
h a2a Steem Steam Sieom Sert Sisem 2mA4 M Gerk essL A A Gast B 9
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ITEM X.3.3.1.1 LOCK OPEN VALVES. ~
GS-2 PERFORM MONTHLY INSPECTIONS PROPOSE TECH SPECS.
OPPD LETTER -- JANUARY 14, 1980 VALVES HAVE BEEN LOCKED OPEN ,
SURVEILLANCE TEST PREPARED IMPLEMENTED PROPOSED TECH SPECS (SUBMITTED UNDER SEPARATE COVER) .
NRC SER FEBRUARY 2, 1981 - RESPONSE ACCEPTABLE.
l TECHNICAL SPECIFICATION APPROVAL GRANTED BY AMENDMENT 49 ON JULY 25, 1980.
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s ITEM X.3.3.1.2 EMERGENCY PROCEDURES GS-4 SHOULD BE AVAILABLE.
OPPD LETTER -- JANUARY 14, 1980 OPERATING INSTRUCTIONS AND EMERGENCY PROCEDURES TO BE CHANGED.
NRC SER FEBRUARY 2, 1981 - RESPONSE IS ACCEPTABLE. OFFICE OF INSPECTION AND l
l ENFORCEMENT VERIFIED PROCEDURES.
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ITEM X.3.3.1.3 CONFIRM AVAILABILITY OF GS-6 TRAIN AFTER TESTING OR MAINTENANCE.
OPPD LETTER -- JANUARY 14, 1980 1
AVAILABILITY CONFIRMED TECH SPECS PROPOSED NRC SER FEBRUARY 2,1981 - RESPONSE ADEGUATE
- AND ACCEPTABLE. TECHNICAL SPECIFICATIONS
- GRANTED BY AMENDMENT 49 ISSUED ON JULY 25,1980.
1 1
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l ITEM X.3.3.1.4 VERIFY SIGNALS AND GS-7 CIRCUITRY ARE SAFETY i GRADE.
i
- MODIFY IN SHORT-TERM.
I
) UPGRADE IN LONG-TERM.
i OPPD -- SHORT TERM: IMPLEMENTED CONTROL
! GRADE.
)
i LONG TERM: SAFETY GRADE INITIATION.
( NRC SER FEBRUARY 2, 1981 - RESPONSE ACCEPTABLE CONTROL GRADE.
OFFICE OF I AND E - CONTROL GRADE OPERABLE. .
SAFETY GRADE SYSTEM INSTALLED - 1981 OUTAGE.
NRC SER SEPTEMBER i, 1982 - SYSlLM ACCEPTABLE.
ITEM X.3.3.1.5 PREPARE PROCEDURE TO MANUALLY CONNECT PUMP TRAIN TO DIESEL BUS FOLLOWING LOSS OF 0FFSITE POWER.
ADDED FW-6 TO AUTO. SEQUENCERS PROCEDURE NOT REQUIRED NRC SER FEBRUARY 2, 1981 4
PROCEDURE IS NOT REQUIRED.
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I'l EM X . 3. 3.1. 6 RE-EVALUATE POSITION l OF VALVES -- CLOSE l FW-744 AND 745. !
OPPD:
FW-744 AND 745 ARE MAINTAINED NORMALLY CLOSED.
I NRC SER FEBRUARY 2, 1981
- RESPONSE IS ACCEPTABLE.
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ITEM X.3.3.2.1 REDUNDANT LEVEL INDICATION AND ALARMS IN THE CONTROL ROOM.
OPPD:
ADDITIONAL LEVEL TRANSMITTERS, LEVEL INDICATORS, AND ASSOCIATED ALARM WERE ADDED.
NRC SER FEBRUARY 2, 1981 :
RESPONSE IS ACCEPTABLE.
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ITEM X.3.3.2.2 PERFORM 7E-HOUR ENDURANCE TEST.
OPPD LETTER JANUARY 14, 1980 SYSTEM TESTED PER RECOMMENDATIONS 0F X.3.3.2.2. BOTH PUMPS SATIS-l FACTORILY COMPLETED THE REQUIREMENT.
t'
- NRC SER FEBRUARY 2, 1981 RESPONSE IS ACCEPTABLE.
il 0FFICE OF I AND E VERIFIED TEST OBJECTIVES MET.
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ITEM X.3.3.2.3 IMPLEMENT SAFETY-GRADE
' INDICATION OF AUXILIARY '
FEEDWATER FLOW.
OPPD:
NO MODS REQUIRED FOR CONTROL GRADE SAFETY GRADE. UPGRADE - 1981 OUTAGE NRC SER STATES SHORT-TrRM RESPONSE
, IS ACCEPTABLE.
! NRC SER SEPTEMBER 1, 1982 - ACCEPTABLE.
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l ITEM X.3.3.2.4 PLANTS WHICH REQUIRE !
LOCAL MANUAL REALIGNMENT PROPOSE TECH SPECS TO PROVIDE DEDICATED INDIVIDUAL.
l OPPD LETTER JANUARY 14, 1980 LOCAL MANUAL REALIGNMENT l NOT REQUIRED. NO TECH SPECS WERE PROPOSED.
NRC SER FEBRUARY 2, 1981 RESPONSE IS ACCEPTABLE.
l
ITEM X.3.3.3.1 INSTALL SYSTEM TO GL-1 AUTO-INITIATE AFW SYSTEM FLOW.
OPPD:
CONTROL GRADE SYSTEM - 1980 REFUELING OUTAGE SAFETY GRADE - 1981 REFUELING OUTAGE NRC SER SEPTEMBER 1, 1982 RESPONSE IS ACCEPTABLE.
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.. L -_i- K,; I ITEM X.3.3.3.2 INSTALL REDUNDANT GL-2 PARALLEL SUPPLY FLOW PATHS.
l OPPD LETTER JANUARY 14, 1980 REDUNDANT PARALLEL SUPPLY FLOW PATHS WILL BE INSTALLED.
~
OPPD LETTER JANUARY 9, 1981 PROVIDED DESIGN DESCRIPTION.
. INSTALLED - 1981 OUTAGE NRC SER FEBRUARY 2, 1981 RESPONSE IS ACCEPTABLE.
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l ITEM X.3.3.3.3 UPGRADE AFW AUTOMATIC l
GL-5 INITIATION SIGNALS AND CIRCUITS TO MEET SAFETY GRADE REQUIREMENTS.
s OPPD:
UPGRADE - 1981 REFUELING OUTAGE i
NRC SER PROVIDED ON SEPTEMBER i, 1982 1
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O ITEM X.3.3.3.4 EVALUATE CONCERNS:
A. DISCHARGE LINES COMBINE INTD SINGLE HEADER. l BREAK COULD RESULT IN LOSS OF SYSTEM FUNCTION.
B. DESIGN DOES NOT MEET HIGH ENERGY LINE BREAK CRITERIA IN SRP 10.4.9 AND BTP 10-1 A. OPPD LETTER JANUARY 9, 1981 IF BREAK OCCURS IN COMMON HEADER, IT CAN BE MANUALLY ISOLATED AND FLOW RESTORED VIA AN ALTERNATE PATH.
B. TO SATISFY HIGH ENERGY LINE BREAK CRITERIA -- OPPD IMPLEMENTED:
- 1. VALVE FW-746 " LOCKED OPEN". l
- 2. ISI AND TESTING INCREASED.
- 3. NEW CHECK VALVE INSTALLED - 1981 OUTAGE i
. i NRC SER FEBRUARY 2, 1981 - DESIGN MEETS BOTH PARTS OF RECOMMENDATION. -
OPPD RESPONDED TO ENCLOSURE 2 REQUEST FOR FOR INFORMATION REGARDING FLOW i REQUIREMENTS - LETTER JANUARY 13, 1982.
OPPD RECEIVED LETTER DATED MARCH 1, 1982, REGARDING NUREG-0737, ITEM II.E.1.1, AUXILIARY FEEDWATER SYSTEM, NRC STATED ITEM II.E.1.1 0F NUREG-0737 WAS bOMPLETE.
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