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Summary of 850925 Meeting W/Util,Ornl & Westinghouse at Site to Discuss Inadequate Core Cooling Instrumentation.List of Attendees & Viewgraphs Encl
	ML20136G961
Person / Time
Site:	Catawba
Issue date:	11/07/1985
From:	Jabbour K; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8511220515
	Download: ML20136G961 (28)
	v • d • e

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION h

WASHINGTON, D. C. 20555 g

November 7, 1985 Docket Nos: 50-413 and 50-414 APPLICANT: Duke Power Company FACILITY:

Catawba Nuclear Station, Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING AND SITE VISIT ON INADEQUATE CORE COOLING INSTRUMENTATION (ICCI) - CATAWBA NUCLEAR STATION, UNITS 1 AND 2 General On September 25, 1985, the NRC staff and its consultant visited the Catawba site to meet with Duke Power Company's (Duke or DPC) representatives and to audit the ICCI implementation for Catawba (License condition 2.C.(15) in CatawbaUnit1 License). A list of attendees is included as Enclosure 1.

s Discussion The meeting discussion covered the subcooling margin monitor (SMM), core exit thermocouples (CET), and reactor vessel level instrumentation system (RVLIS).

.'DPC's viewgraphs are included in Enclosures 2 and 3.

Duke's representatives stated that the Westinghouse Integrated Model 86 inadequate core cooling monitor (ICCM) was used for the above three subsystems.

The SMM computer calculates the margin to saturation, and the CRT provides a pressure and temperature display in relation to the saturation curve. The CET connectors, cables and penetrations are environmentally qualified. All sixty-five thermocouples can be displayed on the primary computer CRT. Twenty thermocouples per train are safety-related, are wired to the ICCM, and can be read on the qualified plasma display unit. Alarm is indicated if the average of the five highest thermocouple readings exceeds 700'F. The remaining twenty-five non-qualified thermocouples can be read on a Tractor Model 7201 indicator on the incore instrument panel.

The RVLIS is the standard Westinghouse differential sy(stem for upper head injection plants.

It provides three different loops i.e., upper range, lower range and dynamic head) for each train. The RVLIS' data are used as inputs to the SPDS. RVLIS' accuracy is reasonable when the reactor coolant pumps are not running, but would degrade when the pumps are operating. RVLIS' accuracy improved considerably after Duke's installation of a temporary cooling unit in the switchgear room to maintain a low instrument temperature. Further discussion included RVLIS' operations and Duke's experience with CETs.

8511220515 851107 PDR ADOCK 05000413 P

PDR

November 7, 1985.

Conclusion Duke will infonn the staff of the installation of the qualified cooling unit for the switchgear room. Duke will provide details of the upgrade for Catawba Unit 1 SMM and the existing backup display. A description of the entire ICCM system, including the instrument panel, in Catawba Unit 2 will also be provided.

W. & N. J' Kahtan N. Jabbour, Proiect Manager Licensing Branch No. 4 Division of Licensing

Enclosures:

As stated cc w/ enclosures:

See next page I

O L

Mr. H. B. Tucker Duke Power Company Catawba Nuclear Station cc:

William L. Porter, Esq.

North Carolina Electric Membership Duke Power Company Corp.

P.O. Box 33189 3333 North Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.

Bishop, Libeman, Cook, Purcell Saluda River Electric Cooperative, and Reynolds Inc.

1200 Seventeenth Street, N.W.

P.O. Box 929 Washington, D. C.

20036 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N 3100 Smoketree Ct.

York, South Carolina 29745 P.O. Box 29513 Raleigh, North Carolina 27626-0513 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, Mr. C. D. Markham 101 Marietta Street, NW, Suite 2900 Power Systems Division Atlanta, Georgia 30323 Westinghouse Electric Corp.

P.O. Box 355 Pittsburgh, Pennsylvania 15230 Robert Guild Esq.

P.O. Box 12097 NUS Corporation Charleston, South Carolina 29412 2536 Countryside Boulevard Clearwater, Florida 33515 Palmetto Alliance 2135 i Devine Street Mr. Jesse L. Riley, President Columbia, South Carolina 29205 Carolina Environmental Study Group 854 Henley Place Karen E. Long Charlotte, North Carolina 28208 Assistent Attorney General N.C. Department of.luttiu.

Richard P. Wilson, Esq.

P.O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 S.C. Attorney General's Office P.O. Box 11549 Spence Perry, Esquire Columbia, South Carolina 29211 Associate General Counsel l

Federal Emergency Management Agency Piedmont Municipal Power Agency Room 840 100 Memorial Drive 500 C Street 1

Greer, South Carolina 29651 Washington, D. C.

20472

}

Mark S. Calvert, Esq.

Mr. Michael Hirsch j

Bishop, Liberman, Cook, Federal Emergency Management Agency Purcell & Reynolds Office of the General Counsel 1200 17th Street, N.W.

Room 840 Washington, D. C.

20036 500 C Street, S.W.

i Washington, D. C.

20472 Brian P. Cassidy, Regional Counsel Federal Emergency Management Agency.

Region 1 J. W. McCormach POCH Boston, Massachusetts 02109 I

\\

Enclosure I l

List of Attendees NRC Duke Power Company K. Jabbour T. Deese T. Huang J. Snipes P. Skinner R. Dickard F. Henry, Jr.

ORNL J. Thomas F. Schiffley T. Morelock P. Leroy H. Lee Westinghouse M. Henshaw W. Hammersten J. Fast P. Goodwin

.~-

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CATAWBA INADEQUATE CORE COOLING INSTRUMENTATION IMPLEMENTATION REVIEW MEETING SEPTEMBER 25, 1 985 CATAWBA NUCLEAR STATION 8

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- SUBC00 LING MONITOR

- CORE EXIT THERM 000UPLES

- REACTOR VESSEL LEVEL INDICATOR 9

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PRESENTATION TOPICS EXPERIENCE WITH ICCI TRAINING ON ICCI INCORPORATION OF ICCI INTo EMERGENCY PROCEDURES CONTROL ROOM TOUR W

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ICCI PRESENTATION OUTLINE I. EXPERIENCE A) RVLIS

1) FUNCTIONAL VERIFICATION DONE DURING STARTUP

- EFFECTS OF ALL REACTOR COOLANT PLw C0reINATIONS

- EFFECT OF POWER INCREASE

2) ftNTHLY SURVEILLANCE

3) USED AS BACKUP INDICATION DURING REACTOR VESSEL FILLING AND DRAINING OPERATIONS

- CORRELATION WITH VESSEL LEVEL INSTRUMENTATION B) CORE EXIT THERM 0 COUPLES

1) MormLY SURVEILLANCE

2) INCORE T/C AND RTD CROSS CALIBRATION DONE DLRING STAR 11JP C) SUBC00LINGPDNITOR

1) USEDDURINGHEATUP AND C00UXM EV0WTIONS

2) SURVEILLANCE IS PERFORED ON PRESSURE AND TEWERATURE 4

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II. TRAINING A) RVLIS

1) SR0/R0 TRAINING 3 HOURS B) ACCIDENT MITIGATION

1) CRITICAL SAFETY FUNCTIONS

2) INADEQUATE CORE COOLING

3) SHUTDOWN NUCLEAR INDICATIONS

4) RADIATION MONITORS

- SR0/R0 TRAINING 12 HOURS C) CORE EXIT THERM 0 COUPLES SUBC00 LING MARGIN MONITOR

1) 0AC TRAINING 3 HOURS

2) PRESSURE AND TEWERATURE INDICATIONS USED WITH SATURATIm CURV FOR BACKUP

3) LOCAL CORE EXIT T/C READING D) EfERGENCY OPERATING PROCEDURES

1) CLASSROOM TRAINING - 24 HOURS

2) IN PLANT PROCEUDRE WALK THROUGH 60 HOURS 4

9

III. INCORPORATION OF ICCI INTO EMERGENCY PROCEDURES A) ICCI INCu!DED FROM BEGINNING B) StBC00 LING f%RGIN MONITOR

1) ACTIONS TAKEN BASED ON SUBC00 LING MARGIN INCLUDE

- SAFETY INJECTION TERMINATION

- SAFETY INJECTION REINITIATION

- 7%NUAL REACTOR C00UWT PLw TRIP

2) 9mern ING 7%RGIN INPUTS SPDS C) RVLIS USED FOR DETECTION OF AN ICC EVENT AND DETECTION OF VOIDS IN T E REACTOR VESSEL HEAD.

- INPUTS SPDS D) CORE Ex1T THERM 0 COUPLES ARE USED FOR THE DETECTION OF THE ADVENT OF INADE2] ATE CORE COOLING SITUATIONS

- INPUTS SPDS E) SPECIFIC EP INCORPORATION DOCLMNTATION 9

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1) Suec00 LING MONITOR

2) CORE Ex1T THERK) COUPLE

- 0AC

- LOCAL

3) f%NUAL SUBC00 LING MARGIN CALCULATION

4) RVLIS B) PROCEDURE WALK-THROUGH 9

INADFWATE CORE C00 LING INCORPORATION INTO EERGENCY PROCEDURES EP/1/A/5000/01 - Rx TRIP OR SAFETY INJECTION

- 0*F SUBC00 LING USED FOR NCP TRIP CRITERIA (IF S/I FLOW) 5 15

- 50*F SUBC00 LING USED FOR TERMINATION CRITERIA FP/1/A/5000/1B - SI TERMINATION FOLLOWING SPURIOUS S/I 19

- 0*F SUBC00 LING CHECKED FOR STARTING NCP IF NONE OPERATING 19

- 97% ON RVLIS CHECKED TO ENSURE NO VOIDS IN RV HEAD EP/1/A/5000/1C - HI ENERGY L1NE BREAK INSIDE CONTAINMENT 9

- 0*F SUBC00 LING USED AS TERMINATION CRITERIA FOR S/I E

- 0*F SUBC00 LING USED AS NCP TRIP CRITERIA EP/1/A/5000/1C1 - SI TERMINATION FOLLNING A HIGH-ENERGY LINE BREAK

- 0*F SUBC00 LING CECKED FOR REINITIATION CRITERIA EACH TIE A ll,10,13,15 S/I PUMP IS S/D 28

- MAINTAIN 50*F SUBC00 LING DURING COOLDOWN 29

- IN NO NCP'S ARE RUNNING 0*F SUBC00 LING AND 97% RVLIS USED AS RESTART CRITERIA EP/1/A/5000/1C2 - POST LOCA COOLDOWN AND DEPRESSURIZATION 5

- 0*F SUBC00 LING AND 97% RVLIS USED FOR NCP RESTART CRITERIA 11 0*F SUBC00 LING USED AS CRITERIA TO GAG UHI ISOL VLYS AND ISOLATE CLA 13 0*F StBC00 LING MAINTAINED DURING C00LDOW 13

- IF <97% RVLIS DURING C/D - THE HEAD IS VENTED 16, 17, 22, 26

- DURING TERMINATION OF S/I - SUBC00 LING 0*F IS CHECKED AFTER EACH PUMP IS TURNED OFF - IF <0*F =wm ING S/I FLOW RESTARTED UNTIL>20*F SLBC00 LING 29

- >0*F StBC00 LING USED AS CRITERIA PRIOR TO PLACING ND INSERVICE E

- <0*F SUBC00 LING USED AS NCP TRIP CRITERIA E

- >0*F qwm ING USED AS CHARACTERISTIC OF NATURAL CIRCULATION EP/1/A/5000/1C5 - LDSS OF EERGENCY COOLANT RECIRCULATION 2

- MINItu S/I FLOW IS DETERMINED BY CETAINING SUBC00 LING >0*F AND RVLIS STABLE 5

- SLBC00 LING AND RVLIS USED TO VERIFY S/I FLOW ADEQUATE

- SUBC00 LING >0*F USED TO VERIFY NATURAL CIRCULATION 23

- SUBC00 LING >0*F USED AS CRITERIA FOR PLACING f0 INSERVICE EP/1/A/5000/ID - STEAM LINE BREAK OUTSIDE CONTAINENT 8

- SUBC00 LING >50*F USED AS S/I TERMINATION CRITERIA

- StBC00 LING <0*F AS NCP TRIP CRITERIA F/1/A/5000/1D1 - S/I TERMINATION FOLLOWING STEAM LINE B 1

- SUBC00 LING IS MONITORED DURING C/D AND DEPRESSURIZ 8

- PZR HEATERS ARE OPERAED AS NECESSARY TO CETAIN SA 20, 21

- RVLIS IS USED TO CHECK FOR VOIDS I CONDITIONS E

m INDICATI94 F /1/A/5000/IE - STEAM GENERATOR TUBE RUPTURE 9,14 j

- RVLIS USED TO CECK FOR VOIDS PRIOR TO AND DURING 11 0*F USED FOR WI ISOLATION CRITERIA 13

- StBC00 LING

- StBC00 LING IS MAINTAINED 0*F DURING C00uxw 16,19 i

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- 9 w m ING AND FOR S/I REINITIATION CRITERIA 0*F USED FOR N

- StsC00 LING

- CORE EXIT T/C USED TO DETERMINE C00LDOWN LIMITS F/1/A/5CE/IEl - POST-SGTR ALTERNATE CmJnN AND DEPR 6

8

- WHEN DEPRESSLRIZING RUPTlRED S/G AND NC SYSTEM, MAINTAIN f

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- RVLIS USED TO MONITOR FOR A VOID DURING D i

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.NA1 URAL CIRC 11ATION 3

F/1/A/5N1D - SGTR ALTERNATE C00LD0mi USING BACKFILL 9

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- mille C/D WITH INTACT S/G NC SYS IS DEPRESSURIZED M g

MAINTAINING SUBC00 LING >0 F 10 i

- DURING C/D - NC SYS IS MONITORED FOR VOIDS USIN t

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- 9WM ING USED AS NCP TRIP CRITERIA, S/I REINITIATION, l

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- & W m ING <0*F USED TO DIRECT OPERATOR DIRECT 6

RECOVERY" 8

- SUBC00 LING USED AS CRITERIA TO IS 9, 11

- RVLIS USED >TO MONITOR FOR VOID IN 27,29 17,20,25

- SLBC00 LING E

REINITIATION OF S/l

- StBC00 LING USED FOR NCP TRIP CRITERIA, AND NATURAL CIRC CHARACTERISTICS F/1/A/5C00/1E4 - SGTR WITH CONTINUQUS NC S 2

l

- >0*F SUBC00 LING USED AS CRITER 17, 20 l

REINITIATION CRITERIA l

- >20*F SLsC00 LING USED FOR S/I FLOW REDUCTIm AFTER E, 29, 20, 25, 27 REINITIATION

- TABLE DIRECTION ACTIONS DURING COOLDOWN MITAINING 0 - 5'F SLBC00 LING

- >0*F SLBC00 LING USED AS CRITERIA FOR PLACING ND INSERVICE 56,63 AND ESTABLISHING NORMAL CHARGING

- RVLIS USED TO CHECK FOR VOIDING IN Rx VESSEL AFTER 68 DRPRESStRIZATION F/1/AM - SGTR WITHOUT PRECSURIZER PRESSLRE CONTROL

-< 30*F SLBC00 LING IS MAINTAINED 1

- >0*F StsC00 LING USED AS S/I FLOW REDUCTION CRITERIA AND 4, 7, 12 S/I FLOW REINIATION CRITERIA

- AFTER C00LDOWN RVLIS USED TO CHECK FOR VOIDS IN HEAD 27

- C%RGING USED TO CONTROL PRESSURE AND MAINTAIN SLBC00 LING >0*F 35

- SLBC00 LING USED FOR NCP TRIP CRITERIA, NATURAL CIRCULATION CHARACTERISTIC EP/1/A/5000/IES - SGTR Cm rrW USING l0

- CHARGING IS CONTROLLED DURING C00LDOW4 TO MAINTAIN SUBC00 LING 70*F 6

EP/1/A/5000/2B1 - INADEQUATE CORE COOLING

- RVLIS USED TO CHECK FOR VOIDS - TABLE IS UTILIZED FOR 7

VARIOUS NCP CONFIGURATIONS - APPROPRIATE ACTION AND PROCEDURE INDICATED

- SATLRATION GRAPHICS CHECKED DURING COOLIXM TO VERIFY 18 SLBC00 LING >0

- AFTER COOLDOWN RVLIS D/P AND LOWER RANGE ARE CHECKED 19 AGAINTO INDICATE VOID FORMATION

- >0*F SLBC00 LING USED FOR CLA ISOLATION CRITERIA 21

- AFTER ALL S/G ARE DEPRESSURIZED T0.0 PSIG - RVLIS AND 22, 24 SATURATION GRAPHICS CIECKED FOR PROPER INDICATION

- CORE EXIT T/C CHECKED TO DETERMINE NEED FOR FEED AND BLEED 24,26

- SATURATION GRAPHICS, CORE EXIT T/C, AND RVLIS CHECKED AT END 31,32,33 0F PROCEDURE TO DETERMINE IF " LOSS OF SECONDARY HEAT SINK" NEEDS TO BE REFERENCED F /1/A M - DEGRADED CORE COOLING r

- CORE EXIT T/C, RVLIS USED TO DETERMINE SEVERITY OF PR2LEM 6, 7 AND CORRECTIVE ACTION, TABLE OF EXPECTED RVLIS VALUES UTILIZED

- SATURATION GRAPHICS AND RVLIS ARE USED TO DETERMINE IF C00LDOWN 20 WAS SUCCESSFUL IN ESTABLISHING CORE FLOW

- WHEN S/G'S ARE DEPRESSURIZED TO 0 PSIG, SATURATION GRAPHICS 23, 25 RVLIS, AND CORE Ex1T T/C'S ARE USED TO VERIFY DESIRED RESULTS EP/1/A/5000/2C1 - LOSS OF SECONDARY HEAT SINK

- CORE Ex!T T/C AND SLBC00 LING >0*F USED TO DETERMINE IF HEAT 2,17 SINK IS REQUIRED

- CORE EXIT T/C USED TO DETERMINE S/I FLOW DURING FEED AND BLEED 25

- 50*F SWC00 LING USED AS CRITERIA FOR REDUCING S/I FLOW 30

- RVLIS USED TO CHECK FOR VOIDS AFTER NORMAL CHANGING ESTABLISHED 36 EP/l/A/5000/2D1 - ImINENT PRESSURIZED THERMAL SHOCK CONDITIONS

- SWC00 LING >0*F USED AS l111 ISOLATION CRITERIA 2

- NC SYS IS DEPRESSURIZED TO REDUCE SLEC00 LING <100*F 6

- SWC00 LING >50*F USED AS S/I TERMINATION CRITERIA AND S/I 10, 17 REINITIATION CRITERIA

- SmC00 LING >0*F AND RVLIS>97% USED AS CRITERIA TO START AN NCP 21 EP/1/A/5E0/2D2 - ANTICIPATED PRESSLRIZED THERMAL SHOCK CONDITION

- StsC00 LING >0*F USED FOR NCP START CRITERIA 2

- RVLIS USED TO CHECK FOR VOIDS 2

EP/1/A/5000/2D3 - HIGH PRESSURIZER PRESSURE

- StBC00 LING >50*F USED FOR S/I TERMINATION CRITERIA 5

F /1/A M - VOID IN REACTOR VESSEL

- RVLIS USED TO CHECK IF REPRESSURIZING NCS COLLASPES VOID 10

- >50*F SUBC00 LING USED FOR NCP START CRITERIA 11

- >50*F StBC00 LING IS ESTABLISHED PRIOR TO VENTING VESSEL HEAD 20

-<0*F 9WM ING AND RVLIS(97% USED AS VESSEL VENT TERMINATION 22 CRITERIA

- RVLIS USED TO VERIFY VOIDS ARE REMOVED AFTER VENTING 24 EP/1/A/5000/03-LDSS OF ALL AC POWER

- StBC00 LING USED TO DETERMINE Wi!CH RECOVERY PROCEDURE TO USE 28 AFTER POWER IS RESTORED

- StsC00 LING >0*F USED AS CHARACTERISTIC OF NATURAL CIRCULATION 51 EP/1/A/5000/03A - LDSS OF ALL AC POWER WITHOUT S/I REQUIRED

- SiBC00 LING >0*F USED TO VERIFY PROPER PROCEDURE IS BEING USED 9, E

- SuBC00 LING >0J USED TO VERIFY S/I NOT REQUIRED AFTER RECOVERY 21

- StBC00 LING USED AS INDICATION OF NATURAL CIRCULATION E

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SOURCE OP/1/A/4150/06 OP/1/A/6700/01 UNIT ONE DATA BOOK PREPARED BY Gregfarbin TABLE 2.6.2 RVLIS AP W/VARIOUS APPROVED BY hy PUMP COMBINATIONS EFFECTIVE DATE7 9/2r //6-RVLIS dP (t)

Operating Train "A"

Train "B" NC Pumps 52%

16%

1) A 174 184

2) B 16%

54%

3) C 184 17%

4) D 59%

24%

5) A,B 59%

604

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65%

8) B,C 244 24%

9) B,D 25%

60%

10) C,D 74%

79%

11) A,B,C 75%

40%

12) A,B,D 75%

754

13) A,C,D 40%

78%

14) B,C,D 96%

98%

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