ML14314A457

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Summary of 930217 Meeting W/Util in Rockville,Md to Discuss Status of Activities Associated w/motor-operated Valve Testing Program at Each CP&L Nuclear Generating Plants. List of Attendees & Viewgraphs Encl
ML14314A457
Person / Time
Site: Harris, Brunswick, Robinson  Duke Energy icon.png
Issue date: 04/26/1993
From: Milano P
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9305030017
Download: ML14314A457 (31)


Text

oV RUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 26, 1993 Docket Nos. 50-261 50-325 and 50-324 50-400 LICENSEE:

Carolina Power & Light Company FACILITIES:

Brunswick Steam Electric Plant, Units 1 and 2 H. B. Robinson Steam Electric Plant, Unit No. 2 Shearon Harris Nuclear Power Plant, Unit 1

SUBJECT:

MEETING

SUMMARY

- MOTOR-OPERATED VALVE TEST PROGRAM Representatives from Carolina Power & Light Company (the licensee) met with the Nuclear Regulatory Commission (NRC) staff on February 17, 1993, at the NRC office in Rockville, Maryland. The meeting was requested by the-NRC to discuss the status of activities associated with the motor-operated valve (MOV) testing program at each of CP&L's nuclear generating plants. The attendees at the meeting are listed in Enclosure 1 and a copy of the slides presented at the meeting are given in Enclosure 2.

In a letter dated February 4, 1993, the NRC staff requested that the licensee include a discussion of the following areas in the meeting presentation:

a. The current status of the CP&L testing program for MOVs, including those actions that remain to be completed and the expected completion dates as these actions relate to the previous response to the NRC's Generic Letter 89-10.
b. The manner in which the MOV test data is being evaluated and how the results are being promptly incorporated into the program.
c. The status of efforts to incorporate feedback of test results into actuator sizing and torque switch settings.
d. A review of the open items from NRC Inspection Report 50-325/91-31, dated December 12, 1991, and an update of the activities and schedules for resolving these concerns.
e. The status of CP&L's response to the 10 CFR Part 21 report on VOTES.

Based on the presentation and the discussions that transpired, the NRC staff believes that the questions were fully answered. In particular, the staff is aware that CP&L is performing a design review of the valve and performance requirements followed by the actual MOV testing where practicable. The overall emphasis of the program is on in-situ testing of the valves and actuators rather than analyses of predicted performance. It is estimated that approximately 50 percent of the MOVs in CP&L's GL 89-10 program are testable.

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-2 Based on the completed MOV tests, it was stated that the MOV sizing and switch setting methodology has been changed from using an original valve factor of 0.3 and a stem friction coefficient of 0.15 to the values of 0.4 and 0.2, respectively. With regard to the testing of butterfly type valves, the program started late due to uncertainties associated with the diagnostic methods and equipment.

After discussing the schedule for completion of the program, the NRC staff requested that the licensee prepare an evaluation that justifies the safety rationale for the likely functioning of those valves not yet tested and setup.

These evaluations may be reviewed by the NRC staff at a subsequent inspection in this area. Overall, the NRC staff believes CP&L is making favorable progress toward resolving the MOV issue at each of the facilities.

Original signed by:

Patrick D. Milano, Senior Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees
2. Slides Presented cc w/enclosures:

See next page DISTRIBUTION:

Docket File J. Mitchell F. Jape, R-II NRC/Local PDRs J. Norberg M. Branch, R-II PD II-1 Reading P. Milano A. Gody, Jr.

T. Murley/F. Miraglia T. Scarbrough L. Plisco, EDO J. Partlow T. Le P. Anderson W. Russell B. Mozafari ACRS (10)

J. Richardson E. Merschoff, R-II OGC S. Varga J. Johnson, R-II E. Jordan G. Lainas

  • See previous concurrence OFFICE LA*

DR PM:PD21:DRPE PM:PD21:DRPE PM:PD21:DRPE NAME PKk4 son PMilano 1

NLe DATE 1/23/93 4/-)2/93 4

92/93 /4ZJ

/93 OFFICE C:EMEB:DET*

AD:PD21:DRPE NAME JNorberg JMitchell I

DATE 4/22/93 2

/2/93 Document Name:

BRN217.MTG

Carolina Power & Light Company cc:

Mr. R. A. Watson Mr. C. R. Dietz Senior Vice President Vice President Nuclear Generation Robinson Nuclear Department Carolina Power & Light Company H. B. Robinson Steam Electric Plant P. 0. Box 1551 P.O. Box 790 Raleigh, North Carolina 27602 Hartsville, South Carolina 29550 Mr. H. Ray Starling Mr. Heyward G. Shealy, Chief Manager - Legal Department Bureau of Radiological Health Carolina Power & Light Company South Carolina Department of Health P.O. Box 1551 and Environmental Control Raleigh, North Carolina 27602 2600 Bull Street Columbia, South Carolina 29201 Mr. H. A. Cole Special Deputy Attorney General Mr. R. B. Starkey State of North Carolina Vice President P.O. Box 629 Nuclear Services Department Raleigh, North Carolina 27602 Carolina Power & Light Company P. 0. Box 1551 U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27602 Resident Inspector's Office H. B. Robinson Steam Electric Plant Resident Inspector/Harris NPS Route 5, Box 413 Harris Nuclear Power Station Hartsville, South Carolina 29550 Nuclear Regulatory Commission Route 1, Box 315B Regional Administrator, Region II New Hill, North Carolina 27562 U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W.

Mr. Gerald E. Vaughn, Vice President Suite 2900 Harris Nuclear Project Atlanta, Georgia 30323 Harris Nuclear Plant P.O. Box 165 Mr. Ray H. Chambers, Jr.

New Hill, North Carolina 27562 General Manager H. B. Robinson Steam Electric Plant Mr. C. S. Hinnant P.O. Box 790 Plant General Manager Hartsville, South Carolina 29550 Harris Nuclear Plant P.O. Box 165 Mr. Dayne H. Brown, director New Hill, North Carolina 27562 Department of Environmental, Health and Natural Resources Mr. R. B. Richey Division of Radiation Protection Vice President P.O. Box 27687 Brunswick Nuclear Project Raleigh, North Carolina 27611-7687 P.O. Box 10429 Southport, North Carolina 28461 Mr. Robert P. Gruber Executive Director Mr. Kelly Holden, Chairman Public Staff - NCUC Board of Commissioners P. 0. Box 29520 P.O. Box 249 Raleigh, North Carolina 27626-0520 Bolivia, North Carolina 28422

-2 Resident Inspector U. S. Nuclear Regulatory Commission Brunswick Steam Electric Plant Star Route 1 P.O. Box 208 Southport, North Carolina 28461 Mr. J. W. Spencer Plant General Manager Brunswick Steam Electric Plant P.O. Box 10429 Southport, North Carolina 28461

MEETING ATTENDANCE LIST CAROLINA POWER & LIGHT COMPANY BRUNSWICK, HARRIS, AND ROBINSON NAME TITLE ORGANIZATION PHONE P. Milano Project Manager NRC/NRR/PD21 504-1457 Ashleigh Lucas VP Engineer CP&L 919-546-6351 Mark Grantham Sr. Engineer CP&L 919-546-2766 Alan Redpath Sr. Engineer CP&L 919-546-4147 Mike Pugh Pr. Engineer CP&L 919-546-6283 R. A. Watson Sr. VP Nuclear CP&L 919-546-4176 D. E. Kanning Sr. Specialist CP&L 919-362-2574 L. S. Rowell Pr. Engineer CP&L 919-546-2770 Steve McCutcheon Eng. Specialist CP&L

.803-383-1493 Tony Groblewski Mgr. Compt-ng.

CP&L 919,457-2143 Tommy Le Project Manager NRC/PDII-1 504-1458 Stephen Koenick Engineer NRR/DE 504-2790 Brenda Mozafari Project Manager NRR/PDII-1 504-2020 Michael Markley Operations Eng.

NRC/RPEB 504-1011 D. J. Nelson Resident Insp.

NRC/R-II 919-457-9531 Dave Waters Brunswick Licensing CP&L 919-546-3678 Frank Jape Section Chief TPS/DRS NRC/R-II 404-331-5540 David McCarthy Mgr. Nuc. Lic.

CP&L 919-546-6901 Gus Lainas A/D RH Reactors NRC/NRR 504-1453 James A. Norberg Chief, Mech. Eng. Br.

NRC 504-3286 Thomas G. Scarbrough Sr. Mechanical Eng.

NRC/NRR 504-2794 Ted Sullivan Section Chief, EMEB NRC/NRR 504-3266 W. T. Russell NRC/ADT/NRR NRC/NRR 504-1274 Jocelyn Mitchell Acting Director NRC/PDII-1 504-1466 B. D. Liaw Deputy Director, DET NRC/NRR/DE 504-3298 J. Richardson Director, DET NRR/DET 504-2722 CAROLINA POWER & LIGHT COMPANY PRESENTATION TO THE NRC

-)N GENERIC LETTER 89-10 MOTOR-OPERA ED VALVE PROGRAM FEBRUARY 17, 1993 T..

GENERIC LETTER 89-10 INTRODUCTION PURPOSE:

To Discuss WITH THE NRc THE CURRENT STATUS OF CP&L's GENERIC LETTER 09-10 PROGRAM FOR MOTOR-OPERATED VALVES:

GENERIC LETTER 89-10 AGENDA INTRODUCTION AND PURPOSE CURRENT CP&L PROGRAK STATUS PLANT SCHEDULES FOR COMPLETION CHALLENGES

,TEST DATA EVALUATION STATUS O TES IESLT LIBERTY 10 CFR PART 21 STATUS OF PLANT INSPECTION REPORT CONCERNS

SUMMARY

GENERIC LETTER 89-10 CP&L PROGRAM CORPORATE MOV TASK FORCE FORMED IN AUGUST 1989 PARTICIPANTS INCLUDE:

PLANT TECHNICAL SUPPORT STAFFS NUCLEAR ENGINEERING NUCLEAR TRAINING NUCLEAR LCENSING PROVIDED VEHICLE-TO ADDRESS MOV ISSUES AND DISSEMINATION OF4 INFORMATION PROVIDED -COSSTENT APPROACH TO GL 89-10 IN SEVERAL AREAs DIAGNOSTID lOVIPMENT TRAIN PROCED~E SHARING OF INDUsmy EXPERIENCE ESTABLISHED-COMMUICATIOR.

LINK BETWEEN PLANTS AND PROVIDES FOROM FOR LESSONS.

LEARNED HAS BEEN RECOGNIZED AS A STRENGTH BY THE NRC EACH PLANT HAS A DEDICATED STAFF OF TECHNICAL SUPPORT MOV ENGINEERS

GENERIC LETTER 89-10 CP&L PROGRAM MOV TRAINING PROVIDED BY NUCLEAR TRANING SECTION GENERIC MOV TRAXNING NOR.; CRAFT PERSONNEL (INPO ACCREDITED)

TRAINING ON DIAGNO TIc EaurPMEN TEST PERSONNEL TRAVELING MAINTENANCE CREW DEDICATED TO MOV TESTING PROVIDES AUGMENTED SUPPORT FOR ALL THREE PLANTS DURING REFUELING OUTAGES WHILE.

TESTING ACTIVITY OCCURS ESTABLISHES A CONSISTENT, KNOWLEDGEABLE TESTING CREW WELL VERSED IN MOV TESTING INDUSTRY INVOLVEMENT CP&L PERSONNEL HAVE BEN.ANY INDUSTRY GROUPS FORMED-TO S

DUSTRY ISSUES BWROG IEEE MOV USERS GROUP EPRI DUKE/KALSI

Generic Letter 89-10 Current CP&L Program Status BNP 238 RNP 87 HNP 116 Number of Valves in Program

Generic Letter 89-10 BNP 156 BNP 82 RNP 70HP8WNP 2

RNP 17 Gate/Globe Valves Butterfly Valves

Generic Letter 89-10 Design Basis Calculations 96 97 100 80 65 4

60 _

56 a)

CD) a-40 20 0

.0 0

BNP HNP RNP U Gate/Globe & Butterfly

Generic Letter 89-10 DP Testable Gate/Globe Valves BNP 78 RNP 50 HNP 65

Generic Letter 89-10 Gate/Globe Valve DP Testing 100 92 80 -

72

0)
  • 60
0.

E 42 O 4 0...

20 0

BNP HNP RNP U 33/78 4t 60/65 U 36/50

GENERIC LETTER 89-10 BNP STATUS UNIT ONE REFUEL OUTAGE FORCED OUTAGE VALVES TO BE REFUEL OUTAGE REFUEL OUTAGE 9/90 TO 3/91 4/92 to 6/93 TESTED ON LINE 9/93 to 11/93 3/95 to 6/95 TESTING COMPLETED OR 15 41 10 34 19 SCHEDULED NUMBER OF GATE/GLOBE 15 30 10 23 0

VALVES NUMBER OF BUTTERFLY 0

11 0

11 19 VALVES RUNNING PERCENTAGE OF 13%

47%

55%

84%

100%

PROGRAM PROJECTED TO BE COMPLETE UN IT TWO REFUEL OUTAGE FORCED OUTAGE VALVES TO BE REFUEL OUTAGE REFUEL OUTAGE 9/91 TO 3/92 4/92 to 3/93 TESTED ON LINE 3/94 to 6/94 9/95 to 12/95 TESTING COMPLETED OR 21 32 10 35 21 SCHEDULED NUMBER OF GATE/GLOBE 21 23 10 24 0

VALVES NUMBER OF BUTTERFLY 0

9 0

11 21 VALVES RUNNING PERCENTAGE OF 18%

45%

53%

82%

100%

PROGRAM PROJECTED TO BE COMPLETE

GENERIC LETTER 89-10 HNP STATUS REFUEL OUTAGE REFUEL OUTAGE VALVES TO BE REFUEL OUTAGE 3/91 TO 5/91 9/92 TO 12/92 TESTED ON LINE 3/94 TESTING COMPLETED OR 41 38 23 14 SCHEDULED NUMBER OF GATE/GLOBE 41 38 0

10 VALVES NUMBER OF BUTTERFLY 0

0 23 4

VALVES RUNNING PERCENTAGE OF 35%

68%

88%

100%

PROGRAM PROJECTED TO BE COMPLETE

GENERIC LETTER 89-10 RNP STATUS REFUEL OUTAGE REFUEL OUTAGE VALVES TO BE REFUEL OUTAGE 9/90 TO 3/91 3/92 TO 6/92 TESTED ON LINE 9/93 TO 11/93 TESTING COMPLETED OR 13 39 14 21 SCHEDULED NUMBER OF GATE/GLOBE 13 39 4

14 VALVES NUMBER OF BUTTERFLY 0

0 10 7

VALVES RUNNING PERCENTAGE OF 15%

60%

76%

100%

PROGRAM PROJECTED TO BE COMPLETE

GENERIC LETTER 89-10 CHALLENGES ELECTRICAL POWER FACTOR ASSUMPTIONS METHODOLOGY FOR MOTOR TORQUE CALCULATIONS HAS BEEN REVISED TO INCORPORATE LIMITORQUE/RELIANCE RECOMMENDATIONS ON POWER FACTOR ELECTRICAL MOTOR TORQUE CALCULATIONS WILL BE REVISED BY 9/1/93 MECHANICAL CALCULATIONS WILL BE REVISED BY 12/31/93

GENERIC LETTER 89-10 CHALLENGES DEVELOPMENT OF JUSTIFICATION FOR VALVES NOT DP TESTED CONTINUE TO MONITOR INDUSTRY INITIATIVES CONTINUE TO ANALYZE CP&L DP TEST RESULTS TO FURTHER VALIDATE SET-UP METHODOLOGY EVALUATE RESULTS FROM EPRI PERFORMANCE PREDICTION PROGRAM

GENERIC LETTER 89-10 CHALLENGES BUTTERFLY VALVE TESTING TESTING OF BUTTERFLY VALVES HAS BEEN FACTORED INTO SCHEDULES FOR EACH PLANT WHERE PRACTICABLE, VALVES WILL BE DP TESTED ALTERNATIVE METHODS MAY BE USED IF JUSTIFIED

GENERIC LETTER 89-10 TEST DATA EVALUATION TEST DATA IS REVIEWED ON SITE TO ENSURE PROPER OPERATION OF VALVE AND VALIDATION OF SETUP PARAMETERS (I.E. VALVE OPENS/CLOSES, PROPER THRUST DELIVERED, OPERATING ANOMALIES EVALUATED)

OPERABILITY CONCERNS PROMPTLY ADDRESSED DP TEST DATA IS AGAIN REVIEWED IN THE CORPORATE OFFICE TO VALIDATE ASSUMPTIONS IN DESIGN BASIS CALCULATIONS ON VARIOUS VALVE CHARACTERISTICS SUCH AS VALVE FACTOR AND STEM FACTOR; THIS IS DOCUMENTED IN A FORMAL WRITTEN REPORT ACTUAL VALVE CHARACTERISTICS ARE FACTORED INTO ORIGINAL SWITCH SETTING CALCULATION

GENERIC LETTER 89-10 STATUS OF TEST RESULTS IN JANUARY 1992, CP&L INCREASED CONSERVATISM IN SWITCH SETTING CALCULATIONS VALVE FACTOR FOR GATE VALVES RAISED STEM FRICTION FACTOR INCREASED CALCULATIONAL METHODOLOGY REVISED TO INCORPORATE RESULTS OF MUG/INEL TESTING ON VOTES DIAGNOSTIC EQUIPMENT ACCURACY AN ADDITIONAL PERCENTAGE ADDED FOR TORQUE SWITCH REPEATABILITY DYNAMIC TESTING IS REVIEWED FOR IMPACT DUE TO RATE OF LOADING RESULTS HAVE NOT PROVIDED INFORMATION TO SUGGEST THAT THRUST SETUP METHODOLOGY SHOULD BE REVISED

GENERIC LETTER 89-10 LIBERTY 10 CFR PART 21 CP&L BEGAN USING VOTES VERSION 2.3 UPON ITS RELEASE AND PARTICIPATED IN THE SYMPOSIUM IN ATLANTA CONDUCTED BY LIBERTY LIBERTY HAS ATTENDED CP&L TASK FORCE MEETINGS, MOST RECENTLY ON FEBRUARY 12, 1993 To ADDRESS QUESTIONS ON NEW SOFTWARE REREVIEW OF ALL TESTS USING OLDER SOFTWARE HAS BEGUN AND WILL BE COMPLETED BY 7/1/93

GENERIC LETTER 89-10 BSEP CURRENT STATUS OF CONCERNS ADDRESSED BY IER 91-31 CONCERN #2 CONCERN:

PREVENTIVE MAINTENANCE NOT REQUIRED TO BE COORDINATED WITH GL 89-10 TESTING STATUS:

OPEN RESOLUTION:

PREVENTIVE MAINTENANCE IS BEING COORDINATED AND THE PROCESS WILL BE FORMALIZED BY 3/29/93.

GENERIC LETTER 89-10 BSEP CURRENT STATUS OF CONCERNS ADDRESSED BY IER 91-31 CONCERN #11 CONCERN:

No PERIODIC TESTING OR INSPECTIONS OF MOV THERMAL OVERLOAD PROTECTION DEVICES STATUS:

OPEN RESOLUTION:

PROCEDURE TO PERFORM APPROPRIATE TESTING OR INSPECTION OF OVERLOADS IS SCHEDULED FOR COMPLETION BY 6/30/93.

GENERIC LETTER 89-10 SHNPP CURRENT STATUS OF CONCERNS ADDRESSED BY IER 92-06 CONCERN #3 CONCERN:

STATIC TESTING Vs. D/P TESTING FOR PERIODIc REVERIFICATION STATUS:

OPEN RESOLUTION:

AWAITING INDUSTRY RESOLUTION

GENERIC LETTER 89-10 SHNPP CURRENT STATUS OF CONCERNS ADDRESSED BY IER 92-06 CONCERN #5 CONCERN:

VALVE MISPOSITIONING STATUS:

OPEN RESOLUTION:

AWAITING INDUSTRY RESOLUTION

GENERIC LETTER 89-10 SHNPP CURRENT STATUS OF CONCERNS ADDRESSED BY IER 92-06 CONCERN #6 CONCERN:

USE OF A.4 POWER FACTOR STATUS:

OPEN RESOLUTION:

ELECTRICAL CALCS WILL BE REVISED BY 9/1/93 TO INCORPORATE HIGHER POWER FACTOR

GENERIC LETTER 89-10 HBR CURRENT STATUS OF CONCERNS ADDRESSED BY IER 91-201 CONCERN #2 CONCERN:

VALVE MISPOSITIONING STATUS:

OPEN RESOLUTION:

AWAITING INDUSTRY RESOLUTION

GENERIC LETTER 89-10 HBR CURRENT STATUS OF CONCERNS ADDRESSED BY IER 91-201 CONCERN #10 CONCERN:

No PERIODIC TESTING OR INSPECTIONS OF MOV THERMAL OVERLOAD PROTECTION DEVICES STATUS:

OPEN RESOLUTION:

A PROCEDURE FOR TESTING OF ALL THERMAL OVERLOAD RELAYS ASSOCIATED WITH 89-10 VALVES IS BEING WRITTEN AND ALL TESTING IS SCHEDULED FOR COMPLETION DURING RFO-15.