ML20155A113

Summary of 880921 Meeting W/Util in Region II Ofcs Re Status of Licensee Actions in Response to IE Bulletin 85-003.List of Attendees & Viewgraphs Encl

ML20155A113
Person / Time
Site:	Hatch
Issue date:	10/03/1988
From:	Crocker L Office of Nuclear Reactor Regulation
To:	Matthews D Office of Nuclear Reactor Regulation
References
IEB-85-003, IEB-85-3, NUDOCS 8810050210
Download: ML20155A113 (42)

Text

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UNITED STATES

[f g NUCLEAR REGULATORY COMMISSION L- 8 W ASHING TON, D. C. 20066 t

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October 3, 1988 Docket Nos. 50-321 -

50-3.66 l MEMORANDUM FOR: David B. Matthews, Director I Project Directorate !!-3 Division of Reactor Projects !/!!

FROM: Lawrence P. Crocker, Project Manager  :

Project Directorate !!-3  ;

Division of Reactor Projects !/!!

SUBJECT:

MEETING

SUMMARY

On September 21, 1988, a meeting was held at the NRC Region !! office with representatives of Georgia Power Company to discuss the status of the licensee's actions in response to NRC Bulletin 85-03 for the Hatch Nuclear t Plant. Enclosure 1 provides a listing of the attendees. The meeting had been i arranged at the request of the licensee to obtain clarification regarding the '

Bulletin requirements.

,r The original Bulletin 85-03 was issued on November 15, 1985, and was intended  !

to ensure that licensee developed and implemented a program to ensure that  :

switch settings on certain safety-related, rotor-operated valves are selected, j set and maintained correctly to accorrnodate the maximum differential pressures '

I expected on these valves during both normal and abnormal events. Supplement 1 to Bulletin 95-03 was issued on April 27, 1988 to clarify which valves on BWRs  !

were to be included in the progran and to clarify the meaning of a phrase in the original bulletin, i The licensee responded to the initial bulletin by letters dated October 2 l 1986, March 12, 1987 and April 8,1987. On April 4,1988, the staff requested i additional information regarding certain aspects of the licenswe's program.  !

The licensee responded to the RAI by letter dated May 4, 1988. Included in [

the May 4 response was a request to meet with the staff to explain the t licensee's program. The September 21 meeting was held in response to that request. In the meantime, the licensee also had responded to Suppleu nt I to '

Bulletin 85-03 by letter dated May 27, 1988.

'The licensee briefed the staff on the program developed to respond to Bulletin [

85 03, including the methodology used to identify valves and determine the maximum differential pressures, the establishment of correct switch settings, l testing results to date, and the program and schedule for long-term i complience. A copy of the briefing charts is provided at Enclosure 2.  ;

The staff informed the licensee that the bulletin is being supersedeo by a i generic letter, to be issued within a few renths, which will address the -

problems the staff has observed end provide guidance on the actions needed for 4 long-term approach tu resolving potential motor-uperated valve problems.

8810050210 881003 PDR ADOCK 05000321 )

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2 The licensr.e has almost completed the testing on Unit 2 valves to meet the original scope of Bulletin 85-03. However, completion of the Unit 2 valve testing to meet the scope of Supplement 1 to the bulletin will have to await ,

the next Unit 2 maintenance / refueling outage in the Spring of 1989. Testing  ;

of all Unit I valves is scheduled to be completed during the maintenance /  !

refueling outage which began on September 28, 1988. The licensee agreed to l submit the test data as it becomes available rather than to hold it for a l complete, final report.

f.A .

Lawrence P. Crocker, Project H)tager i Project Directorate !!-3 l Division of Reactor Project $ l/l!

Enclosures:

1. Attendance List

2. Briefing slides

• l ec: w/ enc'iosures  !

See next page f I

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2 October 3, 1988 The licensee has almost completed the testing on Unit 2 valves to meet the original scope of Bulletin 85-03. However, completion of the Unit 2 valve testing to meet the scope of Supplement 1 to the bulletin will have to await the next Unit 2 maintenance / refueling outage in the Spring of 1989. Testing of all Unit i valves is scheduled to be completed during the maintenance /

refueling cutage which began on Septenter 28, 1988. The licensee agreed to submit the test data as it becomes available rather than to hold it for o complete, final report.

Lawrence P. Crocker, Project Manager Project Directorate II-3 Division of Reactor Projects 1/11

Enclosures:

1. Attendance List

2. Briefing slidec cc: w/ enclosures i See next page DISTRIBUTION FOR NEETING

SUMMARY

DATED: September 21, 1988 Docket Fila NRC POR Local PDR J PDi!-3 Reading M. Rood 14-H-25 L. Crocker 14-H-25 OGC 15-B-18 E. Jordan MNBB-3302 5 Grimes 9-A-2 RKiessel 11-A-1 ACRS(10) H-1016 Frank Jape RII Stephen Tingen .s

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PDil-k  ;\

!!-3 LCrocker:Is DMatthews 10/h'88 10/ /88 3

Mr. W. G. Hairston, III Edwin I. Hatch Nuclear Plant, Georgia Power Company Units Nos. 1 and 2 cc:

G. F. Trowbridge, Et,q. Mr. R. P. Mcdonald Shaw, Pittrnan, Potts and Trowbridge Executive Vice President -

2300 N Street, N. W. Nuclear Operations Washington, D.C. 20037 Georgia Power Company P.O. Box 4545 Mr. L. T. Gucwa Atlanta, Georgia 30302 Engineering Departrnent Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302 Nuclear Safety and Compliance Manager Edwin I. Hatch Nuclear Plant Georgia Pcwer Company P. O. Box 442 Baxley, Georgia 31513 ftr. Louis B. Long Southern Company Services, Inc.

P. O. Box 2625 Birmingham, Alabama 35202 Resident Inspector U.S. Nuclear Regulatory Comission Route 1, Box 725 Baxley, Georgia 31513 Regional ,Jninistrator, Region II U.S. Nuclear Regulatory Comission 101 flarietta Street, Suite 2g00 Atlanta, Georiga 30323 Mr. Charles H. Badger Office of Planning and Budget Room 610 270 Washington Street, S.W.

Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter, Comissioner Department of Natural Resources i 270 Washington Street, N.W.

Atlanta, Georgia 30334 Chairman Appling County Comissioners

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1 Baxley, Georgia 31513 l

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, ENCLOSURE 1 1 MEETING i MOTOR-OPERATED YALVES .

BULLETIN 85-03

, , 21 SEPTEMBER 1988 i

NAME POSITION REPRESENTING 1

1 Larry Crocker Project Manager, Hatch NRC, NRR  !

4 Frank Jape TPS/ ORS NRC, Ril l 4 Richard J. Kiessel Sr. Mech. Eng. NRR/0GC8  !

Stephen Tingen TPS/DRS/NRC NRC, R!!

Dan Warsing Tech. Ngr. Lirnitorque i Dave Midlik Lesd Engineer 85-03 Hatch GPC0 t 4 Chris Sorensen IAC ENG. SCSI  !

Gene T41 ton GPC-Corp. Engr. GPC l Brad Harkins SCSI-AE SGS! >

q Jim Heidt Lic Mgr. - Hatch GPC (

) Ken McElroy Lic. Engineer - Hatch GPC j i

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• ENCLOSURE 2 i

, E. I. HATCH NUCLEAR PLANT

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IEB 85-03 l l I

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MOV TESTING  :

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! SEPTEMBER 21,1988 l 4 ,

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PURPOSE OF MEETING OBTAIN NRC CONCURRENCE ON GPC'S BULLETIN 85 - 03 PROGRAM PROGRAM OVERVIEW BWR OWNERS GROUP METHODOLOGY FOR OP CALCULATIONS INDUSTRY STANDARD (LIMITORQUE) SIZING EQUATIONS LIMITORQUE DIAGNOSTIC EQUIPMENT FOR SIGNATURE ANALYSIS LIMITED DP TESTING PROGRAM STATUS UNIT 2 TESTING COMPLETE FOR ORIGINAL BULLETIN SCOPE UNIT 1 TESTING STARTED (OUTAGE BEGINS 9-28-88) l

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AGENOA NRC/GPC MEEJING ON PLANT HATC M LLETIN 85-03 PROGRAM SEPTEMBER 21. 1988 - ATLANTA NRC REGION II 0FFICES 9:00 - 12:00 o ADGENDA o PROGRAM DESCRIPTION HETHODOLOGY TO IDENTIFY VALVES AND DETERMINE HAXIMUM O!FFERENTIAL PRESSURE (DP)

ESTABLISHMENT OF CORRECT SHITCH SETTINGS o SHITCH FUNCTIONAL REVIEH o THRUST CALCULATIONS o OPERATOR CAPABILITY

- TESTING RESULTS o OVERVIEN o AS-FOUND CON 0! TION o STATIC AND DP SIGNATURE ANALYSIS

- LONG-TERM COMPLIANCE o PROCEDURES o PROACTIVE EFFORTS

- SCHEDULE o NRC FUTURE PLANS o

SUMMARY

/0 PEN ITEMS

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I l SUBJECT SYSTEMS l

l The Bulletin addresses high-pressure l coolant injection systems and emergency l feedwater systems which are to be tested

! in accordance with 10 CFR 50.55a(g?

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The applicable systems at Plant Hatch

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i i HIGH PRESSURE COOLANT INJECTION REACTOR CORE ISOLATION COOLING I

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i SUBJECT VALVES i -

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j Valves which are considered to be included under the scope of the Bulletin are those which are required to be

, tested in accordance with Section XI of l the ASME Boiler and Pressure Vessel Code.

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SWITCH SETTINGS ADDRESSED

. OPEN TORQUE SWITCH

= OPEN TORQUE SWITCH BYPASS

. CLOSE TORQUE SWITCH

. CLOSE TORQUE SWITCH BYPASS

. OPEN LIMIT SWITCH ,

, . CLOSE LIMIT SWITCH ,

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. THERMAL OVERLOADS i

OPEN TORQUE SWITCH .

l Jumpered from circuit. i i

i Opening Capability is limited to the  !

l motors ability to develop the maximum required torque when coupled with the l operator gearing. '

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OPEN TORQUE SWITCH BYPASS Setting not required.

Permanent jumper installed around open torque switch. l I

e e p CLOSED TORQUE SWITCH Used to stop travel in the closed direction.

Set to assure that the valve will close against the maximum DP and that damage does not occur to:

Operator thrust components Operator torque components ,

Valve thrust components Valve torque components

1 CLOSED TORQUE I; SWITCH BYPASS .

i Set to bypass the closed torque switch during the initial 1/8" of travel to i

assure that valve clears backseat.

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OPEN LIMIT SWITCH Set to limit travel in the open i

direction to prevent backseating due to inertia.

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CLOSED LIMIT SWITCH Setting not required.

! All control in the close direction is by j the close torque switch.

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l THERMAL OVERLOADS l

! Setting not required.

Overloads bypassed per NRC Regulatory Guide 1.106 l

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The valves were reviewed to establish:

Events that require operation 1

Valve functions Required safety actions

Events that impose maximum DP l;

Location of maximum DP J

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PLANNED EVENTS

• Refueling outages

• Achieving Criticality

. Heatup

• Power Operation

• Achieving Shutdown

. Cooldown

CONDITIONS CONSIDERED i

IN DP CALCULATIONS .

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• Maximum Reactor Vessel Pressure .

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• Maximum Equipment Output i

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• Hydrostatic Head

• Atmospheric Pressure

• Water Hammer

• Velocity Head  ;

I l . LOCA Related Pressure i

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MINIMUM THRUST REQUIREMENT

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'I Forces which must be overcome to operate

! valve:

Stuffing Box Load Stem Load j Differential Pressure Load

STUFFING BOX LOAD 1

1 i Dependent upon stem diameter.

Assigned the following loads:

Up to 1" 1000 #

Up to 1-1/2" 1500 #

Up to 2-1/2" 2500 #

l Up to 4" 4000 #

{ Above 4" 5000 #

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l STEM LOAD The force required to drive the valve j stem into the valve.

l Neglect if line pressure < 500 PSIG l

For line pressure > 500 PSIG:

l; Stem Area X (Line Pressure - Max DP)

! Calculated for both maximum open and close DP, with the higher being j selected.

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DIFFERENTIAL PRESSURE ~

LOAD The force required to overcome the component of resistance caused by differential pressure.

Valve seat area X DP X Valve Factor

MAXIMUM TARGET TORQUE / THRUST -

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Operator Available Torque

! Operator Maximum Allowable Thrust i

! Operator Maximum Allowable Torque

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Valve Maximum Allowable Thrust .

Valve Maximum Allowable Torque l

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l REQUIRED MOTOR TORQUE i

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(Max Calculated Stem Torque / Ratio

• Pullout Efficency

• Application Factor)

• 100 l

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! REQUIRED MOTOR RUN TORQUE i Maximum Unit Run Torque /

! (Unit Ratio

• Unit Efficency /100) l l

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DERATED MOTOR VOLTAGES The required motor torque at the derated voltages is calculated and compared to the rated motor voltages.

90% Voltage for AC Motors 84% Voltage for DC Motors

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e 1988 UNIT 2 OUTAGE MOV TESTING BY ACTUATOR SIZE 8 SMB-000 6 SMB-00 4 SMB-0 3 SMB-1 1 SB-0 1 SB-3 11 HPCI MOVS 12 RCIC MOVS 14 IJ2T

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TEST CREW IN - HOUSE MECHANICS, ELECTRICIANS, INSTRUMENTATION AND CONTROL TECHNICIANS SETUP OF TEST EQUIPMENT LIMITORQUE CERTIFIED TECHNICIANS ASSISTED IN SIGNATURE ANALYSIS ASSISTED IN EQUIPMENT SETUP 1

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i-MOTOR ACTUATOR CHARACTERIZER I,MAC)

• OEM SUPPLIED - LIMITORQUE CORPORATION

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• 14 CKANNEL CAPABILBT - AIL DATA COILECTED EACH STR0KE e USER FRIENDLY SOFTWARE AND DISPLAY - DISPLAY IN REQUIRED ENGINEERING UNITS - N0 FIELD CALCS e MODEM DATA LINK WITH LIMITORQUE

9.159 Warnshaftdisp. L: -0.122 H: -0.122

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j i -0.359 Ihrttst +0.0 Iorgtte -459.1 5.499 Motor etterent L: +1.978 H: +1.978 l _

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! -0.699 A >s ':ine 0.48  ;?eL ':ine +0,43 0.90 2E41-F001 (Iine span 3.00) B:52688PI2.opn

, 3.00

MOTOR ACTUATOR CHARACTERIZER

{MAC)

• LIMIT SWITCHES

• TORQUE SWITCHES

• MOTOR CURRENT

• WORM SHAPT DISPIACEMENT I, SPRING PACK COMPRESSION) -

• STEM THRUST l I

OPEN - MEASURED CLOSE - CALCULATED

• ACTUATOR OUTPUT TORQUE l CLOSE - MEASURED OPEN - CALCULATED

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MOV TESTING STATIC TEST - PERFORMED ON ALL HOVS AT ZERO DIFFERENTIAL PRES $URE PRESSURE TEST - SELECTED MOVS TESTED AT SYSTEM PRESSURE (Rx PRESSURE APPROXIMATELY 1000 PSI)

STATUS OF TESTING - UNIT 2 COMPLETE FOR ORIGINAL BULLETIN SCOPE SUPPLEMENTAL BULLETIN VALVES HILL BE COMPLETED NEXT OUTAGE STATUS OF TESTING - UNIT 1 TESTING STARTING HILL BE COMPLETED FOR ORIGINAL BULLETIN AND SUPPLEMENT DURING UPCOMING OUTAGE (STARTING 9-28-88) l

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, AS - FOUND HOV CONDITIONS 23 MOVS TESTED (UNIT 2) 17 HOVS - AS FOUND THRUST ACCEPTABLE 6 MOVS - AS - FOUND THRUST BELOW THAT CALCULATED

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s DEGRADATIONS FOUND WITH DIAGNOSTIC EOUIPMENT I

3 MOVS - GREASE IN SPRING PACK 2 MOVS - SPRING PACK REPLACED ,

3 MOVS - TORQUE SWITCH REPLACE 0 1 MOV - TORQUE SWITCH PRELOAD 5 MOVS - MISCELLANEOUS HIRING OR GEARING PROBLEM 1 MOV - COMPLETE OPERATOR REBUILO l

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STATIC TEST VS PRESS TEST RESUL7S MOV 2E41-FOO1, CLOSE TRACE THRUST - LS (Titoaseande) -

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40 --- -- " " " " " " "-- " " "-- " - - -- - --

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30 - - - - - -- --------- -------- ----- - --- -- - - -- - - - -- - - -

26 - - - - - " - " " " " - " " " " " " - - - -- -- - --

20 1"---- -"""":-"-"""""-

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16 ---" "-- - - - - - " - - " " - - - - " - - -- -" --- -" --- -" -

10 -""- -- --""" " "-- " "- " --- - - - " - " " " " -- -- -

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0 100 200 300 400 500 600 700 800 900 1000 1100 120013001400 l

TIME - HUNDRETHS OF SECONOS

STATIC TEST 980 PRESS TEST 2 - PT2 TRIP PT MIN REQV THRUST MAX ALLOW THRUST i

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. STATIC TEST VS PRESS TEST RESULTS l MOV 2E41-FOO1, OPEN TRACE THRUST - LS (T"--d=1 l M i i 45 i

40 - - - - - - - ---- - - -- - - -- -- --- - - - --- --

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35 - - - - - - - - - - --- ------ - - ----- -- -- --- --- - ---- ------ -------- -- ------- ---- - -

g . . .. . . . ... . .... . ...... .....

4 g . .. . .. . .. ......... .... ..

4 20 --- -- - - - - - - - -

I i 15 - - --- - - - - -- - - -

1 10 -- - -- ---- --- - ---- -- - - -

5 i t- - ---

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0 100 200 300 *00 500 600 700 800 900 1000 1100 1200 1300 i

4 TIME - Hbl4DRETHS OF SECONOS i

{ STMIC TEST SSO PRESS TEST 2 PT2 TRIP PT MSN REQ *D THRUST

MAX ALLOW THRUST 1

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AS-LEFT THRUST MARGINS l

% AD0VE MINIMUM REQUIRED 0- 100 PSID +18-527% _

11 MOVS 101 - 426 PSID +75-505%  !

2 MOVS  !

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> 1000 PSID +20-405%

! 10 MOVS  :

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PROCEDURES

• 53IT-TET-001-0S LIMITORQUE VALVE OPERATOR DIAGNOSTIC TESTING I,MAC) AND SETUP

• 52PM-MNT-005-0S LIMITORQUE VALVE OPERATOR INSPECTION

• PM ,

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• 52GM-MEL-022-0S LIMITORQUE VALVE OPERATOR ELECTRICAL MAINTENANCE o GENERAL ELECTRICAL MAINTENANCE, CHECKOUT AND SWITCHES

• MECHANICAL MAINTENANCE PROCEDURES FOR VARIOUS OPERATOR SIZES AND TYPES 1

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PROACTIVE EFFORTS

• USE OF MAC TO TR0083SH00T "PROBLEM" MOVs

• CONSOLIDATION OF LIMITORQUE OPERATOR INFORMATION e OPERATOR SIZES, TYPES, SERVICE

• SPAM PARTS

• PERIODIC REVIEW 0F MAINTENANCE WORK ORDERS GENERATED OR COMPLETED

• INCREASED ATTENTION TO NON-EQ, NON SAFETY RELATED MOVs  ;

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