ML20235U624

From kanterella
Jump to navigation Jump to search
Forwards Util Completion Rept for Valve Program Per IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings
ML20235U624
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/06/1987
From: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-85-003, IEB-85-3, NUDOCS 8710140168
Download: ML20235U624 (5)


Text

- - _ __ - ___ _ _ . _- _ _ _ _ _ ___

~..

.' i Den A.

ggp Electric & Gas Company u 29218 Nuclear Operations ig.

N October 6, 1987 ma,,

S?OCf I Alg ,,

Dr. J, Nelson Grace Regional-Administrator -

U. S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW-Atlanta, Georgia 30323 g i

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50D95

,2- ,

Operating License:No. NPF-12 IEB 85-03 Completion Report

/., . ,

Dear:

Dr.;Gmce: -

Attached is the South Carolina Electric & Gas Company (SCE&G) Completion

.s Report for the IEB 85-03 valve program. This Completion Report is submitted

% .in accordance with action item (f) of the Bulletin which includes tha related actions,asspecifiedbyitems(b-d).

-Should'you have any questions, please call at your convenience.-

,[

y truly ours, l

. . N ima MDB/0AN:bjh Attachment pc: 0. W. Dixon, Jr./T. C. Nichols, Jr. M. R. Hazel E. C. Roberts C. L. Ligon

0. S. Bradham R. M. Campbell D. R. Moore K. E. Nodland W. A. Williams, Jr. J. C. Snelson Group Managers G. O. Percival W. R. Baehr R. L. Prevatte i C. A. Price J. B. Kndtts, Jr.

R. B. Clary NPCF W. R. Higgins RTS W. T. Frady File M. D. Blue

(

f"!'W!!?s88% PDR

. _ __ NT

Q w;

'. i 7 y p '. _; y r

IEB 85-03

?e i' Motor' Operated Valve Common Mode Failures During Plant

. Transients Due to Improper Switch Settings South Carolina Electric & Gas Company -

,, Completion Report I. Introduction South Carolina Electric &' Gas _ Company (SCE&G) has completed the-required M

?

action described in IEB 85-03-for the. valves originally identified in our letter dated May 16, 1986. A program to, ensure that valves in the t emergency.feedwater (EFW) and the safety injection (SI) systems wil.1 perform.their associated design basis function has been developed and implemented. .The~ additional valves identified in your Request for.

Additional Information dated August 18, 1987 will be included.in this-program as indicated by our response dated September 17, 1987. This m program utilized Motor Operated Valve Analysis and Test System (MOVATS)

. signature analysis in combination with vendor test data and differential pressure testing. . The plant procedure for obtaining MOVATS signatures was'used for each identified valve pertaining to IEB 85-03.

II. Program Description-The testing _ methodology consisted of obtaining the signature analysis results, documenting discrepancies in operator switch controls'through our nonconformance program, and providing engineering evaluation of any resulting discrepancies. Discrepancies were adjusted in accordance with valve manufacturers' instructions. In all cases each valve would have been capable of performing its design basis function in the as-found condition. Specifically, valve closing thrusts were decreased to reduce the seating force within the optimum performance range.

Our program consisted of the following procedures:

4

1. Torque switch and stem thrust data were obtained from the appropriate vendors. For the Westinghouse valves in the SI system, stem thrust values and torque switch settings were obtained for the closing direction, and previously supplied torque switch setting information was utilized for the open direction. For the Anchor Darling valves in the EFW system, stem thrust values and
torque switrh settings were supplied for both directions. In cases where. che torque switch and stem thrust data conflicted, the known. stem thrust values were utilized in determining the design basis acceptance of each valve.

k, '~

2. Any valve packing replacement or adjustment was performed per plant procedures.

1

- - _ _ _ _ _ _____-__ _ _-__ _ _ i

t'

'W; '

y-

^

s 7.

3. MOVATSiignatureanalysiswas;thenperformedforthespecified

. valves. Torque switch settings and limit' switch settings-27 '

, (including torque switch' bypass settings) were'then verified..

4.; Th'e following valves were then stroke tested agair.st differential-pressures:-

' VALVE DIFFERENTIAL PRESSURE-(PSIG')

'XVG-81'07 2275

'XVG-8801A, 8801B 2275 XVG-8108- 2275 LCV-115B,.1150. 29'

~

LCV-115C,' 115E - 41 As discussed in ou'r supplemental. response dated October 3, 1986,. testing:

of,EFW valves wouldlnot be performed. SCE&G is. confident'that M0 VATS data assures the. design ~ basis operability.of each-valve operator. This conclusion is based on thetsuccessful testing of the SI valves under.

high differential _ pressures.. In contrast,.the valves in the EFW system are' subjected to relatively, low differential pressures.

SCE&G has committed to continuing maintenance'of the IEB identified-

~

valves.through our current plant preventive maintenance program.

~

, III. Summary A sults of Tor _que Switch and Stem Thrust Information Testing of the 14 valves listed below was conducted in accordance with EMP-445.007, "MOVATS Testing of Limitorque Valves," during the third refueling outage. The following are the results of those tests:

Open Thrust (1bf) .

"As-Found" & CloseThrust(1bf) CloseThrust(1bf)

Valve' "As-Left" "As-Found" '"As-Left" XVG-8107- 8620 9630 9630 XVG-8108 14,576 9792 9792 XVG-8801A 7196 9230 9230 XVG-8801B 7699 10,589- 10.589 LCV-1158 8942 15,501 5421 LCV-115D 15,509 15,042 5499 LCV-115C. 7168 8594 6330 LCV-115E 4541 9408 4891 XVG-1001A 1917 2020 2020 XVG-1001B 2912 2381 2381 XVG-1002 2927 4253 4253

,. XVG-1008 4445 4846 4846 XVG-1037A 4950 3324 3324 ~l XVG-10378 3385 6403 6403 I

, i; 3 y 'i 9 Torque Switch Setting i' Torque Switch. .

(Closed) .

Valve' Setting'(0 pen) "As-Found" "As-Left"

' i

XVG-8107- 1.5- *
  • XVG-8108 2.0 *-
  • XVG-8801A 1.75. '1.75 1.75
XVG-8801B 1.5 1.5 1.5 ' l; LCV-115B 1.5 *
  • LCV-1150. 2.0' * '*

1

.LCV-115C 1.5 1.5 1.0  :

.LCV-115E 2.0- 1.75' 1. 5 '

XVG-1001A 2.0 2.0- 2.0 XVG-10018 2.0 '2.0 3 2.0 1 2

XVG-1002 1.5 2.0- 2.0 'l XVG-1008 1.0 2.0 2.0 XVG-1037A 2.0 1.5 1.5 ,

XVG-1037B ;2.0 2.0 2.0 i l

'

  • Valves XVG-8107, XVG-8108, LCV-115B and.LC'V-1150 do not use torque switches in the closing circuit.

~

I NCN-2561 was written for the' Nuclear Engineering disposition of the valves.in which the "as-found" condition was outside of the limits specified by the manufacturer. Some low thrust values'were found acceptable "as-is"; valves with high thrust values were adjusted to reduce their seating forces.

IV. Records and-Procedures The results of the testing performed during the third refueling outage at_.the Virgil C. Summer Nuclear Station are maintained in the Plant Record System. This information is recorded on the following preventive maintenance task sheets (PMTS). This testing was performed under

. preventative test procedure (PTP) 170.002, " Stroke Testing Motor

-0perated Valves."

PMTS Valve P0081543 XVG-8107 P0081544 XVG-8108 P0089527 XVG-8801A P0089528 XVG-8801B P0081528 LCV-1158 f, .P0081529 LCV-11 2 P0081530 LCV-1150 t

L__- _ _

1 i fi. ..

.A ,

1 PMTS Valve i y

P0081531: 'LCV-115E P0081537 'LCV-1001A.

P0081538 '

XVG-1001B ,

P0081539' XVG-1002- l lP0081540 XVG-1008-

~P0081541- .XVG-1037A , ,

P0081542-- XVG-1037B

The followingfelectrical. maintenance procedures (EMPs) are used for 1 motor operator-maintenance.

EMP 445.001J .Limitorque Preventive Maintenance .

EMP 445.002 Limitorque Operator Maintenance .

i EMP 445.003 Determination, Determination and Testing of- j Limitorque 0perators i EMP 445.004' Rotork Maintenance . . . .

EMP 445.005 Limitorque' Limit Switch Lubrication EMP 445.006l Setting Limits on Valves'with Torque Switch Bypassed EMP 445.007 MOVATS. Testing of Limitorque Valves

'EMP 445.008 Limitorque Valve Data EMP 445.009 Setup of LLRT Valves Using MOVATS' i

n i~

_ _ _ - _ - _ _