ML20215J052

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Corrected Deficiency & Part 21 Rept Re Potential Concern That lock-welds Not Installed on Setscrews in Certain Anchor Darling Valve Co Swing Check Valves.Initially Reported on 860425.Deficient Valves Reworked
ML20215J052
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 10/08/1986
From: Foster D
GEORGIA POWER CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-86, REF-PT21-86-370-000, REF-PT21-86-370-000 86100 GN-1104, PT21-86-370, PT21-86-370-000, NUDOCS 8610240275
Download: ML20215J052 (15)
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a a ,,,,,, CORRECTED COPY Georgia Power g*,"';g;' 86 0CI14 P l l 23 mu~wn se October 8, 1986 United States Nuclear Regulatory Commission Region II File: X7BG03-M116 Suite 2900 Log: GN-1104 101 ffarietta Street, Northwest Atlanta, Georgia 30323

Reference:

Vogtle Electric Generating Plant-Units 1 and 2; 50-424, 50-425; Anchor / Darling Swing Check Valves; Letter GN-919 dated May 23, 1986; Letter GN-1061 dated August 28, 1986; Letter GN-1075 dated September 10, 1986 Attention: Mr. J. Nelson Grace

( In previous correspondence on this subject, Georgia Power Company described a potentially reportable concern whereby lock-welds were not installed ~ on setscrews in certain Anchor / Darling Swing Check Valves.

Georgia Power Company has completed its evaluation and concluded that this condition is reportable pursuant to 10 CFR 50.55(e) and 10 CFR

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21. Based upon NRC guidance in NUREG-0302, Revision 1, and other NRC correspondence, Georgia Power Company is reporting this condition pursuant to the reporting requirements of Part 10 CFR 50.55(e). A summary of our evaluation is attached.

This response contains no proprietary information and may be placed in the USNRC Public Document Room.

Your truly/

W D. O. Fos er REF/D0F/tdm Attachment xc: U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 H. G. Baker R. A. Thomas L. T. Gucwa J. P. O'Reilly D. R. Altman C. W. Hayes G. F. Head P. R. Bemis G. A. McCarley R. E. Conway J. A. Bailey R. - W. ficManus J. T. Beckham 0. Batum D. S. Read R. H. Pinson G. Bockhold Sr. Resident (NRC)

P. D. Rice C. E. Belflower C. C. Garrett (OPC)

B. ii. Guthrie J. F. D'Amico J. E. Joiner (TSLA)

D. E. Dutton E. D. Groover D. Feig (GANE) at#"M Pab s S7 i

EVALUATION OF A P0TENTIALLY REPORTABLE CONDITION ANCHOR / DARLING CHECK VALVES Initial Report: On April 25, 1986, Mr. R. E. Folker, Vogtle Project Quality Assurance Engineer, informed Mr. E. F. Christnot of the USNRC Region II of a potentially reportable condition concerning Anchor / Darling swing check valves. Anchor / Darling informed Georgia Power Company that some lock-welds were discovered missing on hinge pin set screws at other nuclear power stations and recommended that certain swing check valves be inspected to determine if this condition exists at. the Vogtle Electric Generating Plant. I In subsequent correspondence, Georgia Power Company indicated that the NRC

'could expect to be informed of the results of the evaluation of this condition by. October 10, 1986.

Background Information: Anchor / Darling reported that some 150 pound and 300 pound swing check valves may have been shipped to Vogtle Electric Generating Plant without the required lock-welds on the following internal valve components identified by location in Figure 1:

1. Hinge Support / Bonnet Interface
2. Hinge Pin Set Screw
3. Disc Nut Pin
4. Hinge Support Cap Screw Anchor / Darling check valves are manufactured and assembled with lock welds at several locations. These lock-welds provide added assurance that specific fasteners remain in place. Without the lock welds, there exists a possibility that the fasteners could become loose and eventually the mating parts could become disengaged. If this occurred the loose valve parts could block fluid flow or the required closing function of the valve could be lost and control of contained fluid backflow would be lost.

A total population of 92 Anchor / Darling swing check valves for Units 1&

2 were originally identified by Anchor / Darling as being potentially discrepant.

A 100% inspection of subject valves was initiated. Subsequently, Georgia Power Company expanded the scope of the inspection to include all Anchor / Darling swing check valves received at the site and listed in Tible

1. As a result of this inspection, a total of 34 valves on Unit I were identified to be discrepant. Futhermore, an additional 22 valves were identified to be discrepant on Unit 2. A list of all 56 discrepant valves is provided in Table 2.

Engineering Evaluation: An evaluation for the Unit 1 & 2 valves identified in Table 2 was performed to determine the impact on plant safety had the condition gone uncorrected. This evaluation assumed that the identified valve defects would have ultimately resulted in disengagement of the valve internal parts and would have created a blockage of flow or loss of valve l function. The results of this evaluation is as follows: 1

1. Nuclear Service Cooling Water (NSCW) Lines
a. Three (3) valves, 1-1202-04-A09, -A14, and -A15 are located in NSCW pump by-pass line. These check valves are classified as active and are used to slow fill the system during system restart following loss of offsite power to preclude and minimize waterhammer events.

Failure of these valves could result in cooling water flow blockage or damage to the various heat exchangers in the system.

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b. Three (3) valves, 1/2-1202-U4-474 and 2-1202-U4-463, are located in the supply lines to the ess.ential chilled water (ESF) chiller condensers (1-1592-C7-001, and 1-1592-C7-002, for train A and B respectively). These check valves are classified as ' active and are used to prevent back drainage. Should the internal valve parts become disengaged, and the cooling water flow blocked, the ESF chillers function would be lost.
c. Three (3) valves, 1/2-1202-U4-464 and 1-1202-04-470, are located in the supply lines to the piping penetration area coolers (1-1561-E7-001, andl-1561-E7-002, for train A & B respectively).

These check valves are classified as active and are used to prevent back drainage. Should the internal valve parts become disengaged, and the cooling water flow blocked, the piping penetration area cooler function would be lost.

d. Valve 1-1202-04-466 is located in the supply line to the containment fan coolers of train A (1-1501-A7-005 and -006). These check valves are classified as active and are used to provide cont'ainment double isolation and to prevent block flow. Failure of these valves could result in deviation from containment double isolation criteria and loss of cooling water to the fan coolers.
e. Two (2) valves, 2-1202-U4-467 and -472 are located in NSCW supply lines to containment fan coolers (1501-AT-001/002 for train A, and 1501-AT-003/004 for train B). These check valves are classified as active and are used to provide containment double isolation and to prevent block flow. Failure of these valves could result in deviation from containment double isolation criteria and loss of cooling water to the fan coolers.
2. Component Cooling Water Lines
a. The following six valves are classified as active and are used to prevent backflow when the pump is on standby. Failure of these six (6) valves could result in blocking the cooling water flow and/or damage of heat exchangers by disengaged valve internal parts.

Tag No. Location 1-1203-04-030 CCW pump (1203-P4-001, Train A) discharge line 1-1203-U4-032 CCW pump (1203-P4-003, Train A) discharge line 1-1203-U4-034 CCW pump (1203-P4-005, Train A) discharge line

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Page three Ido No. Location 1-1203-U4-055 CCW pump (1203-P4-002, Train B) discharge line 1 .203-U4-057- CCW pump (1203-P4-004, Train B) discharge line 1-1203-U4-059 CCW pump (1203-P4-006, Train B) discharge line

b. The following seven valves are classified as non-active and function to prevent backflow when another make up source is used. Failure of these seven (7) valves could result in blockage of make up water flow to the surge tank. However, make up water can be provided from the other backup source with its independent piping system.

Additionally, back flow could be prevented by the normally closed make up valve. Therefore, this type of failure has no impact on the safety function of the system.

Tag No. Location 1-1203-U4-122 Make up line to and 1/2-1203-U4-124 CCW surge tank from demineralized water storage tanks.

1-1203-U4-127, Make up line to 2-1203-U4-122, CCW surge tanks and 1/2-1203-U4-119 from reactor make up water pumps,

c. Valve 2-1203-U4-013 is identified as surplus valve, which does not require a plant safety evaluation.
3. Auxiliary Building & Miscellaneous Drain Lines
a. One (1) valve, 2-1215-04-260, is located in the drain line from the auxiliary feedwater pump room (Train C) to the auxiliary feedwater system pump. This valve is classified as nonactive. Failure of this valve could result in an open drain in the auxiliary feedwater pump room, (Train C). A single failure in Train A, in conjunction with flooding in Train B pump room and open drain in Train C pump room could result in unavailability of auxiliary feedwater system.

Therefore, failure of this check valve will affect the safety function of the auxiliary feedwater system.

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4. Auxiliary Feedwater (AFW) Lines
a. Valve 1-1302-U4-013 is located in the suction line of the turbine-driven AFW pump. Should the internal valve parts become disengaged and flow blocked, the operability of the turbine-driven AFW pump could be lost. Credit is not taken for an available water supply from the second CST since operator action would be required to initiate flow should the first CST water supply become unavailable.
b. Valve 1-1302-04-051 is located in the turbine-driven AFW pump suction line fro n condensate storage tank 002. This valve is classified as nonactive and is used to prevent condendate transfer from condensate storage tank 001. Failure of this valve will block auxiliary feedwater flow to the suction of the pump or damage the auxiliary feedwater pump by disengaged valve internal parts.
c. The following four valves are classified as nonactive and function to prevent drainage of the CST in event of line brea.k. Failure of these valves could result in damage to the auxiliary feedwater pump by disengaged valve internal parts and may partially drain the condensate storage tank (CST).

Tao No. Location 1-1302-U4-062 Degasifier water 1/2-1302-U4-064 return line from degasifier trans-fer pump 1-1302-U4-063 Degasifier feed pump min. flow return line

5. Essential Chilled Water line
a. Valve 1-1592-04-187 is located in the essential chilled pump discharge line. This check valve is classified as nonactive and is used to prevent back flow when the pump stops. Failure of this valve could result in blockage of chilled water flow to cooling coils (Train B) and high temperatures in the building / rooms could be served by the chiller. Safety functions of the equipment in the rooms could be affected. As a result it is concluded that plant safety could have been impacted had the conditions gone uncorrected.
6. Containment Fire Protection Water Supply Line
a. Valve 1-2301-U4-036 is located in the line supplying fire protection water to the containment building. This check valve is classified as active and is used to provide containment double isolation and i prevents back drainage. Should the internal valve parts become l disengaged containment double isolation would be lost. As a result i it is concluded that plant safety could have been impacted had the condition gone uncorrected.

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_ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . . _ . .. - . _ . _ _ ~ _ _ _ _. _ _ __ ___.~.__m- _ _ . . . - _,

Page five

7. Service Air System Lines
a. Two (2) valves, 1/2-2401-U4-034 are located in the service air supply line to containment building for Unit 1 and 2 respectively. These valves are classified as active and are used to provide containment double isolation. Failure of these check valves will result in deviation from containment double isolation criteria. As a result, it is concluded that plant safety could have been impacted had the condition gone uncorrected.
8. Valves in the following systems, listed in Table 2, are not required for plant safety evaluation since the systems are not safety related,
a. System 1217 - Auxiliary Component Cooling Water System
b. System 1228 - Reactor Make-Up Water Storage Tank / Degas
c. System 1901 - Waste Processing System - Gas Evaluation of Quality Atwranen Program Breakdown: A review of the Anchor / Darling Quality Assurance Program was conducted and it was concluded that a significant breakdown had not occurred. This was considered an oversight in establishing the shop _ inspection program, because at the tine these valves were manufactured, the verification of the lock welds had not been included in the inspection check sheet. This oversight has been corrected and the lock welds are now inspected. -

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Conclusion:

Based on the above evaluation, the plant safety could have been

impacted had the condition of the swing check valves designated for use in j plant safety systems gone uncorrected. Therefore, Georgia Power Company has concluded that a reportable condition as defined by the reporting criteria of Part 10 CFR 50.55(e) and 10CFR 21 does exist. Based on guidance in NUREG-0302, Revision 1, concerning duplicate reporting of an' event, Georgia Power Company is reporting this event per the criteria of Part 10 CFR 50.55(e).

Corrective Action: All Unit' I and 2 Anchor / Darling 150 pound and 300 pound swing check valves have been inspected and identified as indicated in Tables 1 and 2. All deficient valves have been reworked to bring them into conformance with the Anchor / Darling design drawings.

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FIGNE 1 LOCK WELDS IN ANCHOR DARLING VALVES WHICH MAY SE DEFICIENT BONNET i

O o

O LOCK WELD AT HINGE SUPPORT / BONNET INTERFACE

' - LOCK WEI.D ON HINGE SUPPORT CAP SCREW C

o HINGE SUPPORT HINGE SUPPORT i HINGE PIN CAF SCREN LOCK WELD ON HINGE PIN SET SCREW N HINGE LOC WELD ,

l' DISC NUT PIN

  • DISC

Page 1 of 5 TABLE 1 ANCHOR DARLING 150/300 LB. SWING CHECK VALVES IN VEGP UNITS 1 & 2 VALVE P.O. ITEM P&ID TAG NO. NO. NUMBER COORDINATES (For reference only)

( 1/2X4DS---)

A. NUCLEAR SERVICE COCLING WATER SYSTEM (1202) 1-1202-U4-463 1-223 134 E2

  • 1-1202-U4-464 1-218 133-2 C3 e 1-1202-U4-470 1-219 135-1 A7
  • 1-1202-04 474 1-222 135-2 c7
  • 1-1202-U4-A09 2-194 133-1 W 1-1202-U4-A13 2-354 133-2 88  ;
  • 1-1202-04-A14 2-192 133-2 N
  • 1-1202-04-A15 2-193 133-2 N 1-1202-04-A07 1-501 133-1 B8 1-1202-U4-A08 1-502 133-1 B7
  • 1-1202-U4-466 1-504 135-1 G5 1-1202-U4-467 1-505 135-1 E5 1-1202-u4-468 1-506 135-1 C5 1-1202-U4-471 1-507 135-2 G6 1-1202-U4-472 1-508 135-2 G6 1-1202-U4-473 1-509 135-2 G6 8 2-1202-04-463 2-196 134 E2 8 2-1202-U4-464 2-471 133-2 D3 2-1202-04-466 2-474 135-1 G5
  • 2-1201-04-467 2-475 135-1 E5 2-1202-04-468 2 476 135-1 C5 2-1202-U4-470 2-472 135-1 M 2-1202-04-471 2-477 135-2 H6
  • 2-1202-04-472 2-478 135-2 H6 2-1202-04-473 2-479 135-2 G6
  • 2-1202-U4-474 2-430 135-2 B8 B. COMPONENT (%)0 LING WATER SYSTEM (1203) 1-1203-U4-013 1-79 surplus -

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  • 1-1203-04-030 1-32 136 H4 a 1-1203-04-032 1-33 136 G4
  • 1-1203-U4-034 1-34 136 F4
  • 1-1203-04-055 1-35 136 D4 890MLC

TABLE 1 - ANCHOR DAPLING CHECK VALVES Page 2 of 5 VALVE P.O. ITEM PLID TAG NO. NO. NUMBER COORDINATES (1/2X4DS -) (For reference only)

  • 1-1203-U4-057 1-36 136 c4 8 1-1203-U4-059 1-37 136 B4 8 1-1203-U4-119 1-186 136 F8
  • 1-1203-U4-122 1-183 136 ET e 1-1203-04-124 1-187 136 c7
  • 1-1203-04-127 1-185 136 a7 1-1203-U4-026 Surplus - -

1-1203-U4-028 surplus - -

' 2-1203-04-013 2-79 Surplus -

  • 2-1203-U4-119 2-171 136 F8
  • 2-1203-04-124 2-172 136 c7 2-1203-04-127 2-170 136 A7 2-1203-04-039 2-37 136 B4 2-1203-U4-057 2-36 136 c4 2-1203-U4-055 2-35 136 D4 2-1203-U4-034 2-34 136 F4 2-1203-U4-032 2-33 136 G4 2-1203-U4-030 2-32 136 H4 8 2-1203-04-122 2-349 136 E7 C. REFUELING WATER STORAGE TANK (1204) 1-1204-U4-262 1-408 121 G3 1-1204-U4-263 1-409 121 G3 2-1204-U4-262 2-381 121 G3 2-1204-U4-263 2-382 121 G3 l D. AUXILIARY BUILDING AND MISCELLANEOUS DRAIN SYSTEMS (1215) 1-1215-04-260 1-482 146-3 c1 1-1215-04-262 1-483 146-3 c2 1-1215-U4-264 1-484 146-3 02 1-1215-U4-266 1-485 146-3 c3 1-1215-U4-268 1-486 146-3 C7 1-1215-il4-293 1-487 146-3 c5
  1. 2-1215-U4-260 2-456 146-3 c1 2-1215-04-262 2-457 146-3 c2 2-1215-U4-264 2-458 146-3 c2 2-1215-04-266 2-459 146-3 C3 2-1215-U4-268 2-460 146-3 CT 2-1215-U4-293 2-461 146-3 CT 890MLC

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Page 3 of 5 TABLE 1 - ANCHOR DARLING CHECX VALVES 0

VALVE P.O. ITEM P&ID NO. NUMBER COORDINATES TAG NO.

( 1/2X4 DB---) (For reference cnly)

E. AUXILIARY COMPONENT COOLING WATER SYSTEM (1217) 1-1217-U4-001 1-75 Surplus -

' 1-1217-U4-041 1-78 138-2 G3

  • 1-1217-04-062 1-76 138-2 F7
  • 1-1217-U4-067 1-144 138-2 D7 1-1217-04-068 1-379 138-1 G7
  • 1-1217-U4-070 1-188 138-1 87 1-74 138-2 F6
  • 1-1217-U4-114
  • 1-1217-04-171 1-77 138-2 C3 1-22 138-1 F4
  • 1-1217-04-026 8 1-1217-U4-028 1-23 138-1 F4
  • 2-1217-U4-001 2-75 Surplus -

2-1217-U4-041 2-78 138-2 G3

  • 2-1217-04-062 2-76 138-2 F7
  • 2-1217-04-067 2-129 138-2 D7
  • 2-1217-U4-068 2-169 138-1 G7 ~
  • 2-1217-04-070 2-355 138-1 H7 e 2-1217-04-114 2-74 138-2 G6
  1. 2-1217-U4-171 2-77 138-2 C3 2-1217-U4-026 2-22 138-1 F4 2-1217-U4-028 2-23 138-1 E4 F. REACTOR MAKE-UP WATER STORAGE TANK / DEGAS SYSTEM (1228) 1-1228-U4-002 1-376 184 G7 1-1228-Uu-004 1-380 184 G5
  • 1-1228-U4-005 1-377 184 D6 1-1228-U4-006 1-378 184 c6 1-1228-U4-003 184 G5
  • 2-1228-U4-002 2-168 184 G7
  • 2-1228-04-004 2-353 184 G5 2-1228-U4-005 2-350 184 D6 2-1228-04-006 2-351 184 B6 2-1228-U4-003 184 GS G. AUXILIARY FEEDWATER SYSTEM (1302)
  • 1-1302-U4-013 1-226 161-2 F7 1-1302-U4-033 1-224 161-2 B7
  • 1-1302-04-051 1-227 161-2 E7 1-1302-U4-052 1-225 161-2 A7 890MLC
  • 1 TABLE 1 - ANCHCR CARLING CHECX VALVES Pigo 4 of 5 a

VALVE P.O. ITEM P&ID TAG NO. NO. NUMBER COORDINATES

( 1/2X4DB---) (For reference only)

  • 1-1302-U4-062 1-220 161-1 G6
  • 1-1302-U4-063 1-382 161-1 G6
  • 1-1302-04-064 1-381 161-1 C6 1-1302-04-086 1-406 161-1 B6 1-1302-U4-087 1-407 161-1 B6 1-1302-U4-058 1-503 161-2 D7 1-1302-U4-061 1-510 161-2 C7 1-1302-U4-085 1-375 161-1 G6 1-1302-U4-030 161-2 F7 1-1302-U4-032 161-2 F4 1-1302-04-034 161-2 B7 2-1302-U4-013 2-200 161-2 F7 2-1302-U4-051 2-201 161-2 E7 2-1302-04-052 2-198 161-2 A7 2-1302-U4-058 2-197 161-2 D7 2-1302-U4-061 2-199 161-2 C7 2-1302-U4-086 2-379 161-1 B6 2-1302-04-087 2-380 161-1 B6
  • 2-1302-04-064 2-173 161-1 C6 2-1302-04-062- 2-503 161-1 G6 2-1302-U4-063 2-504 161-1 G6 2-1302-U4-033 2-473 161-2 H7 2-1302-U4-085 2-348 161-1 -

G6 H. ESSENTIAL CHILLED WATER SYSTEM (1592) 1-1592-U4-186 1-410 221 F4

  • 1-1592-U4-187 1-411 221 D4 2-1592-U4-186 2-393 221 A3 2-1592-04-187 2-394 221 A3 I. FIRE PROTECTION WATER SYSTEM (2301)
  • 1-2301-04-036 1-271 174-4 A7 2-2301-04-036 2-245 174-4 A7 J. SERVICE AIR SYSTEM (2401)
  • 1-2401-U4-034 1-221 186-1 D2 1-2401-U4-042 1-73 Surplus -

890MLC

Page 5 of 5

. TABLE 1 - ANCliCR DARLING CHECX VALVES P.O. ITEM P&ID VALVE COORDINATES NO. NUMBER TAG NO. (For reference only)

( 1/2X4DB---)

186-1 02

  • 2-2401-04-034 2-195 2-73 Surplus -

2-2401-U4-042 K. WASTE PROCESSING SYSTEM - LIQUID (1901) 127 F1

  • 2-1901-U4-039 2-352 L. VALVE THAT WAS DECLARED LOST 1-1228-U4-090 1-184 -

M. CONTAINMENT BUILDING POST-LOCA CAVITY PURGE SYSTEM (1516) 1-1516-U4-003 Surplus 1-1516-04-004 Surplus

  • These valves were deterinined to be discrepant during the inspection (for details, see Table 2).

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s Revised (3-2-36}

  • Page 1 of 3 TABLE 2 A LIST OF DI5CREPANT A/DV SWING CHECK VALVES VALVE ASSEMBLY VALVE TAG NO. DRAWING NO.

(Reference Only)

BECHTEL SUPPLIER DDC LOG (X4AR01)

SYSTEM 1202 - NUCLEAR SERVICE CCOLING WATER SYSTEM 4

1-1202-U4-A09 W7920422 2-233 1-1202-04-A14 W7920422 2-233 1-1202-U4-A15 W7920422 2-233 1-1202-U4-46u W7920309 1-155 1-1202-U4-466 W8421972 1-540 1-1202-U4-470 H7920309 1-155 1-1202-U4-474 H7940001 1-256 2-262

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2-1202-U4-463 H7940007 2-1202-U4-464 W8321914 2-522 2-1202-U4-467 W8421974 2-539 2-1202-04-472 W8421974 2-539 2-1202-U4-474 W8321915 1-528 SYSTEM 1203 - COMPONEKT CCOLING WATER SYSTEM 1-1203-U4-030 4114-3 1-99 1-1203-04-032 4114-3 1-99 1-1203-U4-034 4114-3 1-99 1-1203-04-055 4114-3 1-99 1-1203-U4-057 4114-3 1-99 1-1203-U4-059 4114-3 1-99 1-1203-04-122 W7920308 1-168 1-1203-U4-127 W7920308 1-168 1-1203-04-119 W7920309 1-155 i 1-1203-04-124 W7920309 1-155 l

2-1203-U4-013 (Surplus) W7920607 2-247 2-1203-04-122 W8020930 2-355 2-1203-U4-124 W7920422 2-233 2-1203-04-119 W7920422 2-233 SYSTEM 1217 - AUXILIARY COMPONENT COOLING WATER SYSTEM 1-1217-04-026 4114-3 1-99 1-1217-U4-028 4114-3 1-99 1-1217-04-041 W7920317 1-158 888MLC

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s l Revised (?-2-66)

Page 2 of 3 l

TABLE 2 (Cont'd) l A LIST OF DISCREPANT A/DV SWING CHECK VALVES l

VALVE ASSEMBLY VALVE TAG NO. DRAWING NO.

(Reference Only)

BECHTEL SUPPLIER DDC LOG (X4AR01) 1-1217-U4-062 W7920317 1-158 1-1217-U4-067 W7920296 1-145 1-1217-U4-070 W7920309 1-155 1-1217-U4-114 W7920596 1-248 1-1217-U4-171 W7920317 1-158 2-1217-U4-001 (Surplus) W7920607 2-247 2-1217-U4-062 W7920430 2-204 2-1217-04-067 W7920409 2-216 2-1217-U4-068 W7920421 2-232 2-1217-U4-070 W7920422 2-233 2-1217-U4-114 W7920607 2-247 2-1217-U4-171 W7920430 2-204 SYSTEM 1215 - AUXILIARY BUILDING AND MISCELLANEOUS DRAIN SYSTEMS 2-1215-04-260 W8321749 2-449 SYSTEM 1228 - REACTOR MAKE-UP WATER STORAGE TANK / DEGAS SYSTEM 1-1228-U4-005 W8020923 1-323 2-1228-U4-004 W8020930 2-355 2-1228-U4-002 W7920421 2-232 SYSTEM 1302 - AUXILIARY FEEDWATER SYSTEM 1-1302-U4-051 H794002 1-257 1-1302-U4-062 W7920309 1-155 1-1302-U4-063 W8020924 1-373 1-1302-U4-064 W8020924 1-373 1-1303-U4-013 H7940002 1-257 2-1302-04-064 W7920422 2-233 888MLC

1

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Revised '9-2-36)

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  • Page 3 of 3 TABLE 2 (Cont'd)

A LIST OF DISCREPANT A/DV SWING CHECK VALVES l

SYSTEM 1592 - ESSENTIAL CHILLED W ATER SYSTEM 1-1592-U4-187 W8020994 1-387 SYSTEM 1901 - WASTE PROCESSING SYSTEM - GAS 2-1901-U4-039 W8020930 2-355 SYSTEM 2301 - FIRE PROTECTION SYSTEM 1-2301-04-036 4279-3 1-292 SYSTEM 2401 - SERVICE AIR SYSTEM 1-2401-U4-034 W7920597 1-281-2-2401-04-034 W7920608 2-282 l

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888MLC 1

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