ML20138A562
| ML20138A562 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/03/1985 |
| From: | Hanson G, Jeffrey Jacobson, Sayre E GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20138A555 | List: |
| References | |
| E22-00070, E22-70, PMA-84-06, PMA-84-6, NUDOCS 8603140317 | |
| Download: ML20138A562 (69) | |
Text
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NO. PMA 84-06 DRF No. E22-00070 PLANT MATERIALS APPLICATION ENGINEERING TITLE: FAILURE ANALYSIS, F010 AND F011 VALVES, CLINTON PROJECT Date: December 3, 1985 Prepared By: N G, R. Hanson t
Approved By: . M . y/.s((
J/Ja(obson, Manager Equipment Design Engineering Approved By: -) ..A. hv E .t.Sope_.
E. D. Sayre, Manager N Plant Materials Application NOTICE Neither the General Electric Company nor any of the contributors to this document makes any warranty or representation (express or implied) with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from the use of any of the information contained in this document.
DISTRIBUTION GRH43 C.T. Nieh G.M. Gordon H. Ehsan B.M. Gordon J. Jacobson F.F. Smith E.D. Sayre J.T. Cochran ,
E. Kiss R.T. Reich I
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8603140317 860312 PDR ADOCK O N 1 I E PM .
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Failure Analysis Report of F010 and F011 Valves From The Clinton Reactor
- 1. INTRODUCTION
- 1.1 Discovery of Cracked Valve Stem and Loose Parts in HPCS S_vstem i'
While the Clinton Site was operating the High Pressure Core Spray (HPCS) pump in system test.(October-November, 1985) with suction from the condensate l storage tank a noise was heard in the return line to the condensate storage tank. The noise sounded as if loose parts were rolling down the return line l followed by's "thunk". Subsequently the flow rate dropped substantially.
Disassembly of F010 and F011 valves revealed the fo'11owing damage in the ~
f valves: -
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l F010 Valve
- a. Broken valve stem b.
l Disc and stub of stem were jammed at an angle into the seat and guides resulting in the valve being locked open i
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j c.
l Extruded back seat on stem. The valve stem at the back seat location was
! mushroomed indicating the stem had been pulled into the backseat with the I motor l
! d. Bent Stem Clamp The stem clamp was bent. !
l F011 Valve a.
The dise and dise nut were unscrewed leaving the stem free to
! travel out of the disc. One retainer ring segment was found downstream
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of the valve just beyond the flow restricting orifice. The other ring segment was found in the condensate storage tank.
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- b. I The stem was heavily sailed and the back seat in the bonnet was badly i
cracked as a result of pulling the stem through the back seat with the motor operator. .
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1.2 Objectives of This Failure Analysis Report are to Document Findings and to Make Recommendations e
The objectives of this report are to document the findings regarding F010 and F011 valves at the Clinton site, subsequent failure analysis work, to determine cause of failure and to make r: commendations for'further action.
1.3 Cause of Failure 1.3.1 E22F010 Valve Stem Failure Meta 11ographic studies showed that the crack startgd intergranularly (probably Intergranular Stress Corrosion Cracking) (IGSCC) and progressed to approximately 30' around the circumference to approximately 1 inch deep. The balance'of the cross section shows a brittle cleavage failure indicting the .
shaft broke suddenly with a single application of overload. It is entirely possible that the intergranular cracking (IGC) started due to high tensile stresses resulting from backseating the stem with the motor actuator coupled with the residual stresses from heat treatment and high hardness of the stem (RC 40-42 in the failure area). When the IGC had grown to sufficient size, a
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loading of the stem from the motor operator could have'been sufficient to cause a single brittle fracture to occur in the balance of the stem cross section.
1.3.2 E22F010 Valve Disc Jammed Open Sometime after fracture of the stem the disc became cocked in the valve such that one edge was striking the seat and the opposite side was wedged in the guides, Figure 8. This effectively jammed the valve open with no possibility of closing. The broken top part of the stem was striking the lovet part of ,.
the stem such that it wedged the disc tighter in the open position with each -
stroke. The cocking of the dise was most likely due either to use of the valve for throttling or from closing the valve while the pump was operating.
It is not likely that the stem could have cocked with no flow in the valve.
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-1.3.3 E22F010 Valve Stem Back Seat Mushrooming and E22F011 Back Seat Damage The damage to both valves in the back seat area was caused by pulling the
[ stems into the back seat with the motor operator probably at full thrust. In the case of F010 valve the shaft seat was extruded; while in the case of the F011 valve the back seat was cracked and expanded and the shaft badly galled.
It appears that the limit switches were inoperative and the motor operators pulled until the torque switch turned the motor off. This type of damage is typical where the limit switch is not set properly or where it is bypassed.
l 1.3.4 E22F011 Valve Disc and Nut Separation The dise nut unscrewed from the disc and completely separated the stem and dise due to vibration.
It is not clear when the loosening of the nut occurred. The fact that there was no fretting on the shaft and no damage to the threads would suggest that the loosening and separation occurred very closely together. On the other hand the loosening of the stem clamp and other problems with the valve would l suggest that the nut loosening took place over a leager period of time.
1.4 Recommended Corrective Action 1
l 1.4.1 Damaged Items All damaged items should be replaced or repaired. The stems should be replaced with properly heat treated Type 410 stainless steel. General Electric's current standards require hardness of Type 410 not to exceed RC28 l (See paragraph 2.4 for basis). 17-4 Ph stems may also be used providing the aging temperature is 1075'F or greater (material temperature).
1.4.2 .P.ecking l
As a product improvement GE recommends use of valve packing with high purity packing meeting the limits of CE SIL No 399 to control the pitting that can ,
occur with high chloride packing material. A copy of SIL No 399 is attached.
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I 1.4.3 Back Senting of Valve I
l Measures should be taken to assure that the valve. stems do not remain backseated for long periods of time. This traps water in the back seat pocket which acts as a crevice and. corrodes the shaft. The corrosion and pitting can be a nucleus for ICC as a nucleation site for IGSCC.
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! 1.4.4 Proper Setting of Limit Switch i
The cause for switches being inoperative should be determined. Corrections in both equipment and procedure to assure proper operation in the future should be made. The need for. adjustment of position may be indicative of problems in the valve such as a broken stem or unscrewed disc nut..
1.4.5 Use of valves for Throttling l These valves are not designed for intensive throttling service. They can be used to throttle for a limited amount of flow (down to 30% flow) for short periods of time. If it is desired that these valves be us&d for more throttling than this other alternatives can be developed.
1.4.6 Other Valves -
- Hardness The hardness of other valve stems in the HPCS system was determined near the mid length of the stem as shown in Table 1. It is obvious that the F023 valve stem is too hard and it should either be retempered or replaced. For the other valves it is not as obvious since F010 shows RC35 at mid-length but RC40 at the hard end and RC30-31 at the soft end. For these other valves it is recommended that hardness be taken at midstem and at the top end. These two '
measurements will allow an estimate of the hardness at the lower end of the i valve stem.
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Other Valves should be disassembled and inspected unless there is evidence to show that the stems were not pulled into the back seat with the motor. The stems should be inspected visually and with liquid penetrant to assure freedom from damage. In addition for valves with stems harder than RC28 and which were backseated for an extended period of time (in excess of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />), the stems should be inspected visually and with liquid penetrant to assure freedom from cracking. Alternately the stems may be examined with ultrasonics using a procedure qualified to detect such intergranular cracking.
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Table 1
- Hardness of Valve Stems in HPCS System Yalve Hardness in Mid Stem Location (above the stem clamp)
F001 RC 29.4 F004 RC 32.7 F010 RC 35.0 F011 RC 37.3 F012 RC 32.4
.F015 RC 28.6 ,
F023~ RC 40.5 9
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2.0 DISCUSSION
, 2.1 Contributors to Damage The main contributors to the damage found in the valves (see Section 3.0) lW
, are:
(1) Limit switch problems resulting in overtravel of stem into back t seat.
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'(2) Vibrations (a) due to original positioning of the D004 orifice too li close to the F011 valve and (b) due to extensive use of the valves l'
for throttling. ,
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i (3) High stem hardness with resultant high residual stress caused by j tempering at too low a temperature. (RC41 in region of failure)
! 2.2 Why Vibration loosened Parts in F011 Valve and Not F010 Valve l*
For the F011 valve vibration caused the separation of stem, disc and stem l nut and allowed the split rings to cascade down the pipe. Only the F011 valve had evidence of loosening of parts due to vibration. There are two possible explanations explain this as follows:
a) It is possible that the vibration resulting from the D004 orifice being too close caused the loosening of the stem nut on F011 and
- later throttling served to complete the separation. The F010 valve would not have experienced as severe a vibration from the orifice.
b) It is possible that the F010 valve stem fractured before it had experienced significant throttling and before the vibration from the D004 orifice.
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If item (a) is correct it appears that the valves can withstand the amount of_ throttling use applied at Clinton.. However if item (b) is correct and if such an amount of throttling is applied again of the disc nut and disc may again become disassembled. Further review of the test records or discussions with test personnel may shed more light on this.
In any event throttling should be minimized.
. 2.3 Cracks and Fractures in Stem. F010 Valve The main fracture severing the valve stem was initiated intergranularly
- 4 (IC) and then rapidly propagated by brittle fracture, Figure 12 through
- 14. Longitudinal cracks were also found emanating from the main fracture which were intergranular. There were also other cracks in the stem located at the bottom radius of the groove housing the split ring retainer, Figure 16 and 17. There are several notable attributes'of this stem fracture and these cracks as follows: .
- a. It is unusual to see intergranular cracks this deep with so little apparent time exposed to water considering the low temperatures involved (ambient temperature)
- b. There is corrosion on the stem just above the back seat suggesting that the valve was backseated with water present for a long period '
of time. F011 valve does not show this corrosion.
- c. The valve stem shows a considerable gradient in hardness from one end to another. In the area of the fracture the hardness in RC40-41 while at the other end it is RC30-31. This suggests a tempering temperature of less than 950'T at the lower end and approximately 1050'F at the upper end.
- , d. The fracture exclusive of the IGC area is almost entirely a brittle cleavage failure. This would correspond to a notched tensile
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fracture of material heat treated in the 800-1000'F range, Figure 2.1 e
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1 Considering the above items it appears likely that the IGC in the stem fracture occurred or at least initiated during the period of time when the stem was back seated. Other failures similar to this have started in the packing area and this break would be located in the packing only if the stem were back seated. The stem was probably under significant load from the motor operator which if not actually causing the crack to initiate would have accelerated, the initiation and the propagation of the cracks. The cracks in the retainer ring area show that cracking can start in Type 410 at this hardness level in an, area which is creviced and
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which has a high stress concentration but has essentially no applied stress.
4 2.4 Basis for Current GE Hardness Limits on Type 410 S.S.
There are numerous accounts of failure of Type 410 and 416 stainless
, steels in the literature with hardness of 38-42 RC. On two occasions CE has found cracking of Type 410 stainless steel in the 31-32RC hardness range. There were several factors in common with these failures as follows: .
Operating Meta 11ographic Stress Compone5t Temperature Material Structure Level Other (a) i inch Estimated 416(?) Banded with Probably high Cap Screws at 125-150'F heavy sulf- since it was ide inclus- a fastener ions (b) 1 3/8" %200*F 410 Banded with s46,000 psi ICSC Dia studs heavy sulfide started in inclusions area of l inte rmit-tent wet-ting and drying As a precautionary measure GE has since imposed a limit of RC28 for newly purchased Type 410SS sesinless steel.
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3.0 DESCRIPTION
OF DAMAGED VALVE PARTS j
3.1 The following damage was found for the F010 Valve:
- s. Broken Valve Stem - As shown in Figures 1 and 2, the stem was broken l-above the back seat. 1 7/8 to 2 1/2 inches beyond the newly formed
, back seat area on the shaft.
- b. Stem Upset in Area of Backseat. The upset was caused by the motor l pulling the stem into the backseat, (Figure 3 and 4).
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- c. Coused Area on Stem - See Figure 5. The heavily abraded area on l- both the upper and lower part of the stem, vere due to the bottom shaft (attached to disc) becoming cocked in the valve and the upper shaft scraping against the lower shaft when the valve was closed.
See Figures 5,6, and 8. -
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- d. Bent Stem Clamp The stem clamp fastens t'o the stem by a key and set L
b screw and its purpose is to prevent stem rotation. The stem clamp was bent approximately 1 1/2 inches as shown in Figure 6. In I addition the clamp had been shifted on the shaft approximately 1/2 inch. The clamp was bent when the shaft broke and cocked in the valve thus allowing the shaft to over travel approximately two inches. Figure 8 illustrates this travel.
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- e. Back Seat in Bonnet Deformed - While the back seat did not appear to be deforned from visual inspection, it was later found that the l angle of the seat was not correct. This deformation most likely occurred when the motor pulled the stem into the back seat.
- f. Dise and Stub Shaft Wedged in Valve at an Angle, Figure 7 and 8.
The lower part of the stem and the dise were found tightly wedged in ,
the valve at an angle. The disc had a circular shaped indentation i
'on the lower edge where the disc was pressed into the stellite seat and the upper flanged part of the disc had two l
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impressions matching the guide ribs in the valve body. The disc was not seriously damaged but maintenance was unable to separate the nut from the disc and subsequently cut the lower part of the. disc from the upper part (to avoid cutting the stellite and then saw cut the upper part of the disc to allow disassembly of the disc from the stem.
- g. Seat Chipped - There was some deformation of the seat due to the pressure of the disc on the seat at a local area also resulting in a small chip of stellite flaking away. The chip was not in the seating plane and lapping should correct the small amount of deformation.
3.2 The following d,amage was found 'for the F011 Valve a.- The dise nut was unscrewed from the disc and separated from the .
stem. There was no apparent damage to the threads or shaft.
- b. The split ring retainer was separated from the assembly. One-half of t'he retainer was found just downstream of the D004 pressure reducing orifice and the other half was found in the condensate storage tank.
The orifice was heavily marked by impact and bowed concave toward the downstream side.
- c. The seem was badly aalled due to the motor pulling the stem into the backseat, Figure 9.
- d. The back seat in bonnet is badly cracked as a result of the stem being pulled into the back seat. Figure 10.
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- e 4.0 METALLURGICAL EVALUATIONS L
The following metallurgical evaluations were performed on the F010 valve i stem to aid in determining cause of failuret 4.1 Chemistry A chemical analysis yielded the following results and confirmed that the stem material was 410 stainless steel meeting requirements of ASTM A276.
l Element. Weight %
I- Carbon 0.09 1, '
- Chrome 12.35 r
Phosphorus 0.017 Sulfur 0.007
!. Nickel 0.37 l
l l 4.2 Hardness Hardness traverses are shown in Figure 11. There was a hardness gradient along the length of the shaft from RC41 at the disc side of the shaft to l- RC30 at the threaded and of the shaft. There was also a gradient through i
l the thickness of the shaft and this varied from RC38.5 at the surface to a maximum of RC42.7 near the center.
i l .4.3 Metallography l 'A metallographic section was taken near the failure point and it was
! found to be typical for Type 410 stainless steel microstructure.
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4.4 SEM Examination of Fracture Face i
Both fracture faces from the lower stub piece as well as the upper shaft were examined by scanning electron microscope (SEM).
+ Both pieces were quite badly hammered but the upper one was in better shape and the origin of the crack was identified, Figure 12. A band of intergranular fracture was found approximately 30' in length and 1/2 inch in depth in from the circumference of the shaft. The balance of the fracture was cleavage indicating a rapid fracture. Figures 13 and 14.
l 4.5 Longitudinal Cracks Transverse to Main Fracture There were several short longitudinal cracks extending from the main fracture the longest of which was approximately 3/8 inch long. This crack war t oken open and examined by SEM and it was found to be
- j. completely intergranular. Figure 15 shows metallography of one of the -
l longitudinal cracks.
L i 4.6 PT Examination of Shaft Reveals Additional Cracking When penetrant examination was performed on the shaft several other cracks were found in the groove where the stem retainer rings are located. The largest of these cracks were broken open and a crack i approximately 1 1/2 inches long with a maximum depth of 1/8 inch was found. See figure 16. Examinations of the fracture surface with SEM showed it to be intergranular. This section was fractured at room temperature and less than 1% ductile shear was identified on the fracture surface.
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.'. r FIGURE 1. F010 VALVE DISASSEMBLED. BODY IS BLANKED OFF WITH A COVER PLATE -
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FIGURE 2. F010 VALVE DISASSEMBLED SHOWING l BROKEN VALVE STEM l l
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Effect of Tempering Temperature on Tensile Properties Type 410 200 ,
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TYPICAL PROPERTIES FOR TYPE 410 STAINLESS STEEL . ,
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m , OILQUENCHED AND TEMPERED 14 HOURS. \
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TEMPERit4G TEMPERATURE. 'F, i !
1 FIGURE 2.1 TYPICAL IGCHANICAL PROPERTIES FOR TYPE 410 STAINLESS STEEL TEMPERED AT VARYING TEMPERATURES o
SOURCE! Source Book on Industrial Alloy and Engineering Data, American Society i for Hotals, Hatala Park Ohio, 1978, p229 ,
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l FIGURE 3. I LOWER END OF BROKEN VALVE STEM (F010) '
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- FIGURE 4. CLOSEUP VIEW OF UPSET AREA ON STEM I
(IN RECION OF TIIE BACK SEAT) (F010) ,
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,I l FIGURE 5. COUCED AREAS IN UPPER PART OF STEM (ABOVE)
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S!! AFT Wi!EN LOWER SIIAFT WAS COCKED IN VALVE.
l SEE ALSO FICURE 8. (F010) i 1
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1 j FIGURE 7. UPPER AND LOWER PARTS OF Ti1E DISC (SAW CUT i
TO ASSIST IN DISASSEMBLY) Sl!OWING DEFORMATION
! WilERE Tile DISC WAS PRESSED AGAINST TIIE CUIDE l RIBS (UPPER Pit 0TO) AND T!!E SEAT (LOWER P110TO)
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1' Sl! AFT AND APPROXI" ATE ANGLE FOR DISC, F010 VALVE NG n
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. GALLING DUE TO PULLING STEM INTO BACKSEAT IN BONNET
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UPPER PHOTO SHOWS STEM PARTIALLY PULLED i INTO BACK SEAT. LOWER PHOTO SHOWS CRACKED STELLITE RESULTING FROM PULLING STEM INTO BACK SEAT (F0ll VALVE)
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Appendix A DESCRIPTION OF HPCS SYSTEM A.l.0 High Pressure Core Spray 3ystem (HPCS)
The purpose of the high pressure core spray system (Figure A-1) is to depressurize the nuclear boiler system and to provide makeup water in the event of a loss of reactor coolant. In addition, the high pressure core spray system prevents fuel cladding damage in the event the core becomes uncovered due to loss of coolant by directing water down into the area of the fuel assemblies. The makeup water is jetted as a spray over the area of the fuel assemblies from nozzles mounted in a sparger ring located inside the reactor vessel above the fuel assemblies. The high pressure core spray system is an integral part of the total design for Emergency Core Cooling (ECC) which provides for adequate core cooling and depressurization for'all rates of coolant loss from the nuclear boiler. -
Cooling water for the operation and testing of the high pressure core spray system comes from the condensate storage tank. Upon depletion of this supply, the system automatically transfers to the water in the containment suppression pool. Water inventory lost from the nuclear boiler system drains to the drywell and then into the suppression pool thereby providing an inexhaustible supply of cooling water allowing continued operation of the high pressure core spray system until it is manually stopped by the operator from the control room. System piping and equipment are maintained full of ccadensate water to avoid time delays in filling the lines and to avoid hydraulic hammer.
_ =
4 Operation of the system is automatically i i i redundant signals indicating low reactor vesseln t ated from independent pressure in the primary containment. water level or high remote-manual startup, operating, and shutdownThe system also provid
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in the discharge line prevents back flow from th A testable check valve when the reactor vessel pressure exceeds g the hi he reactor pressure vessel system pressure as can occur during initial activ pressure core spray low flow bypass system is placed into operati ation of the system. A the nuclear system pressure and permits on fl until pump head exceeds ow into the reactor vessel.
The high pressure core spray system can be t operation or when the plant is shut down. ested during normal plant pump suction is from the condensate storage tankDuring normal plant operati line to the condensate storage tank.' During with a full flow return is from the primary containment pressure sup plant shutdown, pump suction flow return line to the suppression pool pression pool with a full for tha .
demand signal. automatic transfer to the service mode upon thThe c .
e presence of ECC A.2 E22-F010 and E22-F011 Valves _
Note in Figure A-1 that return line running to the condensate ank.
storage n the testtthe F010 and operate during the test mode; otherwise th These valves only ey are in the closed condition.
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l Appendix B DESCRIPTION OF F010 AND F011 VALVES Bl.0 Valves The F010 and F011 valves are ten-inch 900 lb globe stop, bolted bonnet,
' rising stem, butt welded ends, cast carbon steel, stellite tria motor operated valves manufactured by the Anchor Darling Company, Figure B-1.
4
, These valves are'primarily designed for tight shut-off and limited throttling.- All sections of the body are designed to provide absolute '
q tightness ensuring minimum pressure drop. Their use, however, is limited to those systems where head losses are not critical as the internal flow i passage' creates a prensure drop across the valve. With the disc in the full open or any interamediate position, the fluid is allowed to flow through the seat area ac a rate determined by the position of the disc. ,
With the disc in the closed position, the force of the stem provides a mechanical seal between the disc and seat and effects a shut-off at the valve.
- B2.0 Motor Operators t
B2.1 The motor operators are Philadelphia Gear Corporation (Limitorque) SMB4
- units. Figure B-3.
Each operator is provided with a high starting torque motor, reduction gear, handwheel for manual operation, a handwheel de-clutching device, a double torque switch, 4-train geared limit switches and a hammer blow device.
The handwheel on each operator is automatically declutched whenever the ,
drive motor is energized. A lever is provided to engage the clutch when manual operation is required. A hammer-blow device is furnished to permit to or to reach full speed before load is applied. The design is such that the operator can be removed from the valve for maintenance without dismantling the valve.
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- 1 B2.2 Torque Limit Switches and Position Limit Switches I Adjustable torque switches assure power cut-off in the event motor is overloaded when valve disc or shaft movement is restricted. The switches operate in both opening and closing directions of travel and are separately adjustable for torque in either direction. See figure B-4.
Rotary geared type, 4-train limit switches are provided. Each motor operated valve actuator is_provided with four mechanically independent position = witch contacts that are indexed to monitor positions of valve
. travel during both motor and hand operations. Each switch has four electrically independent contacts.
There is a position indicator for remote indication of valve position. i B2.3 Meter Control Circuits
- a. Valve Closure F010 and F011 valve motor control circuits, whose safety direction is clo9e are designed such that either LS7 or TS17 will allow the valve to go fully closed. See figure B-2. Since full closure is imperative for all nuclear boiler isolation valves, TS17 is used to mechanically torque the valve tightly closed. In the event TS17 fails, LS7 will conplete the closing cycle. LS7 must be set such that it epens just before TS17, thereby allowing TS17 to break the ' seal-in. This design feature prevents cycling of the valve in the event of torque
. switch relaxation. During testing, the valve motion being sealed-in through the torque switeb provides valve protection from an overtorqued condition.
- b. Valve Opening For opening the valve the limit switch must be set to shut off the motor before the stem enters the back seat. The torque switch should be set to as low a setting as is commensurate with proper opening of the valve and yet provide some protection against damage to the back seat in event the limit switch malfunctions.
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- 1. Torque sernngs must be mode wirn pc. =05 ond ser pointer. pc. = 7. or de. insunng right shur off.
- switch mounted in Limitorque. 53'ed 'O'Que Sem"9.The higher the num- 6. A moximum stop semng plore is fur-ber the higher the torque outpur of the nished on oli units. Do not exceed this ser-1 Moke sure oli e!ectnc power is off. unit. nng werhout consulnng factory
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+6 i 1 ACTUATING L.NK ' __ -- ~ts M e Aew = ' 8 <1 SHAFT g me emwme,r*% . - . to . 2 CONTACT SUPPORT I W14# simyygGUE-LllMTER A.* - l 1? 1 BUSHING , I 6 w3 swSw MON c.~~ e . - 14 1 BEARING - ' O <15 **2 **-CONTACT FINGER - "'t~- - 16 4 TERMINAL STUD 1 J, g g 's--COMPR. SPRING ~'s' l .# . l* ^ .._ ' T s TORSION SPRING "T9 trJSULATOR 20 1 FLAT WASHER - w -- 6 I j 'f 21 -1 O '-RING - 22 2 SCREW ROUND HD / \ @ ' SLOTTED %-18 x 56 LG .i .- -" t 23 s.1 mROLL-PIN 3.22OIA rsmLG f % l 24 1 LOCKWASMER'e @ '"D . -2F.3 *WIHRUSTWASHE.R .M - l ,,' - 26 2 sneLOCKWASMEA ,,,, g ,.' O 77 'W? --tOCKWASHER s1o s 28 1 ROLL PIN 3/32 Ol A x 3/4LG O '._" b. ' b [b ~ 29 x8 : . HEX. NUT siO-32 ~.- - 30 2 NEX NUT s6-32 . <*70 Mg 6 411et ..vtCOTTER PINT pDIA. 32 1 SCREW SOC. HD. 3 x N LG. @ @' ^\ , i \ ) l CAP M-20 x 54 LG @\ t 1 a3; ,. 5: A;4me as.go . SCREW-PAN g og tg HD.SE.LF-TAPHNG W . - - ' - , J 34 2 SCREW-MEx. SOC SET ! s6 32 x s,sLG g N I ifhdh h J4 I - @ ~ O 36 1 SCREW-MACH. RD. HD 0 9 6 @O @@ F C) 35-40 x 2ne LG ! g. OST-% WAX' AS REQUIRED '4 '" * . g 39 ? LOCKWASHER 'p M DD + I - As. x t f,-o .R tNG ' < %.** * % ~ ** * - 46 1 MOUNTING BRACKET g g } , . ~ ' FIGURE B-4 -- r___,# - >I i 9A -d-r% e.s. '
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- c. - - . . --. . . . . - . ~ . . , .-.
Appendix C HISTORY'0F F010 AND F011 VALVES . Following is a brief outifne of che history of the F010 and F011 valves. 4 i 8/74 Valves were ordered from Anchor Darling, Hayward California by General Electric 8/77 Valves fabrication completed by Anchor Darling. Stems were heat treated by Oakland Heat Treating (Lindberg). 9/77 Valves shipped to Clinton Site and placed in storage 5/80 Valves installed at Clinton Site. Dec 84 - Jan 85 System operated for Integrated Flush - C&IO Phase 4/29/85 F011 valve stem guide is found disconnected and wedged against base of bonnet. Valve fixed on 6/20/85 but breaker keeps tripping. 5/21/85 MUR-17593 written to fix breaker trips on F011. Cause - tripping due to residual MOV rotor / stator motion / field development. Breaker overload increased from position 4 to 5 6/5/85 FPR written to address F011 breaker trips 7/885 FPR #3489 written for all valve breakers Preoperational Phase 8/23/85 Performed vibration measurement of RST line per XTP-VI-01. See attached sheets for actual data. FPR #6065 written to request relocation of orifice O u - __ - , - _ _ - A. - . .. ~ . . . ~ , _ . _ . - - . - . . ...x.~ . - . . e 8/28/85 Received engineering evaluation to relocate orifice temporarily. .' CWR 16712 performed the relocation. 9/13/85 Performed RST to RST flow test per PTP-HP-01. Run time: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 18 min . Flow Regime: minimum flow (315 gpm) to 5600 gpm Engineer noted apparent piping / valve resonance et = 3300 gpm 9/19/85 FECN's 22,103 and 60,336 were issued which approved the relocation of the orifice. CVR 17403 submitted to manufacture new orifice. 10/11/85 Found F010 stem clamp collar bound on the stem and bent. CR 1-85-10-040 vritten, noted that similar problem occurred on F011 4/29/85 (MWR B9425). Addressing possible damage to stem, NCMR g 1-1918 says " damage due to improperly staked set screw. THis generic condition to be addressed by 10CFR 21-85-02/21-85-05. - 11/02/85 During testing, it is reported that a loud noise like something moving down the inside of the pipe and coming to a resounding stop. 11/03/85 Reported that 1.P.Co. found 1/2 retainer ring downstream of orifice D004 and disassemble F010 and F011. 11/04/85 Received JK575 requesting help 11/05/85 FDDR LH1-5466 R/0 Issued 11/06/85 George Hanson at site 11/08/85 FDDR LHI-5466 R/1 issued l e O _e 4 e A 1 -w-_- m f N.UCLEAR SERVICES DEPARTMENT
- SAN JOSE. CAUFORNIA 95125 November 1983 SIL No. 399 File Tab ,A Category 3 NONMETALLIC MATERI ALS FOR NUCLEAR STEAM SUPPLY SYSTEMS The following recommendations are for nonmetallic materials such as gaskets, valve stem packing and lubricants which are used in nuclear steam supply systems (NSSS) and which will remain in service as part of the operating system exposed to NSSS coolant. This information is the result of continual development, changing over the past several years to reflect latest available technology and operating experience. Therefore, all of these criteria might not have been applied in their present form to any one material in the past, but it would be prudent to follow these recommendations in the future.
DISCUSSION Selection of nonmetallic materials such as gaskets, valve stem packing and lubricants is an important area of plant maintenance. The following recom-mendations may help in extending the life of metallic materials associated with them. General Electric does not endorse any particular nonmetallic materials or manufacturers, but the following limitations should be considered by BWR owner / operators who select and use such materials. RECOMMENDATIONS General Electric recommends that the following be considered by utilities when selecting nonmetallic material such as gaskets, valve stem packing and lubricants for the NSSS:
- 1. Vendor certification or alternate testing should be obtained to assure that contaminants do not exceed the following:
Total Fluo rine 300 ppm Chlorine 500 ppm Sul fur " 700 ppm Heavy Metals 500 ppm ***
- - Quantities are based on total element contents, not leachables.
" reactive" sulfur with chemical valence less than +6 (i.e. sulfite, sulfide, etc.). If active sulfur analysis is not done, then all of the sulfur is assumed to be active sulfur.
- - No single one of the heavy (low melting point) metals should constitute more than 200 ppm. The eleven heavy metals of concern are zinc, cadmium, mercury, lead, tin, silver, arsenic, antimony bismuth, gallium and indium. Analysis of all or some of the heavy metals may be waived if the vendor certifies that there are no deliberate additions or reasons to exp;ct significant GENERAL h ELECTRIC
=================--- . , W- . . rSIL N'). Page 2 quantities of these meta:s to be present. A 2. There the should beorno manufacture added constituents packaging of the product.of nitrates or nitrites used in For additional information contact your local General Electric service rep-resentative. Prepared by: G.R. Hanson/0.R. Helsing Approved by ! N' Issued by: M. [ pSaNo D.L. Allred, Manager R.E. Bates, Specialist Customer Service Information Service Comunications Product
Reference:
A71 - Plant Recomendations
,s
. - - . . . _ _ . . .. . . . ~ . . - - - - - _ . - . _ - -.
i .
~
. e ACKNOWLEDGEMENT Appreciation'is expressed to.the following individuals for their significant -
contributions to the preparation of this document: Clyde Nieh for his technical input regarding valve and system details, John Cochran for his technical input from the Clinton site, Barry Gordon for his careful review of the document and to Alicia Ord mez for her patient retyping of the many corrections.
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A n naten SC Fu In 39
- DATE OF ISSUE '55UED :
CENERAL ELECTRIC : : FDDR NO. LH1-5504
- : REVISION O FIELD DEVIATION DISPOSITION , NOV 2 2 1985
- SHEET 1 0F 4 REOUEST : :
PSF K en PROJECT Clinton UNIT I : FDDR ORIGINATOR DATE EQUIPMENT (MPL OR DESCRIPTION OR BOTH) E22-F010 : J.T. Cocht n 11-21-85
- ,3.6-1 DOCUMENT NO. :SH NO.: REV : TITLE "
VPF3238-682-2 : Fig.4: Instruction Manual Motor Operated Carbon Steel Valves DEVIATION DESCRIPTION NCMK 01-1960 ,
Vcive E22-F010 has been damaged during test:
c) The valve stem is fractured approximately 1 3/*" above the back seat level.
b) The disk was cut apart during disassembly, c) The disk nut was cut apart during disassembly.
d) There is a chip out of the hard face seat ring. mb/rs c) There are several gouge in the valve pody disk guide ribs. (J g .
SITE QC CONCURRENCE g g /* $ DATE///.2.2/g- FIELD CONCURRENCE 9 s-(,e.oss,)
X SUGGESTED DISPOSITION DATE/[-)E-B EXPEDITED DISPOSITION
'FTr~ part numbers refer to the Reference (Anchor Darling Dwg. 2999-3 Rev.D) Sheet 3 of this FDDR. The following steps may be performed out of order to effect repairs.
a) Penetrant test the bonnet back seat hard face part 34. If free of indications the bonnet is suitable for reuse.
(CONTINUED ON SHEET 2 0F THIS FDDR)
Crst: 8Y275 Material:- 408-20122-910 DISPOSITION NEED DATE 11-21-85 EXPEDITED DISPOSITION APPROVAL BY DATE FINAL DISPOSITION Some as Suggested Disposition ,
QC. ~~Vesth flye eejtwemeds' of-#iliW Ad he AWW,qis ECA/ECN N/R FDI NO. N/R
. JUSTIFICATION OF DISPOSITION DECISION (SAFETY, RELIABILITY)
D: mage to valve parts have required substantial repairs. Replacing broken parts and p2rforming repair of pressure boundary parts in accordance with the Code Section XI will restore the valve to design conditions resulting in safe reliable operation.
DESIGN VERIFICATION STATEMENT The disposition will restore the valve E22-F010 to an acceptable configuration based en an independent review and engineering judgment, E
VERIFIED BY
- D E NO. IF APPLICABLE Clyde Nieh f?[
c
- 21 DATE 11-22-85 UIPMENT IS SAFETY RELATED QUALITY : APPROVALS DATE N/R : SAFETY FUNCTION IS AFFECTED
- : YES NO X
- COMPLETION RECORD : SUPPLIER ACT DAD SYSTEM ENCR : : * *I
- {dkl.&f6 ENGRG Q
. //-st. 8.5' :
DISTRIBUTION CODE INTERNAL EXTERNAL J.T. c ran //.11-ff : : FIELD WORK ORDER NO.
j g lDISPOSITIONCOMPLETE DATE ORCT M GER t lSITEQUALITYCONTROL
- : )
- FIELD MANAGER I
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- CENERAL ELECTRIC FIELD DEVIATION DISPOSITION REQUEST : !
i- 't :
IFDDR NO. LH1-5504 Rev.0 SHEET ~
2 0F 4 :
L : PROJECT' Clinton I DATE 11-21-85 : l
! -I :
EXPEDITED APPROVAL
! t :
I
' EQUIPMENT (DESCRIPTION AND/0R MPL) E22-F010 t
SUCCESTED DISPOSITION: (CONTINUED FROM SHEET 1) : !
- Under the direction of an Anchor Darling field representative, perform the folloiwng :
- : work: Steps (b) through-(1). !
b) Inspect the bonnet back seat (Part 34) and dress as required to meet design :
s requirements.
a c) Break sharp corners and blend the chipped area in the valve seat so as to preserve : -
a the maximum valve seat width. :
- d) Bland the gouge marks in the valve body disk guide ribs. The work must be : '
performed under Code Section XI since this is a pressure retaining part. :
L a) IPC is to supply the following replacement parts: :
1 1) Stem part (5) Anchor Darling Drswing 5287-2-2. :
a 2) Disk nut part (64) Anchor Darling Drawing 5287-2-2. :
t 3) Stem clamp, part (25) or straighten the bent stem clamp. :
i a 4) Valve dis 4gart 4) Anchor Darling Drawing 5287-1-5 or equivalent. A :
j r. possible sou s to remove a disk from the Black Fox valve without operator.: 1
- 5) Valve stem packings (parts 16 and 16A).
3
- t. 6) Replacement gasket part (18) :
f) Since the disk is a pressure retaining part, the use of a substitute disk :
t must be resolved with the authorized code inspector. :
l 8 g) Check shaft dimensions and bonnet back seat dimensions to assure that a proper :
3 back seat can be achieved. :
- 8 h) Using the procedure on Sheets 4-2 and 4-3 of VPF 3238-682-2 (Anchor Darling Valve
- IOM Manual) lap the seat to the point where a seal line is established. :
j t 1) Reassemble the valve per VPF 3238-682-2 Sheets 5-4 and 5-5. .
- I j) Reset limit and torque switches and manually operate the valve to assure that they :
j t are properly set. CAUTION: Operation of the valve by means of the motor, without :
' s having the switches properly set can lead to destruction of the back seat. :
r : Under close surveillance, operate the valve by means of the motor operator : l l t to assure that the limit scope are working properly. : r i t- k) Check bonnet and stem leakage, correct any observed leaks. :
l 1) Assemble code data package to substantiate acceptable valve repairs. :
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- GENERAL ELECTRIC : FDDR No. LH1-5504 '
. t . FIELD DEVIATION, DISPOSITION : Revision 0 AFFECTED DOCUMENTS LIST : Sheet 4 of 4 4 a f = Documents Transmitted to Document Control Center : Job No. 8Y275
- * = Documents Transferred to S&L for Maintenance : WPSS ACTIVITY TYPE R .
8 SCHEDULE COMMITMENTS TO MEET ESTABLISHED SOP CYCLE DATES -. =. . . . __. . . .
-t . : : : 't : UPDATE WITH '
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- P a 5'Orr T7 CD?ERAL ELECTRIC ,a DATE OF ISSUE gggg :
- : IDDR NO. ,___
, FIELD DEVIATION DISPOSITION _: LH1-5504 NOV 2 71985 : REVISION ~
rI REQUEST *
- SHEET 1 0F 5 PROJECT _ Clinton :
UNIT ' '* I # 8 : FDDR ORIGINATOR EQUIPMENT (MPL OR DESCRIPTIONE22-F010 OR BOTH) : J DA" 11 DOCUMENT NO. 2 OE T. Co hr n VPF3238-682-2:SH NO.: REV : TITLE
- Fig.4: :
E __ DEVIATION DESCRIPTION Instruction NCMR 01-1960 Manual Motor Operated Carbon Ste(1 Valves _. This FDDR LH1 5504 Rev.1 completely supersedes FDDR LHI-5504 Rev 0 Valve E22-F010 has been damaged during test: . . b) The disk was cut apart during disassembly.a) The valve stem . c) The disk nut was cut apart during disassembly. d) There is a chip out of the hard face seat ring. e) There are several gouge in th valve body dish guide ribs. SITE QC CONCURRENCE 7b M MATE FIELD CONCURREN 3_X_ . SUGGESTED DISPOSITION / _,m DATF//fy. F EXPEDITED DISPOSITION "
/
~
For part FDDR. numbers refer to the Reference (Anchor Darling Dwg a) Penetrant test the' bonnet back seat hard face part 34.The . the bonnet is suitable for reuse. ' If free of indications Cost: 8Y275 Material: 408-20122-910 (CONTINUED ON SHEET 2 0F THIS FDDR) DISPOSITION KEED DATE 11-21-85 FINAL DISPOSITION EXPEDITED DISPOSITION APPROVAL BY DATE Same as Suggested Disposition. e ran/n/as-St To V U M M ) of: EWL5toA3 ) ' ECA/ECN N/R FDI NO. N/R Damage to valve parts have required substantial repairs. JUST restore the valve to design conditions resulting in safe . will re
~ DESIGN VERIFICATION STATEMENT nut is the preferred method of locking disc to disc sc to nut. disc R
~
/
APP OV S g DATE VERIFIED BY //p p c 4 .a, _ r ,.
@S DATE 4 -J W
/ /' M 3,/n /<.< :: DRF N/RNO. IF APPLICABLE : THIS EQUIPMENT IS SAFETY RELATE; os QUALITY :
~
_N/R
/ ~
- APPROVALS DATE :
YES X NO
- SAFETY FUNCTION IS AFFECTED
^ : YES NO X f
fCOMPLETIONRECORD:5UPPLIE
// .2.~2 0: REQUIRED BY R.E. : REQUIRED DISTRIBUTION CODE Nrb E
// 2.7 .1~
- FI M WORK ORDER NO. i
~ jjq,p g-- ; DISPOSITION COMPLETE PROJECT V.ANAGCR
- DATE I SITE QU5LYTY CO:GROL j
- FIELD MANAGER l
- i
. . - ,.- ~.~,...- - - ~- - - - -
i -
- - %a. (o op 57
= *'
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- = p
- PROJECT Clinton I SHEET 2 OF 5
- EXPEDITE APPROVAL- - DATE ~
IT~21-85 )k
. EQUIPMENT'(DESCRIPTION AND/OR E22-F010MPL) .l : 'SUCCESTED (Rev.0)
DISPOSITION: (CONTINUED FROM SHEET 1)
- t
- i. UnderSteps work: the direction (b) through of (1).
an Anchor Darling field representativ t : e, perform the following b)' Inspect requirements.the bonnet back seat (Part 34) and dress as required t o meet design c) the Break sharp corners and blend the chipped area in the valve seat maximum valve seat vidth. so as to preserve i, a d) Blend the gouge marks in the valve body disk guide ribs I The work must be C
~
- e) IPC is to supply the following replacement parts: ng part. performe
- 1) Stem part (5) Anchor Darling Drawing 5287-2-2.
- 2) Disk nut part (64) Anchor Darling Drawi.ng5287-2-2.
, : 4) Valve disk part (4) Anchor Darling Drawing 3) Stem .
I
- 5287-2-5 or equivalent. A
- 5) Valve stem packings (parts 16 and 16A).possibleox valve withoutsource operator.,is
- 6) Replacement gasket part 18) a f) Since the disk is a pressure r(etaining part,
- must be resolved with the authorized code inspector.the use of a substitute disk :
p g) backCheck shaft dimensions and bonnet back seat dimensions to as ; seat can be achieved. 1 : sure that a proper -
- h) Using the procedure on Sheets 4-2 and 4-3 of VPF 3238-682 2 : (A nchor Darling Valve
- IOM Manual)
- 1) Reassemble lap the th., valve per VPF seat to the point where a seal'line is : i
- 3238-682-2 established. :
i
- j) Reset limit t et.
are properly d torque switches and manually operate thSheets 5-4 and 5 5 . . .o e CAUTION: i 0"
- having the switches properly Operation of the set can valve lead by means ofofthe to destruction th motor, wi Under close surveillance, operate the valve by means of th e back seat. :
p : to assure that the limit stops are working properly e motor operator : 3 : k) Check bonnet and stem leakage, correct any observed leaks .
- 1) Assemble code dats package to substantiate acceptable .
e repairs. valv : , (Rev.1) : j : (M) In reassembly of :he disk to the stem, the disk nut th : +
's tach other.
each welded to the disk, Part 11 with three one inch reads l Part 117 are to be :
- Per Anchor Darling Drawing 93-14884 ong tack welds at 120' to
's nut materf al is A108 and the disk material is SA352.Rev.T (Sheet 4 of this FDg ge y:q i for the welds and visually inspect Use 9'"YW 8
i ] procedure welds. for the absence of cra kid: eid c ng in the
- a (h)'only.The Anchor Darling 'teld Representative is required for St
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- hTSS ACIIVITY TYPE R - :
6 = Documents Transmitted to Document Control Center :
- * = Docu:mnts Transferred to S&L for Raintenance
- SchwULE COOTI! CTS 'IO 61;r EsTABLISIED SOP CYr7R DATES : : : UPDATE WITH : ,
- : : RESP : RESP : FDDR ISSUE :: ;
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- MPL ITH! NO. : CQP : IZ'R : YES : NO :
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,- CCIIRE ILIO ~RIC : : 70DR NO. LH1-5503
- : RE7ISION O FIELD DEVIATION DISPOSI!!CN : NOV 241cES : Su!ET 1 Or u I
REOUIST : . _ : PROJECT Clinten G.GIR Of I : 7DR ORIGEIATOR DATE 8 EQUI? MENT OGL CR DESCRI?IION OR 30Td) E22-7011 : J. T. Cochran e 11-21,85
- ""hvl &
. uCCUMEIT NO. :SE N0.: REV : TITLE VPF 3238-682-2: Fir.4 : : Instruccion Manual Motor Ceersted Carbon Se sel valve DEVIATION DESCRIPTION NCMR 02-0563 Valve E22-7011 has been damaged during test:
a) The integral Stallite back seat in the bonnet is cracked radially and circumferentially, there is evidence of separation from the substrate. I [ (C0hwus. CN SHEET 2) ..
; SITE OC'CCNCURRDICE /// dATEw/se/cq FIELD CCNCURREIC' ~ u J24,w DA E ^
I. SUGGESTED DISPOSITICT / EXPCITED DISPOSITICN For nart nu=bers refer to the ref erence (Anchor Darling Dvg. 2999-3 Rev. D), Sheet 3 of thir FDDR. The following steps may be perfor=ed out of order to effect repairs. a) I?C to confirs with Anchor Darling ca,..
,tjatge Bonnet ca p y aired in confor=ance with Code requirements within ; ;ix s-. site sche:1ul:.nq needs ,
b) I?C to ship the valve Bonnet (part 2) to Anchor Darling for replace =entj( ry. o. (CONTDiUD CN SHEET 2) Cost: 8T275 Material: 408-20122-910 ' DIS 70SITION NEED DATE 11-21-85 EI?DITED DISPOSITICN APPROVAL 15 DATE
'.. rEiAL DIS 20SITION e Same as Suggested Disposition. 1:0R Rcr'eaENCE ONt.1 j Quality Centrol is to verify that field work is in ee::.pliance with this ID ECA/ECN EIS TDI NO. N/R JUSTIFICAIION OF DISPOSI!!CN DECISICN (SAPETT, RELIA 3IL!!T) ~
Damage to the valve back seat prevents continued operation without repair. Actions required by this itDR will return the valve to full code compliance condition which v111 assure safe reliable operati.m. l DESIGN VERITICATION STAIIMEiT l Ths disposition vill restore valve E22-7011 to an acceptable configuration based e an i
! independent review and engineering . judge =ent, . l
' l
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VERI?ID BY Fr. Snith. J . DATE '/ ' APPROV;;LS : DRI NO. I? APPLICASL*'
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3fR 'CCMPLITICN RECC D : SUPPLIER AC , tEAD s STEx EiGR ; ; Re u!xo zT 1.E. : RE:u! n- l GIMG fiv 1..f A it/ttssi fl/Ja/Ty DISTRI2UT CN CCDE : 0 I :YES N J,, , l
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_ ._ . _ _._ . _ . _ _ _ ___._. -y Anu m % l ff%E N OF l i .* i GENERAL II.ICTRIC 7IILD DI7IATICN DIS?OS!!!CN'RE00ZC ! FDDR NO. LH1-5503 Rev. O SHIET . - 2, _ 0F __ 4 : Clint:n I DAIE ,,,.,,, ,;,11-21-4 5 :
- - : PROJECT _ . .
- EXPEDITED APPROVAL
. l- :.I t : i
! 8 : *
.j i .
*ICUI? MENT (DESCRI? TION AND/0R MPL) E22-?011
.o....L
+
4
- DE7IATION DESCRIPTICN: (CCNTINUID TRCM SHEIT L)
- b.) The stem is galled for a length of approxi=acely lig inches he' low],the back saat 2
- bevel surface. l . ' . i .'
- c.) Tield stem liardness measurements of RC 372, Brinell 333 exceed g/she desired :
- ,maxiumum value of Brinell 300.*. .li.f -
a d.) The disc separated from the~ stem and the stem retaining rinisdn're lost.
- e.) There are scratch marks on the body disc guide surfaces. : fh .
- SUCCIETED DISpCSI~ICN: (CC.uRww TROM SHIET 1)
*:h' I :
- of the bacir, seat. Replacement by use of a seal velded insert is acceptable if Code :
o : requirements are maintained. :
- c) Replace the valve seen (part 5) with a sees having a Brinell hardness less than 300. : .
J (I? Co. to supply) :
- d) Provide replacement Retaining Ring stem (part 63) (I? CO. to supply) :
- : a) Provide replacement valve sten packings parts 16 and 16A (I? Co. to supply)
- f) Provide replacement, gasket (part 18). (I? Co. to supply.) :
g) Ancher-Darling to provide a Code Package update for the repairs which will maintain : ! ( .. ' :: . the code status of the of the repaired valve. : i : Under the direction of an Anchor Darling field representative perfo= steps h,1* and :
- j. :
h) Ratfurbish the valve bcdy disc guides to blend scratch = arks. '
- 1) Check the disc seat = sting surface and refinish if required. :
- j) Reassemble the valve using the existing disc (Part 4) disc cut (Part 64), and parts :
l : f' rom item b, c, d, e and f above. :
- : k) 7.eset limit switches and manually operate the valre to assure that they are properly :
- sec. CAUTICN: Operatica of the valve by =eans of the motor, withcut having the :
. : switches properly set can lead to destruction of the back seat. :
- Under close surveillance, operate the valve by means of the =otor operator to :
e : assure that the switches are working properly. :
- 1) Check bonnet and seat leakage, correct any observed leaks. .
l : a) Asse=ble code data package to substantiate acceptability of valve repairs. :
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- GC;IR/J., ILICTRIC : .T R No. LH1-5503
- FIc D DI7IATI'*N DIS?OS!!!CN : Revisi:n 0 AFFICTID DCCUMENTS LIST : Sheet 4 of 4 s : -
- 6 = Docu=ents Transmitted to Docu=ent Control Cancer : Job No. SY275 :
- * = Dr :uments Transferred to S&L for Maintenance : 1.*?SS ACTIVI!Y TYPE R .
't SCMIDULI CC'eMI MINTS TO MII"* ISTA3tISF.ID SOP CYCLE DATIS .. -
, : : : : I.i?DATI WITE
- : : RESP : RESP : FDDR ISSUI
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- QV?? 3238-662-2 : Anchor Darling Dwg. : I22-FOLL : I5I ~ ~: CN :- *
- X
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CENERAL ELECTRIC : DATE OFS R $ :
- : FDDR NO. _ LH1-5503 FIELD DEVIATION DISPOSITION - DEC 1 9 1985 : REVISI N _
1 REOUEST : : SHEET __ 1 0F nec e e, 5 PROJECT _ Clinton :
*'ONIT"f I
- FDDR ORIGINATOR EQUIPMENT (MPL OR DESCRIPTION OR BOTH)
'E22-F011 : ..
DATE DOCUMENT NO. 12-18-8:
- SH NO.: REV : TITLE VPF 3238-682-2 Fig.4 : :
DEVIATION DESCRIPTION
- Instruction Manual Motor Operated Carbon Steel Valve NCMR 02-0563 This FDDR completely DTF .tK684
- JRev.0) supersedes LH1-5503 Rev.0.
Valve E22-F011 has been damaged during test: a) there The is integral evidenceStellite of separation back from seatthe in substrate. the bonnet is cracked radially and entially, circum SITE OC CONCURRENCE (CONTINUED N HEET 2 0F THIS FDDR de X SUGGESTED DISPOSITION DATE/2 /Mk'S FIELD CONCURRENCE d Ad M "*DATE EXPEDITED DISPOSITION There is no technical change to (Rev.0) therefore only this revision and verification. requi res justification
, fRev.0) ! For part numbers refer to the reference, FDDR.
The following steps may be performed out of order to effect repairss ( a) Code IPC to confirm with Anchor Darling that the Bonnet can be repaired in co f requirements within site scheduling needs. n ormance with b) IPC to ship the valve Bonnet
. (part 2) to Anchor Darling for replacement of the back seat Cost: 8Y275 Material: 408-20122-910 (CONTINUED ON SHEET 2 0F THIS FDDR.
DISPOSITION NEED DATE 11-21-85 FINAL DISPOSITION EXPEDITED DISPOSITION APPROVAL BY DATE Same as Suggested Disposition. Quality Control is to verify that field work is in compliance with this FDDR ECA/ECN EIS . JUSTIFICATION OF DISPOSITION DECISION (SAFETY, RELIABILITY) FDI No. N/R bonnet replacing the damaged integral backseat. eAnchor /Darlinghas The bone seal welded to the will affected. be finished to permit either MT or PT acceptance in's ga p weld is recessed and lon. not Safety and reliability are DESIGN VERIFICATION STATEMENT { 3 Verified by judgement. an independent review of the submitted data and based on engineering ,* S VERIFIEIF BY c.Nieb l
- DRF NO. IF APPLICABLE :
DATE / M - R !
~ /.2 : N/R
.QUAUITY ' ~
- THIS EQUIPMENT IS SAFETY RELATED YES X ,
N/R APPROVALS NO DATE :
,A NGR : : SAFETYYES FUNCTION IS AFFECTED NO X
a OMPLETION RECORD : SUPPLIER ACT REQUIRED BY R.E. :
/MIMfs DISTRIBUTION CODE REQUIRED t
f h NGR fy fy.77 [FIELDUORKORDERNO. I 1 gg ,,,, l - _ PROJECT MANAGER DISPOSITION COMPLETE MATE t [SITEQUALITYCONTROL
~~
- FIELD MANAGER
Pac,.a.15 mV oT') t' GENERAL ELECTRIC FIELD DEVIATION DISPOSITION REQUEST : t : f' LH1-5503 Rev. 1 SHEET 2 0F 5 :
\f 4FDDR NO. 12-18-85
- PROJECT Clinton I DATE :
' EXPEDITED APPROVAL :
l; e 8
'EOUIPMENT (DESCRIPTION AND/OR MPL) E22-F011 8
- DEVIATION DESCRIPTION: (CONTINUED FROM SHEET 1) :
? : b.) The stem is galled for a length of'approximately ll inches below the back seat ~ bevel sdrface. :
- l. t
- t c.) Field stem hardness measurements of RC 372, Brinell 333 exceed the desired
maxiumum value of Brinell 300. : d.) The disc separated from the stem and the stea retaining rings are lost. : 2 e.) There are scratch marks on the body disc gufde surfaces. :
- : I
- (Rev.1) :
e Review and approval is requested of Anchor / Darling Drawing 2999 't Rev.(J) for :
- application to Clinton valve E22-F011. . i
'e : .
. SUCCESTED DISPOSITION: (CONTINUED FROM SHEET 1) :
- Replacement by use of a seal welded insert is acceptable if Code requirements are
- maintained. e :
!, c) Replace the valve stem (part 5) with a stem having a Brinell hardness less than 300. . l (IP Co. to supply) . d) Provide replacement Retaining Ring stem (part 63) (IP CO. to supply) : (3 e) Provide replacement valve stem packings parts 16 and 16A (IP Co. to supply) : ! t f) Provide replacement gasket (part 18). (IP Co. to supply) : . l t g) Anchor-Darling to provide a Code Package update for the repairs which will maintain : t the code status of the of the repaired valve. : l l- t- Under the direction of an Anchor Darling field representative perform steps h, i and : [ l- 'j. : h) Refurbish the valve body disc guides to blend scratch marks. l t 1) Check the disc seat mating surface and refinish if required. : ) : j) Reassemble the valve using the existing dise (Part 4) disc nut (Part 64), and parts : l t from item b, c, d, e and f above. : ! t k) Reset limit switches and manually operate the valve to assure that they are properly : [ t set. CAUTION: Operation of the valve by means of the motor, without having the : ! : switches properly set can lead to destruction of the back seat. ,. : ; ( : Under close surveillance, operate the valve by means of the motor operator to - : l 3 assure that the switches are working properly. l t 1) Check bonnet and seat leakage, correct any observed leaks. : a) Assemble code data package to substantiate acceptability cf valve repairs. :
- (Rev.1) :
f"M/T'I s Anchor / Darling Drawirg 2999-3 Rev. (J) depicting a modified bonnet to accept a dropfn !
- backseat is approved for valve E22-F011 at Clinton Station. Sheet 4 of this TDDR. :
- General Electric to incorporate Anchor / Darling Drawing 2999-3 Rev. (J) into the vendor :
print file for valve E22-F011 at Clinton Station. : I 8 l t
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,: GENERAL ELECTRIC : FDDR No. LH1-5503 *
! FIELD DEVIATION DISPOSITION : Revision 0 *
[t AFFECTED DOCUMENTS LIST t Sheet ~ 5 of 5 !
\ : 0 - Docums:nts Transmitted to Document Control Center ! Job No. 8Y275 :
- * = Documents Transferred to S&L for Maintenance : kTSS ACTIVITY TYPE R !
- SCHEDULE CO.S!ITMENTS TO MEET ESTABLISHED SOP CYCLE DATES :
- : : * ! UPDATE WiTH :
- : : : RESP RESP ! FDDR ISSUE :
- DOCUMENT ID NO.
- DOCUMENT TITLE / TYPE : MPL ITEM NO. COMP ENG'R YES t NO :
- VPF 3238-682-2 : Anchor Darling Dvg. E22-F011 : 753 : CN : X :
- @ Fig. 4 2 2999-3 2 : t t :
- t t : ! t :
- : ! t ! ! !
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M
hYW,b4MEAIT' ISSUED (Pkal. O cv e D DATE OF ISSUE : CENERAL ELECTRIC : FEB 0 61986 : FDDR NO. tui-5503
- REVISION 2 FIELD DEVIATION DISPOSITION : '
p3h g gl : SHEET 1 0F 2 REQUEST : : PLOJECT - Clinton UNIT I : FDDR ORIGINATOR DATE EQUIPMENT (MPL OR DESCRIPTION OR BOTH) ~E22-F011 : C. L. Moore 2/6/86
- W. f. Wn 2 4 h t' DOCUMENT NO. :SH NO.: REV : TITLE VPF 3238-682-2: Fig.4: : Instruction Manual, Motor Operated Carbon Steel Valve DEVIATION DESCRIPTION JK-793 This FDDR supplements LH1-5503 Rev. 1.
I.P. Co. has requested that the Anchor Darling Valve Company representative presence be ccde non-mandatory. SITE OC CONCURRENCE DATFI//54 FIELD CONCURRENCE "A DATEy-4.ff, X SUGGESTED DISPOSITION EXPEDITED DISPOSITIC:1 Change "Under cl'e direction of an Anchor Darling Field representative perform steps h, i, t cnd j" to "when performing steps h, i, and j , seek the guidance of the Anchor D4.rling Field r:presentative as his availability permits" Czst: 8Y275 Material: None DISPOSITION NEED DATE 2/7/86 EXPEDITED DISPOSITION APPROVAL BY DATE FINAL DISPOSITION S me as suggested. - pc -Howe.x.r/s/u ECA/ECN N/R FDI NO. N/R JUSTIFICATION OF DISPOSITION DECISION (SAFETY, RELIABILITY) I.P'. Co. has accomplished this same task previously and nothing to be done is irreversible. DESIGN VERIFICATION STATEMENT i The disposition is verified to be adequate b/ reviewing LH1-5503 Rev. 1, VPF 3238-682-2, cnd by engineering judgment. VERIFIED BY J.R.01nier4T jf/- DATE 2 /6/8/ 3 AP Vyyf ,fAJE : DRF NO. I.' APPLICABLE : THIf EQUIP (T NT IS SAFETY RELATED MX/4tf/4* *
;////86 t N/R t TES X NO QUALITY s APPROVA'.S DATE : SAFETY FUNCTION IS AFFECTED N/R : : YES NO X
#3' A 0 8 I
!
- I COMPLETIO ECORD SUPPLIER ACTION REQUIRED BY R.E.
- REQUIRED e KfEg 9// /r/ DISTRIBUTION CODE -
" I i
^
.h*N 2/ / l IELD WORK ORDER NO.
gf 4
- 8
, DISPOSITION COMPLLIE DATE PROJECT h1AN/.GER : 1 SIIF, QUALITY CONTROL
- FIELD MANAGER
t W W IN Pa s.c. 9 0 e 1 7
- GENERAL ELECTRIC t FDDR No. Lill-5503 !
! FIELD DEVIATION DISPOSITION 3 Revision W/rM4 2 2 l
- AFFECTED DOCUMENTS LIST : Sheet 1 of 2 :
3 0 - Documents Transmitted to Document Control Center ! Job No. 8Y275 :
* * = Documents Transferred to S&L for Maintenance ! WPSS ACTIVITY TYPE R !
! SCllEDULE_COSS!ITMENTS TO MEET ESTABLISHED SOP CYCLE DATES :
- ! !
- UPDATE WITH t t ! ! RESP 8 RESP FDDR ISSUE :
DOCUMENT ID NO. DOCUMENT TITLE / TYPE t MPL ITEM NO. COMP t ENG'R : YES : NO t
! No Documents Affected : I
- t ! : :
! I t : ! I 8 : I ! ! ! ! !
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A,rscame&
% atw 97
- DATE OF ISSUE 46t @
CENERAL ELECTRIC : : FDDR NO. LH1-5503
- FEB 01,1999- : REVISION 3 FIELD DEVIATION DISPOSITION : : SHEET 1 0F 7 REQUEST : Rqg e e,
- PROJECT Clinton UNIT ' I"' s FDDR ORIGINATOR DATE EQUIPMENT (MPL OR DESCRIPIION OR BOTH) E22-F011 : J. T. Cochran 2/7/86 tGfh45 4*w r v
DOCUMENT NO. :SH NO.: REV : TITLE (/ VPF 3238-682-2: Fig.4: : Instruction Manual. Motor Operated Carbon Steel Valve DEVIATION DESCRIPTION DTFJK-797 NCMR 02-0563 DTF JK684 DTF CR 322 NCMR 2-0673 Thin FDDR supplements LHL-5503 Rev. O Rev. I and Rev. 2. (R,v. 0) Valve E22-F011 has been damaged during tests c) The integral Stellite back seat in the bonnet is cracked radially and circumferential1y, there is evidence of separation from the substrate. / (CONTINUED ON HEET 2) 4/. - p SITE QC CONCURRENCE N DATEh FIELD CONCURRENCE -f4 wre/ ' DATF/-7-T4 X SUGGESTED DISPOSITION EXPEDITED DISPOSITION S 3M 14 Bie Fst part numbers refer to the reference, (Anchor Darling Dwg. 2999-3 Rev. D), Sheet -3 of this FDDR. The following steps may be performed out of order to effect repairs.
. c) IPC to confirm with Anchor Darling that the Bonnet can be repaired in conformance with Code requirements within site scheduling needs.
I b) IPC to ship the valve Bonnet (part 2) to Anchor Darling for replacement of the back, seat. Csst: 8Y274 Material IP Co. to supply (CONTirJuaD oN SHEET 2) DISPOSITION NEED DATE 2/7/86 EXPEDITED DISPOSITION APPROVAL BY DATE FINAL DISPOSITION S=3 as suggested disposition. i Quality control is to verify that field work is in compliance,with"thiis FDDRU ",f" 9 # h h. r; s' ry;. - - EIS L * *' ECA/ECN FDI'N0fN/R JUSTIFICATION OF DISPOSITION DEJISION (SAFETY, RELIABILITY) Anchor / Darling has designed a recessed drop-in back seat which will be seal welded to the b:nnet replacing the damaged integral backseat. The bonnet to insert veld is recessed and will be finished to permit either MT or PT acceptance inspection. Safety and reliability crs not affected. The presence of an An: hor Darling repretientative is non-mandatory, sitice I.P. has accomplished this same task previously and nothing to be done is irreversible. Un of equivalent parts from the spare Black Fox valve is justified because the valves were made to equivalent purchase specification. (CONTINUED ON SHEET 3) DESIGN VERIFICATION STATEMENT R'v. I Verified based on submitted data as reviewed by C. T. Nieh. R v. 2 Verified based on independent review of the disposition described in Rev. 1. (CONTINUEDONSHgRI ED BY Jd.. [.JtIhc DATE 2 8 ( APgp ' 43rY AE : DRF NO. IF APPLICABLE : Tills EQUIPMENT IS SAFETY RELATED L , f 7/ N/R : YES _X NO QUALITY : APPROVALS DATE : SAFETY FUNCTION IS AFFECTED N/R : : YES NO X R : R : : COMPLETION RECORD SUPPLIER ACTION REQUIRED BY R.E. : REQUIRED M M~ M/hT DISTRIBUTION CODE :
" I g, E.;CRG MANACTsR pM3 for- INTERNAL EXTERNAL : .< tt _ .. . _ rx e..b.,, :th/g4 : : FIELD ,,
WORK ORDER NO. R SP R : : DI'SPOSITION CO.TLETE DATE PROJEQ.W/GER :
- :: 5}T' QUALITY CONTROL
- FIELL MANAGER
TMCfM1W ' Prn.930G2
- GENERAL ELECTRIC FIELD DEVIATION DISPOSITION REQUEST :
FDDR NO. LH1-5503 Rev. 3 SHEET 2 0F 7 :
- PROJECT Clinton I DATE 2/7/86 :
- EXPEDITED APPROVAL :
I
- EQUIPMENT (DESCRIPTION AND/OR MPL) s E22-F011 [
- DEVIATION DESCRIPTION: (CONTINUED FROM SHEET 1) :
a b) The stem is galled for a lena,th of approximately 1 1/2 inches below the back seat : bevel surface. :
- c) Field stem hardness measurements of RC 372, Brinell 333 exceed the desired maximum :
- value of Brinell 300. :
- d) The disc separated from the stem and the stem retaining rings are lost.
- a) There are scratch marks on the body disc guide surfaces. :
- (Rev. M *
- Review and approval is requested of Anchor / Darling Drawing 2999-3 Rev. (J) for :
a cpplication to Clinton valve E22-F011. - :
- (Rev. 2) a
- I.P. Co. has requested that the Anchor Darling Valve Company representative presence
- be made non-mandatory. :
r _(Rev. 3) :
- a) I.P. Co. has requested approval to use packing gland parts and stem clamp parts from the spare " Black Fox" valve, and to install new disc and dise nut.
- b) Actual. hardness test data of the new valve stem supplied by I.P. Co. is documented on sheet 4 of this FDDR. Hardness exceeds Brinell 300 in some places.
- SUCCESTED DISPOSITION: (CONTINUED FROM 3HEET 1)
- Replacement by use of a seal welded insert is acceptable if Code requirements are caintained. :
c) Replace the valve stem (part 5) with a stem having a Brinell hardness less than 300. :
- (IP Co. to supply) t
- d) Provide replacement Retaining Ring stem (part 63) (IP Co. to supply)
- c) Provide replacement valve stem packings parts 16 and 16A (IP Co. to supply)
- f) Provide replacement gasket (part 18). (IP Co. to supply) a
- g) The following items from the spare " Black Fox:" valve are approved for incorporation
- in the reassembly of E22-F011; stem clamp (Part 25), as modified by FDDR LH1-5570 :
- Rev. O, gland flange (Part 30), gland (Part 7), gland nuts (part 22)., gland bolts
- (part 21), two keys (stem clamp) (part 25a), and set screws (part 17) :
- h) Anchor-Darling to provide a Code Package update for the repairs which will maintain
- the code status of the repaired valve. Wheng paefpgg gaps h, i, and j seek the :
guidance of the Anchor Darling Field representafva as his availability permits. :
- 1) Refurbish the valve body disc guides to blend scratch marks.
- j) Check the disc seat mating surface and refinish if required in accordance with : '
s sheets 4-2 and 4-3 of VPF 3238-682-2. : 1
- k) Accept the IP Co. - supplied stem as-is. Reassemble the valve using IP Co. supplied :
dise (Part 4), dise nut (Part 64), and parts from item b, c, d, e,f and g above.
- Perform reassembly per VPF 3238-682-2 sheets 5-4 and 5-5. :
I t l i 1
. Arrau+ mew %
PM 93 ce &7 8 8 GENERAL ELECTRIC FIELD DEVIATION DISPOSITION REQUEST : tFDDR NO. LH1-5503 Rev. 3 SHEET 3 0F 7 : SPROJECT Clinton 1 DATE 2/7/86 : EXPEDITED APPROVAL : g 8 ' EQUIPMENT (DESCRIPTION AND/OR MPL) E22-F011 , I
- SUCCESTED DISPOSITION: (CONTINUED FROM SHEET 2) :
I 1) Reset limit switches and manually operate the valve to assure that they are properly t set. CAUTION: Operation of the valve by means of the motor, without : having the switches properly set, can lead to destruction of the back seat. t Under cicte surveillance, operate the valve of the motor operator to assure : s that the switches are working properly. I c) Check bonnet and seat leakage, correct any observed les.ks. : I n) Assembly code data package to substantiate acceptability of valve repairs. : 8 8
- Anchor / Darling Drawing 2999-3 Rev. (J) depicting a modified bonnet to accept a :
- drop in back seat is approved for valve E22-F011 at .Clinton Station, Sheet 6 of this :
1 FDDR. :
- 3
- General Electric to incorporate Anchor / Darling Drawing 2999-3 Rev. (J) into I the vendor print file for valve E22-F011 at Clinton Station.
8
- JUSTIFICATION: (CONTINUED FROM SHEET 1) t
- The water-wetted surfaces of the IP Co. - supplied valve stem have hardness less than :
or just slightly above Brinell 300; this indicates an acceptable condition of heat t t treat of the stem in the area of concern. I I t ! I I DESIGN VERIFICATION STATEMENT (CONTINUED FROM SHEET 1) : 1 Rev. 3 Verified by review of data submitted by IP Co. (Sheet 4) and by comparison 8 of parts descriptions of VPF 3238-682-2, Fig. 4, with the descriptions of the
- replacement parts from the Black Fox valve drawing. . gjpt.( nse) :
The disposition restores the valve to the condition intended by the friginal design.
- g '
VERIFIED BY..u.. o. a.J. ~w Date 2/7/86 :
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m L E 7)EW h h4E., C7 b GENERAL ELECTRIC I FDDR No. LH1-5503 1 i FIELD DEVIATION DISPOSITION 3 Revision 3 I I AFFECTED DOCLHENTS LIST ! Sheet 7 of 7 1 2 @ = Documents Transmitted to Docu=ent Control Center ! Job No. 8Y276 4 7e. b 1 1 * = Documents Transferred to S&L for Maintenance 1 WPSS ACTIVITY TYPE R t-7 M !
- SCHEDULE CO>D!ITMENTS TO MEET ESTABLISHED SOP CYCLE DATES 2 3 t t UPDATE WITH :
1 1 1 1 RESP 3 RESP ! FDDR ISSUE I
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