ML20210B093
| ML20210B093 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/08/1986 |
| From: | Vander Grigt R TEXAS UTILITIES SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20197F755 | List:
|
| References | |
| FOIA-85-59 1CP-PT-40-03, 1CP-PT-40-3, NUDOCS 8601270394 | |
| Download: ML20210B093 (82) | |
Text
CPSES TEST PROCEDURE MANIPULATOR CRANE Procedure No: trp-PT-40-03 Revision:
0 Prepared By:
R.
J<-Vander Crfft Test Procedure Type: Acceptance Preoperational X
Retest Test Procedure:
Reviewed By:
~
Lead Start Engineer
/>
/
Reviewed By:
4-
,d^
Manager Plant Operations N)
Reviewed By:
c _, -
IUSI Nuc1 ar Engineering '!gr.
Reviewed By:
Westin house Site Mgr.
Approved By:
h[m Date: I-[-[ 3
/ana1[e'rfuclearOperation M
Authorized to Perform By:
Date:
Lead Startup Engineer Test Results:
Reviewed By:
l Lead Startup Engineer Reviewed By:
Manager Plant Operations Reviewed By:
IUSI Nuclear Engineering Mgr.
Reviewed By:
Westinghouse Site Mgr.
8
~7 t t Approved By:
Dato:,_ _
Manager L For Information Only 8601270394 051212 PDR FOIA CARDEB5-59 PDR
ICP-PT-40-03 Revision 0 Page 2 of 47 04-5-83 TABLE OF CONTENTS SECTION TITLE PACE COVER SHEET 1
TABLE OF CONTENTS 2
1.0 TEST OBJECTIVES 3
2.0 ACCEPTANCE CRITERIA 3
3.0 REFERENCES
4 3.1 Drawings 4
3.2 Vendor Manuals 4
3.3 Documents 5
4.0 TEST EQUIPMENT 5
5.0 SPECIAL PRECAUTIONS 5
6.0 PREREQUISITES 5
7.0 PROCEDURE 7.1 Main Holst 125% Static Load Test 6
7.2 Trolley and Bridge Checks not over the Reactor Vessel 8
7.3 Bridge, Trolley and Holst Interlock Checks 10 7.4 Bridge and Trolley Index Checks and Hoist Control checks not over the Reactor Vessel 11 7.5 Loss of Power Performance Check 15 7.6 Auxiliary Hoist 125% Static Load Test 16 7.7 Bridge, Trolley and !!oist Checks over the Reactor Vessel 17 7.8 Bridge, Trolley and Hoist Mutual Checks 20 7.9 Stud Limit and Transfer System Interlock Checks 22 7.10 Auxiliary Hoist 100% Load Operations 24 7.11 Automatic Positioning Full Performance Test 25 7.12 T. V. Mast Full Performance Test 29 ATTACHMENTS For Information Only
ICP-PT-40-03 Revision 0 Page 3 of 47 04-5-83 1.0 TEST OBJECTIVES The objective of this test is to demonstrate the proper operation of the manipulator crane and its interlocks and safety features under no load, normal and overloaded conditions. The test also shall demonstrate the refueling machines capability to accurately access each fuel storage, handling, and core locations under manual and automatic controls.
2.0 ACCEPTANCE CRITERIA The system shall be deemed operational upon meeting the following criteria.
2.1 The bridge operation in manual and interlock functions preventing hoist and trolley movement, and improper operation, are verified. Performed in sections 7.2, 7.3, 7.7, 7.8 and 7.9 2.2 The-trolley operation and interlock functions preventing bridge and hoist movement, and improper operation, are verified. Performed in sections 7.2, 7.3, 7.7, 7.8 and 7.9 2.3 The operation of the fuel hoist and gripper assembly interlocks preventing hoist operation and gripper operation mechanically and electrically are verified.
2.4 The operation of the auxiliary hoist at upper limit and overload protection are verified during lifting operations. Performed in sections 7.6 and 7.10 2.5 The operation of the Dillon Load Cell and its no load and overload functions are verified. No load at 650 lbs stops hoist, overload stops hoist at 2800 pounds.
Performed in sections 7.1 and 7.4 2.6 The operation of the main hoist and gripper is verified j
under 125% (3200 lbs) static overload conditions.
i Performed in section 7.1 2.7 The full performance operation of the bridge, hoist and trolley is verified under 100% (2500 lbs) load conditions. Performed in section 7.11 2.8 The auxiliary hoist overload protection is verified in a 125% (3300 lbs) overload test. Performed in section 7.6 4
i For information Only I
t-
i ICP-PT-40-03 Revision 0 Page 4 of 47 i
04-5-83 i
2.9 The auxiliary hoist operation is verified under 100%
(3000 lbs) load conditions. Performed in 7.10 2.10 The manipulator crane is manually operable under loss of power conditions. Performed in section 7.5 2.11 The ability of the automatic position control to accept programming instructions and automatically position the manipulator crane to instructed locations is verified.
4 Performed in section 7.11 2.12 The T.V. mast and camera are demonstrated operable and its ability to view and record objects is verified.
i Performed in section 7.12 i
2.13 The bridge and trolley indexing will demonstrate that when positioned the manipulator crane will remove and insert a fuel assembly from selected locations,
,i i-
3.0 REFERENCES
3.1 Drawings 3.1.1 Flow Diagrams None 3.1.2 I & C Diagrams a
None 4
j 3.1.3 Elementary Diagrams j
None 3.1.4 One-Line Diagrams i
2323-El-0008 Rev. 8 2323-El-0165 Rev. 5 l
3.1.5 Vendor Diagrams l
None l
3.2 Vendor Manuals 3.2.1 Refueling Machine Technical Manual CP-0001-072 i
l 3.2.2 Underwater T.V. System Tech. Manual CP-0001-068 1
3.2.3 Westinghouse Reference Operating Instructions F-/.12 e
I For Information Only i
.s i
i-
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1 1CP-PT-60-03 Revision 0 Page 5 of 47 04-5-83 3.3 Documents 3.3.1 Final Safety Analysis Report 3.3.1.1 Chapter 9 Section 9.1.4 3.3.1.2 Chapter 14. Section 14.2-2 Sheet 54 of 60 3.3.2 Station Refueling Manual procedure #RFO-302
" Handling of Fuel Assemblies During Refueling Operations".
4.0 Test Equipment 4.1 Test loads of 3,750, +30
-0 pounds. (Calibration not necessary) 4.2 Test load rigging equipment 4.3 Dummy fuel assembly 4.4 Inline scale 0-4,000 1 50 lbs Equipment I.D. No.
Calibration Due Date Fame /Date 4.5 Containment Spent Fuel Handling Tool 5.0 SPECIAL PRECAUTIONS 5.1 The procedures shall be supervised by an individual thoroughly familiar with the equipment, its referenced technical manuals, and refueling procedures.
5.2 The test area shall be roped off and well marked during the performance test.
5.3 When ever the dummy fuel assembly is being moved, the allowable range of assembly weight is 1 50 pounds of its normal weight due to drag.
6.0 PREREQUISITES l
6.1 The components contained within the boundarien of this test have been turned over from construction to TUCCO l
Startup in accordance with Startup Administrative Procedure CP-SAP-3.
Name/Date 6.2 The Master System Punchlist has been updated and authorization to perforn the test, as required by CP-SAP-21, has been granted.
Name/Date l
F or Inf orniettion C)nly
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ICP-PT-40-03 Revision 0 Page 6 of 47 04-5-83 6.3 The Temporary Modification Log, as required by Startup j
Administrative Procedure CP-SAP-13, and the Station Temporary Bypass Log, as required by Station Administrative Procedure STA-602, have been reviewed and found not to preclude conduct of this test.
Name/Date 6.4 All prerequisite tests required by Table I for mechanical and electrical components and annunciators have been verified complete.
Name/Date 6.5 The calibration and loop functional test of the instrumentation listed in Table II. has been verified complete.
Name/Date 6.6 The Manipulator crane initial conditions are established per Table III.
Name/Date 6.7 The Underwater T. V. System has been functionally checked in accordance with reference 3.
Name/Date 7.0 PROCEDURE 7.1 Main Hoist 125% Static Load Test.
7.1.1 Verify that prerequisite Step 6.6 is performed.
Name/Date I
7.1.2 Verify that the Load Test Fixture is in place.
Name/Date i
7.1.3 Traverse the manipulator crane to the test fixture location.
Name/Date 7.1.4 Lower the hoist and guide the gripper into the test fixture.
SU-QA Nace/Date VERIFICATION 7.1.5 Verify that the hoist stops when indicated mast l
POINT weight is 650 pounds and observe that the slack l
"7./.Jr' cable light is lit. Record the ZZ axis tape par U o.
reading I
Name/Date l
Name 7.1.6 Verify that the Bridge and Trolley Indexes properly line up the gripper to the test Data fixture.
l Name/Date l
7.1.7 Rotate the gripper control to engage and observe the " GRIPPER ENGAGED LIGHT" is lit.
Name/Date 7.1.8 Raise hoist and verify hoist stops at 2800 pounds on the Dillon Load Cell readout and observe the " OVERLOAD" light is lit.
Name/Date For information Only i
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ICP-PT-40-03 Revision 0 Page 7 of 47 04-5-83 7.1.9 Turn the hoist overload bypass switch (TS-1) in the console to on and observe the " HOIST INTERLOCKED BYPASSED" light is lit.
Name/Date CAUTION Approach the mechanical load limit switch at the slowest possible speed in the follow-ing step. Do not allow the hoist to exceed 3400 pounds as observed on the Dillon Load i
Cell in case of limit switch failure.
A~
7.1.10 Raise the hoist until upward motion is stopped by limit switch LS-16.
Name/Date 7.1.11 Verify that the Dillon I.osd Cell readout is at 3200, +200, -0 pounds.
Name/Date 7.1.12 Observe weight constant and note no lowering of hoist.
Name/Date 7.1.13 Lcwer hoist until slack cable light lites and heist stops. Observe that the " OVERLOAD LIGHT" is extinguished.
Name/Date 7.1.14 Turn the hoist overload bypass switch (TS-1) in the console to 0FF and observe the " HOIST INTERLOCK BYPASSED" light is extinguished.
Name/Date 7.1.15 Slowly raise the hoist until the Dillon weight indicator reads greater than 1200 pounds.
Name/Date 7.1.16 Turn the gripper control to disengage and verify the gripper does not operate.
Name/Date 7.1.17 Turn the gripper control to engage, turn the SU43A gripper interlock bypass (LS-8) to on and VERIFICATION observe the " GRIPPER INTERLOCKS BYPASSED" light POjplT is lit.
"7. / / 7 Para. No.
7.1.17.1 Gripper to engage.
Name/Date NImi 7.1.17.2 LS-8 to on.
Name/Date pate 7.1.17.3
" GRIPPER INTERLOCK BYPASSED" lit.
Name/Date 7.1.18 Turn the gripper control to disengage. Verify gripper attempts to operate but does not disengage, observe gripper engaged light goes out, gripper failure alarm sounds and " GRIPPER FAILURE AND ALARM RESET" light is flashing.
For Information Only
ICP-PT-40-03 Revision 0 Page 8 of 47 04-5-63 7.1.18.1 Gripper to Disengage.
Name/Date 7.1.18.2 Gripper attempts to operate but dces not disengage.
Name/Date 7.1.18.3 gripper engaged off.
Name/Date 7.1.18.4 Alarm sounds.
Name/Date 7.1.18.5 Gripper Failure lights.
Name/Date 7.1.19 Silence the alarm by depressing the " Gripper Failure and Alarm Reset" light and observe
" Gripper Failure and Alarm Reset" light continues to flash.
7.1.19.1 Alarm off.
Name/Date 7.1.19.2 Light flashing.
Name/Date 7.1.20 Lower hoist until slack cable lites and hoist secps.
Name/Date 7.1.21 Turn the gripper control to disengage and observe the " GRIPPER DISENGAGED" light is lit.
Name/Date 7.1.22 Raise the hoist to the gripper up disengaged position and observe the " GRIPPER UP DISENGAGED" light is on.
Record ZZ Axis tape Name/Date 7.1.23 Return the manipulator crane to the fuel storage area.
Name/Date 7.2 Trolley and Bridge Checks not over the Reactor Vessel 7.2.1 Verify that prerequisite step 6.6 is performed.
Name/Date CAUTION Steps that position the bridge and trolley against the bumper stops or could permit contact of the refueling cavity walls l
by the manipulator crane mast l
shall be performed exercising due care. Approach limits of travel slowly.
l l
7.2.2 Traverse the bridge right and verify that with the bumper stops compressed the mast does not contact the refueling cavity wall.
Name/Date For Information Only 1-
1CP-PT-40-03 Revision 0 Page 9 of 4/
04-5-83 7.2.3 Traverse the trolley forward and verify that with the bumper stops compressed the mast does not contact the refueling cavity wall.
Name/Date 7.2.4 Traverse the trolley reverse and verify that with the bumper stops compressed the mast does not contact the refueling cavity wall.
Name/Date 7.2.5 Traverse the bridge left and verify that LS-12 stops the bridge and observe the mast does not contact the refueling cavity wall.
Name/Date 7.2.6 Traverse the trolley forward to the fuel transfer system centerline.
Name/Date 7.2.7 Traverse the bridge left over the lower internals storage stand.
Name/Date 7.2.6 Attempt to traverse the trolley in both directions and verify no trolley movement.
7.2.8.1 No Forward motion.
Name/Date 7.2.8.2 No Reverse motion.
Name/Date 7.2.9' Turn the trolley interlock bypass switch (TS-5) to on and observe that the " TROLLEY INTERLOCK BYPASSED" light is lit.
Name/Date 7.2.10 Traverse the trolley in both directions and verify the trolley traverses off the fuel transfer system centerline.
7.2.10.1 Forward motion.
Name/Date 7.2.10.2 Reverse motion.
Name/Date 7.2.11 Traverse the trolley forward to the Fuel transfer system centerline.
Name/Date 7.2.12 Traverse the bridge right to the test fixture transfer area.
Name/Date 7.2.13 Traverse the trolley reverse to the test fixture position.
Name/Date 7.2.14 Traverse the bridge in both directions and verify the bridge operates only in the test fixture area.
7.2.14.1 Left.
Name/Date 7.2.14.2 Right.
Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 10 of 47 04-5-83 7.2.15 Turn the bridge right bypass (TS-4) to on and observe the " BRIDGE INTERLOCKS BYPASS" light is lit.
Name/Date 7.2.16 Traverse the bridge right past the test fixture and verify bridge operates right only.
Name/Date 7.2.17 Turn the bridge right bypass (TS-4) to of f, turn the bridge left bypass to on and observe that the " Bridge Interlocks Bypassed" light extinguishes and then lights.
7.2.17.1 TS-4 off.
Name/Date 7.2.17.2 TS-3 on.
Name/Date 7.2.18 Traverse the bridge left past the test fixture and verify bridge operates Left only.
Name/Date 7.2.19 Return the Manipulator Crane to a position over the containment fuel storage area.
7.2.19.1 Turn bridge right bypass (TS-4) to on.
Name/Date 7.2.19.2 Traverse bridge right to test fixture area.
Name/Date 7.2.19.3 Traverse trolley to the fuel transfer system centerline.
Name/Date 7.2.19.4 Traverse bridge right over the containment fuel storage area.
Name/Date 7.2.19.5 Turn bridge right bypass (TS-4) to off.
Name/Date 7.2.19.6 Turn bridge left bypass (TS-3) to off.
Name/Date 7.3 Bridge, Trolley, Hoist Interlock Check 7.3.1 Verify prerequisite step 6.6 is performed.
Name/Date 7.3.2 Lower the hoist until the Gripper Up Disengaged light goes out.
Name/Date 7.3.3 Attempt to traverse the bridge and trolley both directions and verify no movement.
7.3.3.1 No Bridge Left movement.
Name/Date 7.3.3.2 No Bridge Right movement.
Name/Date 7.3.3.3 No Trolley Forward movement.
_ Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 11 of 47 04-5-63 7.3.3.4 No Trolley Reverse movement.
Name/Date 7.3.4 Turn trolley interlock bypass (TS-5) to on and verify trolley operation in both directions.
7.3.4.1 TS-5 on.
Name/Date 7.3.4.2 Trolley forward motion.
Name/Date 7.3.4.3 Trolley Reverse motion.
Name/Date 7.3.5 Turn trolley interlock bypass (TS-5) to off and turn bridge left interlock bypass (TS-3) to on and verify bridge operates left only.
7.3.5.1 TS-5 off.
Name/Date 7.3.5.2 TS-3 on.
Name/Date 7.3.5.3 Bridge Left only.
Name/Date SU-QA 7.3.6 Turn bridge left interlock bypass (TS-3) to off VERIFICATION and turn bridge right interlock bypass (TS-4) to POINT on and verify bridge operates right only.
'7 j?. d Pari,74o.
7.3.6.1 TS-3 off.
~
Name/Date N sG 7.3.6.2 TS-4 on.
Name/Date olEi~
7.3.6.3 Bridge right only.
Name/Date 7.3.7 Turn bridge right interlock bypass (TS-4) to off, Cripper up disengaged bypass (TS-6) to on and raise the hoist to its upper limit observing
" GRIPPER TUBE UP" light is lit and verify the hoist stops.
7.3.7.1 TS-4 off.
Name/Date 7.3.7.2 TS-6 on.
Name/Date l
7.3.7.3 Hoist stops.
I Name/Date 7.4 Bridge and trolley index checks and hoist control checks not over the Reactor Vessel.
7.4.1 Verify that prerequisite step 6.6 is performed and a BPRA insert rack is installed in
(
Containment Fuel Sterage rack A-6.
7.4.1.1 Prerequisite Step 6.6 perforced.
Name/Date 7.4.1.2 BPRA Insert Rack in A-6.
t
.Name/Date For Information Only I
f-
ICP-PT-40-03 Revision 0 Page 12 of 47 04-5-83 7.4.2 Using the bridge and trolley controls position the nanipulator crane over the containment fuel rack A-6 index marks.
Name/Date 7.4.3 Lower the hoist slowly observing the gripper assem'ily enter the BPRA Insert rack.
Name/Date 7.4.4 Verify hoist stops at 650 pounds and observe the slaci cable light lit.
Record ZZ axis tape Name/Date 7.4.5 Turn the gripper control to engage, verify the gripper engages and observe the gripper engaged light is lit.
Name/Date 7.4.6 Slowly raise the hoist until BPRA insert rack is just above the top of the Containment fuel racks.
Name/Date 7.4.7 Adjust the tare adjust until the dillion weight indicator reads greater than 1200 pounds.
Name/Date 7.4.8 Turn the gripper control to disengage and verify the gripper does not operate.
Name/Date 7.4.9 Turn the gripper control to engage, turn the gripper interlock bypass (LS-8) to on and observe the " GRIPPER INTERLOCKS BYPASSED" light is lit.
7.4.9.1 Gripper to engage.
Name/Date 7.4.9.2 LS-8 to on.
Name/Date 7.4.9.3 " GRIPPER INTERLOCK BYPASSED" lit.
Name/Date 7.4.10 Turn the gripper control to disengage. Verify gripper attempts to operate but does not disengage, observe gripper engaged light goes out, gripper failure alarm sounds and " GRIPPER FAILUPE AND ALARM RESET" light is flashing.
7.4.10.1 Gripper to Disengage.
Name/Date 7.4.10.2 Gripper attempts to operate but does not disengage.
Name/Date 7.4.10.3 gripper engaged off Name/Date 7.4.10.4 Alarm sounds.
Name/Date 7.4.10.5 Gripper Failure lights.
Name/Date l
l For Information Only l
ICP-PT-40-03 Revision 0 Page 13 of 47 04-5-83 7.4.11 Silence the alarm by depressing the " Gripper Failure and Alarm Reset" light and observe
" Gripper Failure and Alarm Reset" light continues to flash.
7.4.11.1 Alarm off.
Name/Date 7.4.11.2 Light flashing.
Name/Date 7.4.12 Attempt to operate the hoist in both directions with both controls and verify hoist does not operate.
J 7.4.12.1 Hoist up.
Name/Date 7.4.12.2 Hoist down.
Name/Date 7.4.12.3 Pushbutton up.
Name/Date 7.4.12.4 Push'outton down.
Name/Date 7.4.13 Attempt to operate the bridge and trolley in both directions and verify bridge and trolley do not operate.
7.4.13.1 No Bridge right motion.
Name/Date 7.4.13.2 No Bridge left motion.
Name/Date 7.4.13.3 No Trolley forward motion.
Name/Date 7.4.13.4 No Trolley reverse motion.
Name/Date 7.4.14 Turn gripper control to engage and verify gripper returns to the full engaged position.
Observe that Gripper engaged light is lit.
I Gripper Failure and Alarm Reset light is out.
7.4.14.1 Gripper to engage.
Name/Date 7.4.14.2 Gripper engaged light on.
Name/Date l
7.4.14.3 Gripper Failure light out.
Name/Date 7.4.15 Turn the gripper interlock bypass (LS-8) to of f and observe " Gripper Interlocis Bypassed" light is out.
7.4.15.1 LS-8 to off.
Name/Date 7.4.15.2 Bypass light out.
Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 14 of 47 04-5-83 7.4.16 Slowly lower the hoist over Containment fuel rack location A-6 and observe slack cable light is lit.
Name/Date 7.4.17 Disengage gripper.
Name/Date 7.4.18 Raise hoist to the G.U.D position.
Name/Date 7.4.19 Reposition the manipulator Crane using the bridge and trolley controls over Containment fuel racks location A-1.
Name/Date 7.4.20 Lower the hoist slowly observing the gripper enter the dummy fuel assembly top nozzle.
Name/Date 7.4.21 Verify hoist stops at 650 pounds and observe slack cable light lit. Record ZZ axis tape reading Name/Date 7.4.22 Turn the gripper control to engage, verify the gripper engages and observe the gripper engaged light is lit.
Name/Date 7.4.23 Raise the hoist until stopped by the limit switch (LS-3). Observe that " Gripper Tube Up" light is on.
Record ZZ axis tape Name/Date 7.4.24 Place a jumper across limit switch LS-3 between wires 220 and 221.
Name/Date 7.4.25 Raise the hoist until limit switch (LS-4) stops upward travel.
Name/Date 7.4.26 Lower hoist until limit switch (LS-3) closes and remove jumper placed across LS-3 between wire 220 and 221.
Name/Date 7.4.27 Raise the hoist to the gripper tube up position.
Name/Date l
7.4.28 Manually un-trip LS-4 and attempt to traverse the bridge and trolley in both directions.
Verify bridge and trolley do not operate.
{
7.4.28.1 LS-4 untripped.
Name/Date 7.4.28.2 No bridge rfght motion.
Name/Date 7.4.28.3 No bridge left motion.
Name/Date 7.4.28.4 No trolley forward motion.
Name/Date 7.4.28.5 No trolley reverse motion.
_Name/Date l
For Information Only l
l
- ~..
E i*
4 1CP-PT-40-03 Revision 0 Page 15 of 47 04-5-83 7.4.29 Place LS-4 in the tripped position and manually l
actuate LS-13.
Attempt to traverse the bridge i
and trolley in both directions. Verify bridge and trolley do not operate.
7.4.29.1 LS-4 tripped.
Name/Date j
7.4.29.2 LS-13 actuated.
Name/Date jl 7.4.29.3 No bridge right motion.
Name/Date 7.4.29.4 No bridge left motien.
i Name/Date 7.4.29.5 No trolley forward motion.
Name/Date 7.4.29.6 No trolley reverse motion.
Name/Date 7.4.30 Release LS-13 manually.
Name/Date 7.4.31 Position the Manipulator Crane over the centainment fuel storage location A-1 and insert the dummy fuel assembly.
Name/Date 7.4.32 Disengage the gripper and raise the hoist to the
, gripper up disengaged (GUD) position.
7.4.32.1 Gripper disengaged.
Name/Date i
7.4.32.2 G. U. D.
Name/Date 7.5 Loss of Power Performance Test i
7.5.1 Verify that prereaufsite 6.6 is performed.
Name/Date
,7.5.2 Open breaker ICB on the Manipulator Crane MCC.
Name/Date l
7.5.3 Attach the handwheels to the following motors.
l 7.5.3.1 Bridge drive Name/Date lj 7.5.3.2 Trolley drive.
Name/Date 7.5.3.3 Hoist drive.
Name/Date 7.5.4 Manually release the bridge and trolley drive i
motor brakes.
7.5.4.1 Bridge brakes released.
Name/Date 7.5.4.2 Trolley brakes released.
Name/Date i
s l
For Information Only I
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l 1CP-PT-40-03 Revision 0 1
Page 16 of 47 04-5-83 l
7.5.5 Manually operate the bridge and trolley drives in both directions and verify freedom of motion.
7.5.5.1 Bridge left.
1 Name/Date 7.5.5.2 Bridge right.
Name/Date 7.5.5.3 Trolley forward.
Name/Date 7.5.5.4 Trolley reverse.
Name/Date 7.5.6 Engage the bridge and trolley brakes and release the hoist brake.
7.5.6.1 Bridge brakes on.
Name/Date 7.5.6.2 Trolley brakes on.
i Name/Date 7.5.6.3 Hoist brakes released.
Name/Date 7.5.7 Manually operate the hoist in both directions and verify freedom of motion.
Name/Date 7.5.7.1 Hoist down freely.
Name/Date 7.5.7.2 Hoist up freely.
Name/Date 7.5.8 Engage the hoist brake and remove the handwheel from the bridge, trolley and hoist motors.
7.5.8.1 Hoist brake on.
Name/Date 7.5.8.2 Bridge handwheel removed.
Name/Date 7.5.8.3 Trolley handwheel removed.
Name/Date f
7.5.8.4 Hoist handwheel removed.
Name/Date 7.6 Auxiliary Hoist 125% Static Load Test 7.6.1 Verify that prerequisite step 6.6 is performed.
Name/Date 7.6.2 Verify that the floor of the refueling cavity where the test weight is to be placed is covered.
Name/Date 7.6.3 Using the polar crane, place the 3750 pound test weight into the refueling cavity.
Name/Date
[
7.6.4 Position the Manipulator Crane auxiliary hoist over the test weight and install the inline L
scale and rigging en the hoist.
7.6.4.1 Over weight.
_ Name/Date For Information Only w---
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ICP-PT-40-03 Revision 0 Page 17 of 47 04-5-83 7.6.4.2 Scale installed.
Name/Date 7.6.4.3 Ri ging installed.
F SU42A Name/Date VERIFICATION 7.6.5 Attach the rigging to the test weight.
POINT Name/Date 7.6.6 Slowly raise the auxiliary hoist and verify the fjf*,f load limit stops the hoist at 3300 ! 20 pounds.
Name/Date 7.6.7 Place a jumper across the contacts of the load limit switch.
g, Name/Date 7.6.8 Slowly raise the auxiliary hoist until the test weight is approximately one foot off the refueling cavity floor.
Name/Date 7.6.9 Observe weight constant and verify no slippage has occurred.
Name/Date 7.6.10 Lower the test weight until the rigging slackens and disconnect from the test weight.
7.6.10.1 Rigging slack.
Name/Date 7.6.10.2 Rigging disconnected.
Name/Date 7.7 Bridge, Trolley and Hoist Checks over the Reactor Vessel 7.7.1 Verify that prerequisite step 6.6 is performed for checks over the Reactor Vessel.
7.7.1.1 Verify Reactor vessel head removed and upper internals are removed.
Name/Date 7.7.1.2 Prerequisite step 6.6 performed.
Name/Date 7.7.2 Traverse the Manipulator Crane to containment fuel storage location A-1.
Name/Date
~
Lower the hoist and guide the gripper into the 7.7.3 dummy fuel ast,embly top nozzle.
Name/Date 7.7.4 Observe hoist stops at approximately 650 pounds, slack cable lights and engage the gripper.
7.7.4.1 Cripper engaged.
Name/Date 7.7.5 Raise hoist to the Gripper tube up position.
Name/Date 7.7.6 Traverse the Manipulator Crane over the Reactor Vessel to location H-8.
Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 18 of 47 04-5-83 7.7.7 With hoist control lower gripper tube until hoist stops and observe upper slow zone light is lit.
Record ZZ axis tape Name/Date 7.7.8 Lower hoist through upper slow zone using pushbutton control until upper slow zone light goes out.
Record ZZ axis tape Name/Date 7.7.9 Lower gripper tube with hoist control switch until hoist stops and observe lower slow zone light is lit.
Record ZZ axis tape Name/Date 7.7.10 Depress down pushbutton to lower the dummy fuel assembly to the full down position. Verify hoist stops at 650 pounds and observe the slack cable and tube down lights are lit.
Record ZZ axis tape Name/Date 7.7.11 Attempt to raise the gripper tube with the hoist control switch and verify hoist does not operate. _
Name/Date 7.7.12 Using up pushbutton raise dummy fuel assembly until lower slow zone light goes out.
Namc/Date 7.7.13 Raise the gripper to the gripper up disengaged position (ZZ axis) recorded in 7.1.16.
Name/Da.b'~
7.7.14 Attempt to drive bridge and trolley in both directions. Verify bridge and trolley do not operate and observe gripper up disengaged light is not on.
7.7.14.1 No Bridge right.
Name/Date 7.7.14.2 No Bridge left.
Name/Date 7.7.14.3 No Trolley forward.
Name/Date 7.7.14.4 No Trolley reverse.
Name/Date 7.7.15 Raise gripper tube until upper slow zone light goes out.
Name/Date 7.7.16 Raise gripper to full up position.
Name/Date 7.7.17 Manually engage LS-1 (Fuel Gripper Disengaged) limic switch.
Name/Date 7.7.18 Verify gripper failure alarm sounds and observe gripper disengaged light is lit and gripper failure indicating light is flashing.
Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 19 of 47 04-5-83 7.7.19 Silence alarm and release LS-1.
Observe gripper failure alarm indicating light goes out.
Name/Date 7.7.20 Slowly lower hoist approximately 10 feet.
While lowering, verify bridge and trolley do not operate in either direction and hoist continues to lower.
7.7.20.1 No Bridge left.
Name/Date 7.7.20.2 No Bridge right.
Name/Date 7.7.20.3 No Trolley forward.
Name/Date 7.7.20.4 No Trolley reverse.
Name/Date 7.7.20.5 Hoist lowering.
Name/Date 7.7.21 Slowly raise hoist to the full up position.
While raising, verify bridge and trolley do not operate in either direction and hoist continues raising.
7.7.21.1 No Bridge left.
Name/Date 7.7.21.2 No Bridge right.
Name/Date 7.7.21.3 No Trolley forward.
Name/Date 7.7.21.4 No Trolley reverse.
NamelDate 7.7.21.5 Hoist raising.
Name/Date 7.7.22 Lower hoist using pushbutton approximately 10 feet. While lowering verify bridge and trolley do not operate in either direction and hoist only lovers in slow speed.
7.7.22.1 No Bridge left.
Name/Date
{
7.7.22.2 No Bridge right.
Name/Date 7.7.22.3 No Trolley forward.
Name/Date 7.7.22.4 No Trolley reverse.
Name/Date 7.7.22.5 No Hoist Raise.
Name/Date 7.7.22.6 No Hoist Lower.
l Name/Date 7.7.22.7 Slow lower.
t Name/Date l
For information Only t
1
ICP-PT-40-03 Revision 0 Page 20 of 47 04-5-83 7.7.23 Raise hoist using pushbutton to the full up position. While raising verify bridge and trolley do not operate and hoist only raises in slow speed.
7.7.23.1 No Bridge left.
Name/Date 7.7.23.2 No Bridge right.
Name/Date 7.7.23.3 No Trolley forward.
Name/Date 7.7.23.4 No Trolley reverse.
Name/Date 7.7.23.5 No Hoist lower.
Name/Date 7.7.23.6 No Hoist raise.
Name/Date 7.7.23.7 Up in slow.
Name/Date 7.7.24 Unlock the mast and rotate the mast through its full range of travel (approx. 300*).
Name/Date 7.7.25 Return mast to its aligned position.
Name/Date 7.7.26 Return the dummy fuel assembly to containment fuel storage location A-1.
Name/Date 7.8 Bridge, Trolley and Hoist Mutual Interlocks Check 7.8.1 Verify that prerequisite step 6.6 is performed for checks over the Reactor Vessel.
7.8.1.1 Verify Reactor vessel head removed and upper internals are removed.
Name/Date 7.8.1.2 Prerequisite step 6.6 performed.
Name/Date 7.8.2 Engage gripper.
Name/Date 7.8.3 Place bridge and trolley bypasses (TS-3, TS-4 and TS-5) in the bypass position.
7.8.3.1 TS-3 bypass.
Name/Date 7.8.3.2 TS-4 bypass.
Name/Date 7.8.3.3 TS-5 bypass.
Name/Date 7.8.4 Traverse the Manipulator Crane over Reactor Vessel.
Name/Date 4
7.8.5 Lower gripper until tube up light goes out.
Name/Date
+
For Information Only f
ICP-PT-40-03 Revision 0 l
Page 21 of 47 04-5-83 7.8.6 Slowly trolley forward. While the trolley is moving forward verify that the bridge and hoist do not operate and trolley continues.
7.8.6.1 No Bridge left.
Name/Date 7.8.6.2 No Bridge right.
Name/Date 7.8.6.3 No Hoist up.
Name/Date 7.8.6.4 No Hoist lower.
Name/Date 7.8.6.5 No Pushbutton up.
Name/Date 7.8.6.6 No Pushbutton down.
Name/Date 7.8.6.7 Trolley forward continues.
Name/Date 7.8.7 Slowly trolley reverse. While the trolley is moving verify the bridge and hoist do not operate and trolley reverse centinues.
7.8.7.1 No Bridge left.
Name/Date
, 7.8.7.2 No Bridge right.
Name/Date 7.8.7.3 No Hoist raise.
Name/Date 7.8.7.4 No Hoist lower.
Name/Date 7.8.7.5 No Pushbutton up.
Name/Date 7.8.7.6 No Pushbutton down.
Name/Date 7.8.7.7 Trolley reverse continues.
Name/Date 7.8.8 Slowly bridge left. While the bridge is ncving verify the trolley and hoist do not operate and the bridge left continues.
7.8.8.1 No Trolley forward.
Name/Date 7.8.8.2 No Trolley reverse.
Name/Date 7.8.8.3 No Hoist raise.
Name/Date 7.8.8.4 No Hoist lower.
Name/Date 7.8.8.5 No Pushbutton up.
Name/Date i
7.8.8.6 No Pushbutton down.
Name/Date 7.8.8.7 Bridge left continues.
Name/Date For information Only 4
,n c.
,-,,n-,_
-n,
--,.,-_,-,,,r
ICP-PT-40-03 Revision 0 Page 23 of 47 04-5-83 7.9.5 Turn bridge left interlock bypass switch (TS-3) to bypass and observe bridge interlocks bypassed light is lit.
Name/Date 7.9.6 Verify that the bridge is now operable in the left direction.
Name/Date 7.9.7 Turn TS-3 to off.
Name/Date 7.9.8 Bridge right until LS-6 trips and verify bridge stops.
Name/Date 7.9.9 Turn bridge right interlock bypass switch (TS-4) to bypass and observe bridge interlock bypassed light is lit.
Name/Date 7.9.10 Verify bridge is now operable in the right direction.
Name/Date 7.9.11 Turn TS-4 to off.
Name/Date 7.9.12 Position bridge left of LS-6.
Name/Date 7.9.13 Bridge right until LS-6 trips.
Name/Date 7.9.14 Trolley forward.until LS-7 is on its cam, and trolley stops.
7.9.14.1 LS-7 on cam.
Name/Date 7.9.14.2 Trolley stops.
Name/Date 7.9.15 Verify that the bridge is operable in the "right" direction for 1 foot.
Name/Date 7.9.16 Verify that trolley will not operate.
7.9.16.1 No Trolley forward motion.
Name/Date 7.9.16.2 No Trolley reverse motion.
Name/Date 7.9.17 Bridge left until over the Reactor Vessel.
Name/Date 7.9.18 Trolley forward until LS-18 trips and verify trolley stops.
Name/Date 7.9.19 Turn trolley interlock (TS-5) to bypass, verify trolley operates forward and observe trolley interlocks bypassed light is lit.
Name/Date 7.9.20 Verify trolley operates in the forward direction.
Name/Date For Information Only
= - -. -
ICP-PT-40-03 Revision 0 Page 24 of 47 04-5-83 7.9.21 Trolley reverse until over Reactor Vessel and turn TS-5 to off.
4 7.9.21.1 Over vessel.
Name/Date 7.9.21.2 TS-5 off.
Name/Date 7.9.22 Trolley reverse until LS-14 trips and verify trolley stops.
Name/Date 7.9.23 Turn trolley interlocks (TS-5) to bypass and verify trolley operates reverse.
Name/Date 7.9.24 Trolley forward until over the Reactor Vessel and tirn TS-5 to off.
7.9.24.1
&cer vessel.
Name/Date 7.9.24.2 TS-5 off.
Name/Date 7.9.25 Return Manipulator Crane to a position over the containment fuel storage racks.
Name/Date 7.10 Auxiliary Hoist 100% Load Operations 7.10.1 Verify that prerequisite 6.6 is performed.
Name/Date 7.10.2 Using the Polar crane place the 3000 pound test weight in the refueling cavity.
Name/Date 7.10.3 Position the hoist over the test weight.
Name/Date 7.10.4 Attach the 3000 pound weight to the hoist hook.
Name/Date
-~~~
SU-QA 7.10.', Raise the hoist to its full up position.
VERIFICAYlON Name/Date l
POltfr 7.'.0.6 Verify full travel of the trolley to the stops in both directions.
f
- 1. /L o Para No.
7.10.6.1 east to west.
Name/Date N'**
7.10.6.2 west to east.
D***
Name/Date 7.10.7 Return the 3000 pound load to its starting position in the refueling cavity.
Name/Date 7.10.8 Disconnect the rigging from the hoist hook.
Name/Date 7.10.9 Remove the 3000 pound weight from the refueling
}
cavity using the polar crane.
I Name/Date
[
For Information Only i
i i
1CP-PT-40-03 Revision 0 Page 25 of 47 04-5-83 7.11 Automatic Positioning Full Performance Test.
7.11.1 Verify that prerequisite steps 6.6 is performed for checks over the Reactor Vessel.
7.11.1.1 Verify Reactor vessel head removed and upper internals are removed.
Name/Date 7.11.1.2 Prerequisite step 6.6 performed.
Name/Date 7.11.2 Raise the gripper to the full up position.
Name/Date 7.11.3 Turn the MODE selector switch on the automatic control panel to the MANUAL position.
Name/Date 7.11.4 Traverse the Manipulator Crane to the containment storage racks.
Name/Date 7.11.5 Align the mast over the durny fuel assembly using the manual and inching controls as required.
Name/Date 7.11.6 Lower the gripper to the dummy fuel assembly using the panel and pendant controls as required.
Name/Date 7.11.7 Verify that the slack cable light is lit.
Name/Date 7.11.8 Turn the gripper control to the engage position and observe the " GRIPPER ENGAGED" light is lit.
Name/Date 7.11.9 Raise the dummy fuel assembly until the limit switch stops upward travel.
Name/Date 7.11.10 Traverse the trolley to the fuel transfer system center line.
Name/Date 7.11.11 Traverse the manipulator crane along the fuel transfer system center line until the mast is lined up with the test fixture.
Name/Date 7.11.12 Align the mast over the test fixture using the manual and inching controls as required.
Name/Date 7.11.13 Turn the key operated switch on the rear panel to the RECORD position.
Name/Date 7.11.14 Verify that the RECORD light is illuminated.
Name/Date 7.11.15 Depress the CLEAR ENTRY switch.
Name/Date 7.11.16 Verify that the FAULT light is extinguished.
Name/Date For information Only
ICP-PT-40-03 Revision 0 Page 26 of 47 04-5-83 7.11.17 Turn the MODE selector switch to the HOME position.
Name/Date 7.11.18 Depress the TRANSFER AREA switch.
Name/Date 7.11.19 Verify that the TRANSFER AREA switch is illuminated.
Name/Date 7.11.20 Depress the "J" selector switch.
Name/Date 7.11.21 Depress the "8" selector switch.
Name/Date 7.11.22 Depress the STORE pushbutton switch.
Name/Date 7.11.23 Verify the following:
7.11.23.1 DESTINATION display reads J8.
Name/Date 7.11.23.2 ERIDGE display reads J.
Name/Date 7.11.23.3 TROLLEY display reads 8.
Name/Date 7.11.24 Turn the key switch to the RUN position.
Name/Date 7.11.25 Verify that the RECORD light is extinguished.
Name/Date 7.11.26 Set the core memory switches as listed on Table IV.
Name/Date 7.11.27 Verify that the WRITE / PROTECT switch, number 8 on the 214-029-3DA board, is in the closed position.
Name/Date 7.11.28 Turn the RUN/ RECORD switch to the RECORD position.
Name/Date 7.11.29 Verify that the following lights are extinguished:
7.11.29.1 FAULT.
Name/Date 7.11.29.2 SET HOME.
Name/Date 7.11.30 Turn the MODE selector switch to the MANUAL position.
Name/Date Note Refer to Figure 1 for programming locations.
7.11.31 Traverse the manipulator crane to the first core position listed on Data Sheet 2.
.Name/Date For Information Only
ICP-PT-40-03 Revision 0 Page 27 of 47 04-5-83 7.11.32 Lower the dummy fuel assembly to verify alignment to position.
Name/Date 7.11.33 Raise the dummy fuel assembly until stopped by the limit switch.
Name/Date 7.11.34 Verify that the "CRIPPER TUBE UP" light is lit.
Name/Date 7.11.35 Turn the MODE selector switch to the AUTO position.
Name/Date Note There is a 2 second delay before another keyboard entry is recognized.
7.11.36 Depress the area switch for the location being programmed (i.e. CORE, TRANSFER AREA).
Name/Date J
7.11.37 Depress t)- coordinate keys for the position
]
being programmed.
Name/Date 7.11.38 Depress the STORE key.
Name/Date 7.11.39 Verify that the PRESENT LOCATION and DESTINATION readouts both show the STORED location.
Name/Date i
7.11.40 Repeat Steps 7.11.28 to 7.11.38 for all locatiens listed on Data Sheet 2.
Name/Date i
7.11.41 Initial the appropriate space upon completion of each locations programming. Verify completion of programming here.
Name/Date Note A tabulated format of steps 7.11.28 to 7.11.38 is attached as Table V for ease of reference.
7.11.42 Turn the write protect switch No. 8 to the OPEN position.
Name/Date 7.11.43 Turn the RUN/ RECORD switch to the RUN position, Name/Date l
7.11.44 Verify that the RECORD light is extinguished.
Name/Date 7.11.45 Verify that the MODE selector switch is in the AUTO position.
Name/Date For Information Only
. = _.. -.
ICP-PT-40-03 Revision 0 Page 28 of 47 04-5-83 7.11.46 Verify that the following lights are extinguished:
7.11.46.1 FAULT.
Name/Date 7.11.46.2 SET HOME.
Name/Date 7.11.47 Press the CLEAR ENTRY key.
1 Name/Date 7.11.48 Depress the area key for the target location (i.e. CORE, TRANSFER AREA).
Name/Date 7.11.49 Enter the bridge target position coordinate.
Name/Date 7.11.50 Enter the trolley target position coordinate.
Name/Date 7.11.51 Verify that the DESTINATION readout is the same cs the coordinates entered.
Name/Date 7.11.52 Press the START key.
Name/Date 7.11.53 Verify that the Manipulator Crane traverses to the selected position.
Name/Date 7.11.54 Lower the dummy fuel assembly partly into the selected location.
Name/Date 7.11.55 Raise the dummy fuel assembly until stopped by the limit switch.
Name/Date 7.11.56 Verify that the " GRIPPER TUBE UP" light is lit.
Name/Date Note A tabulated format of steps 7.11.45 to 7.11.55 is attached as Table VI for ease of reference.
7.11.57' Repeat Steps 7.11.45 to 7.11.55 for all locations listed on Data Sheet 2.
Name/Date 7.11.58 Initial the appropriate space upon verification of each location. Verify completion of all positions here.
Name/Date 7.11.59 Turn the MODE selector switch to the MANUAL position.
Name/Date 7.11.60 Traverse the Manipulator Crane to the containment storage rack.
Name/Date For information Only
ICP-PT-40-03 Revision 0 Page 29 of 47 04-5-83 7.11.61 Using the panel and pendant controls as appropriate lower the dummy fuel assembly to its storage location.
Name/Date 7.11.62 Verify that the following light is lit:
7.11.62.1 SLACK CABLE.
Name/Date 7.11.63 Turn the gripper control switch to the disengage position and observe the "CRIPPER DISENGAGED" light is lit.
Name/Date 7.11.64 Raise the gripper until stopped by the limit switch.
Name/Date 7.11.75 Verify that the " GRIPPER UP DISENCAGED" light is lit.
Name/Date 7.12 T.V. Mast Full Performance Test.
7.12.1 Verify prerequisite 6.7 has been accomplished.
Name/Da' e 7.12.2 Verify that prerequisite steps 6.6 is performed for checks over the reactor vessel.
Name/Date 7.12.1.1 Verify Reactor vessel head removed and upper internals are removed.
Name/Date 7.12.1.2 Prerequisite step 6.6 perforned.
Name/Date j
7.12.3 Position the Manipulator Crane above the Reactor Vessel.
SU-QA I
Name/Date VERIFICATION 7.12.4 Verify full travel of the T.V. mast to the limit PCHNT switches in both directions until the rotary I
limit switch trips the mast motor.
37,j;7, 4 Para. ko.
l 7.12.4.1 Hoisting.
l Name Name/Date 7.12.4.2 Lowering.
cgpr --
Name/Date j
7.12.5 Rotate the camera in both directions. Verify j
the camera rotates approximately 360 degrees.
l Name/Date 7.12.6 Direct the camera's field of vision to include one of the reactor vessel guide studs.
Name/Date 7.12.7 Verify the camera lens will focus on the guide stud remotely.
Namc/Date i
7.12.8 Raise the camera and mast to its full up l
position.
Name/Date For Information Only
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TABLE I Mechanical / Electrical Prerequisite Test Verification ICP-PT-40-03 Revision 0 i
X - Denotes required for preop / accept test Pa w 31 of 47 h-Denotestestscompleteandrecord(s)onfile l
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t ICP-PT-40-03 Revision 0 Page 32 of 47 04-5-83 TABLE II INSTRUMENT CALIBRATION / LOOP TEST VERIFICATION System No.
PT-40-03 System
Title:
Refueling Machine Calibration and loop tests of the following instruments are complete and have at least 60 days remaining in their normal calibration interval.
Instrument /
Setpoint/
Initials /
Channel No.
Description Location Range Date Dillon Load Cell Load Cell and Control 0/-
Cell Readout Panel 6,000 Pressure Cauge Air Pressure Control 70 - 100 on gripper Panel psig Dillon load trip Load cell read-Control 2700 out Panel pounds Backup Overload Backup trip Outer 3200 trip Mast pounds Pressure Switches Controls pressure 70 psig &
on gripper 100 psig For Information Only
ICP-PT-40-03 Revision 0 Page 33 of 47 04-5-83 TABLE III Manipulator Crane Initial Conditions 1.
MCC IEB1-2 is energized.
2.
Breaker 6D in MCC IEB1-2 is closed.
3.
Manipulator Crane main disconnect switch is closed.
4 All 6 bypass switches are in "0FF" 5.
All circuit breakers on the Manipulator Crane MCC are closed.
6.
The automatic positioning unit control mode selector switch is in the
" MANUAL" position.
7.
The inching permissive key switch on the automatic positioning panel is in the "0FF" position.
8.
Push to test all indicating lights.
The following should be illuminated:
Grippe,r Disengaged (0 pal) a.
b.
Gripper Up Disengaged (Green)
The following should not be illuminated:
a.
Gripper Engaged (Green) b.
Gripper Failure and Alarm Reset (Red)
" Gripper Interlocks Bypassed (Red) c.
d.
Trolley Interlocks Bypassed (Red)-
e.
Gripper tube Down (Amber) f.
Bridge Interlocks Bypassed (Red) g.
Slack Cable (Blue) h.
Overload (Red) 1.
Overload Bypassed (Red) j.
Gripper tube Up (Green) k.
Hoist Interlocks Bypassed (Red)
For Information Only L
9 ICP-PT-40-03 Revision 0 Page 34 of 47 04-5-83 1.
Slow Zone #1 entering core (Amber) m.
Slow Zone #2 bottom of Core (Amber) n.
Overheat (Red) 9.
Air pres grc gage is reading between 70 and 100 psig.
- 10. All manual handwheel operators ar* removed from their motors.
11.
Brake release mechanisms are set for normal operations.
- 12. Dummy fuel assembly is available in the containment fuel storage rack locations A-1.
- 13. The Manipulator Crane is located over the containment fuel storage area.
14.
Support brackets for the lower internals lifting rig guide pins have been removed.
i 4
?
I
?
For Information Only r
ry--
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ICP-PT-40-03 Revision 0 Page 35 of 47 04-5-83 TABLE IV 8193 Auto Positioning Control Switch Settings Switch No.
Position 1
Closed 2
Open 3
Open 4
Open 5
Closed 6
Closed 7
Closed 8
Closed = Not Write Protected For Information Only
FT 1CP-PT-40-03 Revision 0 Page 36 of 47 04-5-83 TABLE V System No. PT-40-03 System Iitle: Refueling Machine AUTOMATIC SYSTDI PROGRAMMING Abbreviated Format for Procedure Steps 1.11.28 - 7.11.38 Step No.
Procedure 7.11.28.1 FAULT light out 7.11.28.2 SET HOME light out 7.11.29 Mode Switch = MANUAL 7.11.30 Advance mast to new position 7.11.31 Lower Fuel Assembly 7.11.32 Raise Fuel Assembly 7.11.33 GRIPPER TUBE UP light on 7.11.34 Mode Switch = AUTO 7.11.35 Area switch = CORE / TRANSFER AREA 7.11.36 Enter coordinates 7.11.37 Depress STORE key 7.11.38 Verify LOCATION and DESTINATION For Information Only
- e-4O#1M4 W*
1CP-PT-40-03 Revision 0 Page 37 of 47 04-5-83 TABLE VI System No. PT-40-03 System
Title:
Refueling Machine AUTOMATIC SYSTD1 OPERATION Abbreviated Format for Procedure Steps 7.11.45 - 7.11.55 Step No.
Procedure 7.11.45.1 FAULT light out 7.11.45.2 SET HOME light out 7.11.46 Press CLEAR ENTRY 7.11.47 Enter area = CORE / TRANSFER AREA 7.11.48 Enter bridge coordinate 7.11.49 Enter trolley coordinate 7.11.50 Verify DESTINATION 7.11.51 Press START 7.11.52 Verify traverse 7.11.53 Lower Fuel Assembly 7.11.54 Raise Fuel Assembly 7.11.55 Verify CRIPPER TUBE UP I
t I
I 4
5 1
For Information Only-
ICP-PT-40-03 Revision 0 Page 38 of 47 04-5-83 DATA SilEET 2 Page 1 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROCRAMMED NAME/DATE A 5 A 6 A 7 A 8 A 9 A 10 A 11 B 3 B 4 B 5 B 6 B 7 B 8 B 9 B 10 B 11 B 12 B 13 C 2 i~
C 3 C 4 C 5 C 6 C 7 C 8 For Information Only i
ICP-PT-40-03 Revision 0 Page 39 of.47 04-5-P3 DATA SEEET 2 Page 2 of 10 VERIFIED CORREC*
CORE LOCATION (X, Y Index)
PROGRAMMED NAME/DATE C 9 C 10 C 11 C 12 C 13 C 14 D 2 D 3 D 4
.D 5
D 6 D 7 D 8 D 9 D 10 D 11 D 12 D 13 D 14 E 1 E 2 E 3 E 4 E 5 E 6 For Information Only
ICP-PT-40-03 Revision 0 Page 40 of 47 04-5-83 DATA SHEET 2 Page 3 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRAMIED MAME/DATE E 7 E 8 E 9 E 10 E 11 E 12 E 13 E 14 E 15 F 1 F 2 F 3 F 4 1
F 5 F 6 F 7 F 8 F 9 F 10 F 11 F 12 F 13 F 14 F 15 l
c 1 l
l For information Only L.
ICP-PT-40-03 Revision 0 Page 41 of 47 04-5-83 DATA SHEET 2 Page 4 of 10 ZZ AXIS VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRAMMED TAPE NAME/DATE G 2 G 3 G 4 G 5 G 6 C 7 G 8 G 9 G 10 G 11 G 12 G 13 G 14 C 15 H 1 H 2 O
H 3 H 4 H 5 H 6 H 7 H 8 i
H 9 H 10 H 11 For Information Only
ICP-PT-40-03 Revision 0 Page 42 of 47 04-5-83 DATA SHEET 2 Page 5 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRAMMED NAME/DATE H 12 H 13 H 14 H 15 J 1 J 2 J 3 J 4 3 5 3 6 3 7 J 8 J 9 J 10 J 11 J 12 J 13 J 14 J 15 K 1 K 2 K 3 K 4 K 5 K 6 For information Only
ICP-PT-40-03 Revision 0 Page 43 of 47 04-5-83 DATA SHEET 2 Page 6 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRAMMED NAME/DATE K 7 K 8 K 9 K 10 K 11 K 12 K 13 K 14 K 15 L 1 L 2 L 3 L 4 L 5 L 6 L 7 L 8 I.
9 L 10 L 11 L 12 L 13 L 14 L 15 M 2 For Information Only
ICP-PT-40-03 Revision 0 Page 44 of 47 04-5-83 DATA SHEET 2 Page 7 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRAMMED NAME/DATE M 3 M 4 M 5 M 6 M 7 j
M 8 M 9 M 10 M 11 i
M 12 M 13 M 14 N 2 5
N 3 N 4 N 5 N 6 N 7 N 8 N 9 1
N 10 N 11 N 12 N 13 N 14 For Information Only t
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ICP-PT-40-03 Revision 0 Page 45 of 47 04-5-63 DATA SHEET 2 Page 8 of 10 VERIFIED CORRECT CORE LOCATION (X, Y Index)
PROGRA}DfED NAME/DATE P 3 P 4 P 5 P 6 P 7 P 8 P 9 P 10 P 11 P 12
~
P 13 R 5 R6 R 7 R
8, R 9 R 10 R 11 For information Only
..o ICP-PT-40-03 Revision 0 Page 46 of 47 04-5-83 DATA SilEET 2 Page 9 of 10 VERIFIED CORRECT CANAL LOCATION (X, Y Index)
PROGRAMMED ZZ AXIS NAME/DATE TAPE A 1 A 2 A 3 A.4 A 5 B 1 B 2 B 3 B 4 3 5 C 1 C 2 C 3 C 4 C 5 D 1 D 2 D 3 D 4 D 5 E 1 i
E 2
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E 3 E 4 l
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For information Only 1
I l.
t-
.e ICP-PT-40-03 Revision 0 Page 47 of 47 04-5-83 DATA SHEET 2 1
Page 10 of 10 VERIFIED CORRECT CANAL LOCATION (X, Y Index)
PROGRAMMED NAME/DATE F 6 G7 H -7 J 8 (Test fixture) i 4
i i
I For Information Only
1CP-PT-40-03 Revision 0 Page 22 of 47 04-5-83 7.8.9 Slowly bridge right. While the bridge is moving verify the trolley and hoist mo not operate and the bridge right continues.
7.8.9.1 No Trolley forward.
Name/Date 7.8.9.2 No Trolley reverse.
Name/Date 7.8.9.3 No Hoist raise.
Name/Date~~
7.8.9.4 No Hoist lower.
Name/Date 7.8.9.5 No Pushbutton up.
Name/Date 7.8.9.6 No Pushbutton down.
Name/Date 7.8.9.7 Bridge right continues.
Same/Date 7.8.10 Return Manipulator Crane to a location over the containment fuel storage racks.
Name/Date 7.8.11 Place bridge and trolley bypasses (TS-3, TS-4 and TS-5) in the off position.
7.8.11.1 TS-3 of f Name/Date 7.8.11.2 TS-4 off Name/Date 7.8.11.3 TS-5 off Name/Date 7.8.12 Disengage gripper and return mast to the Gripper Up disengaged position.
Name/Date 7.9 Stud Limit and Transfer System Interlock Checks 7.9.1 Verify the prerequisite step 6.6 is performed for checks over the Reactor Vessel.
7.9.1.1 Verify Reactor vessel head removed and upper internals are removed.
Name/Date 7.9.1.2 Prerequisite step 6.6 performed.
Name/Date 7.9.2 Position the Manipulator Crane over the Reactor Vessel.
Name/Date 7.9.3 Trolley reverse off the transfer system centerline.
Name/Date 7.9.4 Bridge left until LS-11 trips and verify bridge stops.
Name/Date For Information Only
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l' h O REColeENDED ACTION: ATTEMP TO STRAIGHTEN T/C COLEM(i USING SUITABLE STRONG BACK E
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Dockets: 50-445/84-08 i
TN,.gr you$.b.bcQM 506 446/84-44 o r.
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Texas Utilities Electric Company Q$.,,Y,M ATTM:
M. D. Spence President TUGC0 Skyway Tower 400 North Olive Street Lock Box 81 Dallas. Texas 75201 Gentlemen:
This mfers to the inspection conducted under the Resident Inspection Progres by Messrs. J. E. Cummins, W. F. Smith, L. E. Martin and C. R. Serg i
of this offica during the period Neves6er 14,1983, through March 31, 1984, of activities authorized by NRC Construction Pemits CPPR-126 and CPPR-127 of t
the Cananche Peak facility, Units 1 and 2, and to the discussion of our j
findings with Mr. J. T. Merritt, and other meebers of your staff at the i
conclusion of the inspection.
Areas exanined durir.g the inspectimi included licensee action on previous findings,10 CFR Part 50.55(e) report followup,10 CFR Part 21 report follow-up, allegation followup (Unit 1), independent inspection of coatings, train-ing of protective coatings inspectors, review of safety-related systems (Unit 1), inventory of audit material in custody of NRC, and plant tours.
Within these areas, the inspection consisted of selective examination of pro.
cedures and mpr:sentative records, interviews with personnel, and observa-tions by the inspectors.
The inspection findings are docunented in the enclosed inspection mport.
Ouring this inspection, it was found that certain of your activities were in Violation of NRC requirements. Consequently, you are required to mspond to this violation in writing, in accortlance with the provisions of Section 2.201 l
of the NRC's " Rules of Practim," Part 2, Title 10 Code of Federal Regula-tions. Your response should be based on the specifics contained in the Notice of Violation enclosed with this letter.
.u ng t,is,ns-ti.
,t s,- t,at ce,ta,n o,,_ activit,esF0lA-85-5!
appeared to deviate from a commitment made to the NRC. This item and jf7[
i reference to the comitment are identified in the enclosed Notice of l
Deviation. You are requested to respond to this deviation in writing.
Your response should be based on the specifics contained in the N. ice of Deviation enclosed with this 1 ter.
ORS &Pg TF-iF-RW TF $
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In Reply Refer To:
Dockets: 50-445/84-08
?.'% p,>or,%'<.:,sff?>
I 50-446/84-04
\\M'l.5:.' Yl}
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WG${.g,d\\O Texas Utilities Electric Company
"'vg*h b%D ATTN:
M. D. Spence, President. TUGC0 Skyway Tower M-400 North Olive Street Lock Box 81 Dallas Texas 75201 Gentlemen:
j This refers to the inspection conducted under the Resident Inspection Progree by Messrs. J. E. Camusins, W. F. Smith, L. E. Martin and C. R. merg of this offica during the peMod Noves6er 14,1983, through March 31, 1984, of activities authorized by NRC Construction Pemits CPPR-126 and CPPR-127 of l
the Cananche Peak facility, Units 1 and 2. and to the discussion of our findings with Mr. J. T. Marvitt, and other mem6ers of your staff at the conclusion of the inspection.
Areas examined during the inspection included licensee action on previous findings,10 CFR Part 50.55(e) mport follomup,10 CFR Part 21 report follow-up, allegation follomup (thit 1), independent inspection of coatings, train-ing of protective coatings inspectors, myiew of safety-related systems 4
(Unit 1), inventory of audit matedal in custody of NRC, and plant tours.
Within these amas, the inspection consisted of selective examination of pro-cedures and mpresentative records, interviews with personnel, and observa-tions by the inspectors.
The inspection findings art documented in the enclosed inspection report.
l During this inspection, it was found that certain of your activities wem in violation of NRC requirements. Consequently, you are mquired to respond to this violation in wHting, in accordance with the provisions of Section 2.201 I
of the NRC's " Rules of Practice," Part 2, Title 10. Code of Federal Regula-tio' ns. Your response should be based on the specifics contained in the Notice of Violation enciased with this letter.
During this inspection, it was found that certain of your activities appeared to deviate free a coneitment made to the NRC. This item and I
reference to the comitment are identified in the enclosed Notice of Deviation. You are requested to respond to this deviation in writing.
l Your msponse should be based on the specifics contained in the N ice I
of Deviation enclosed with this 1 ter.
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OFFICIAL RECORD COPY ceOSt7GG4e
Texas Utilities Electric 2
Campany In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will be plamd in the NRC Public Docuunnt Room unless you notify this offica, by telephone, within 10 days of the data of this letter, and submit written application to withhold infonnation contained themin within 30 days of the date of this letter. Such application must be consistant with the mquimeents of 2.790(b)(1).
The msponses directed by this letter and the accompanying Notices am not suWect to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96511.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincemly.
Or18taal $1sted 378 F.ienard L. M i
Richard L. Bangart, Director Region IV Task Force
Enclosures:
i 1.
Appendix A Notice of Violation 2.
Appendix 8 Notice of Deviation 3.
Appendix C NRC Inspaction Report 50-445/84-08 50-446/84-04 cc w/ enc 1:
l Texas Utilities Electric Conpany' ATTN: H. C. Schmidt, Manager Nuclear Services Skyway Tower 400 North Olive Street Lock Box 81 Dallas. Texas 75201 Texas Utilities Electric Company ATTN:
B. R. Clements, Vice President, Nuclear Skyway Tower 400 North Olive Street Lock Box 81 Dallas Texas 75201
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- 5. Treby ELD D. Hunnicutt. TF F.IS SYS E M R. L. Bangart, Task Force TRT(2)B(CPSES)/
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APPENDIX A NOTICE OF VIOLATION Texas Utilities Electric Company Docket: 50-445/84-08 4
Comanche Peak Steam Electric Constructi.on Pemit: CPPR-126 l
Station (CPSES) Unit 1 Based on the msults of an NRC inspection conducted during the period of November 14, 1983, through March 31, 1984, and in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C), 49 FR 8583, dated March 8, 1984, the following violations were identified:
A.
Gaps on Unit 1 Polar Crane Bracket and Seismic Connections Exceed Desion Reouirements 10 CFR 50, Appendix B, Criterion y requires that, " activities affecting quality shall be prescribed by documented instructions,
+
procedures, or drawings, of a type appropriate to the circumstances i
and shall be accomplished in accordance with these instructions, procedures, or drawings."
Design change Authorization 9872 required that all gaps on the Unit 1 i
polar crane bracket and seismic connections greater than 1/16 inch be shimed.
Contrary to the above on February 13, 1984, the NRC inspector reviewed the polar crane bracket and seismic connections listed below and observed that there were unshimed gaps that exceeded 1/16 inch.
]
Connection location onGirder(.looking Approximate Girder Number from inside containment)
Gap 1
23 center 1/8" 23 right 1/8" 26 right 3/16" 20 center 5/32" 20 left 3/16" 19 right 3/16" 17 center 5/32" i
16 right 1/8" l
This is a Severity Level IV Violation (Supplement 11.0) (445/8408-01).
8.
Failure to Perform Inspections of Installation Activities Related to Unit 1. Main Coolant System Crossover Leg Restraints Criterion X of Appendix 8 to 10 CFR Part 50 requires that inspections
]
of activities affecting quality shall be established and executed by or for the organizations performing the activity to verify conformance with the documented instructions, procedures, and drawings for i
accomplishing the activity.
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2 Texas Utilities Electric Company Quality Assurance Plan, in Section 10.0, requires that planned written inspection procedures.be utilized. It further requires that inspection activities include the types of characteristics to be measured, the methods of examination, and the criteria.
Contrary to the above, it was determined that inspections were not made of the installations of the Unit 1 crossover leg restraints, nor were any documents requiring such an inspection iss :ed. Specifically, the require-ments for installation, as specified in Gibbs & Hill Drawing 2323-51-0550, were not inspected and documented. The eight crossover restraints (2 per loop) are major components of the main coolant piping seismic restraints and support system.
This is a Severity Level IV Violation. (SupplementII.0)(445/8408-02)
Pursuant to the provisions of 10 CFR 2.201, Texas Utilities Electric Company is hereby required to submit to this office, within 30 days of the date of corrective steps which have been taken and the results achieved;this Notice, a w 1 the (2
tive steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Consideration may be given to extend-ing your response time for good cause shown.
Dated: July 26, 1984 l
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RPS1 Resident Inspector-Oos RPS2 Resident Inspector-Cons TP5 J. E. Gagliardo, D/TF J. Collins, RA T. F. Westeman, EO C. Wisner, PA0 R. Denise, DRRP&EP S. Treby, ELD D. Hunnicutt, TF MIS SYSTEM R. L. Bangart, Task Force TRT(2)(CPSES)/
RIV File A d TEXAS STATE DEPT. OF HEALTH Juanita Ellis Renaa Hicks 31111e P. Garde l'
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APPENDIX B NOTICE OF DEVIATION Texas Utilities Electric Company
. Docket: 50-445/84-08 Comanche Peak Steam Electric Construction Pemit: CPPR-126 Station (CPSES) Unit 1 Based on the results of an NRC inspection conducted during the period of Ncvember 14, 1983, through March 31, 1984, and in accordance with the NRC enforce-ment Policy (10 CFR Part 2, Appendix C), 49 FR 8583, dated March 8,1984, the following deviation was identified:
Deviation from Design Infomation for Installation of Seismic Category I/
Seismic Category II Structural Steel for tne Bolted Connections Between the W16x40 and the Wall on Platfom OP-ll in the Pressurizer Compartment.
1.
CPSES FSAR Section IA(B), on page 1A(B)-26, states, "The quality assurance program for design and construction at CPSES incorporates the intended objectives of ANSI N45.2.11." (Draft 2. Revision 2 -
May 1973)
Contrary to the above, the licensee did not incorporate the intended objectives of ANSI N45.2.11 into the design of certain personnel access platfoms at CPSES. A review of the design documentation, including Gibbs and Hill Drawing 2323-S1-0556, Revision 4 Design Change Authorization (DCA) 9764, Revision 3, and DCA 1090, indicated that the above platform was originally designed as nonsafety-related.
2.
ANSI N45.2.11 (Oraft 2, Revision 2 - May 1973), paragraph 3, requires that design input requirements be specified to the level of detail i
necessary to pemit the design activity to be carried out in a correct manner and should include basic functions, loads, and physical interfaces. ANSI N45.2.11, paragraph 8, requires that design changes be subjected to design control measures coninensurate with the above.
Contrary to the above, the design documentation was upgraded to l
Seismic Category II with the particular beams supporting safety-related instrument tubing for two channels of pressurizer level upgraded to Seismic Category !.
DCA 1090 required that the bolted connections between the W16x40 and the wall be " hand tight only", but did not address any locking device or thread upset to prevent nut backoff.
l l
3.
AISC Manual for Steel Construction in the Specification for Design, Fabrication, and Erection of Structural Steel for Building in Section 1.23.5 addresses the need for tightening high strength bolted connections to prevent the nut from loosening and falling off.
mob 49
2 In deviation from the above, DCA 9764 upgraded the platform to Category I and changeout of material, but did not change the connection requirements specified in DCA 1090.
This is a deviation (445/8408-03).
Texas Utilities Electric Company is hereby requested to submit to this office within 30 days of the date of this Notice of Deviation, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further deviation from comitments made to the Comission; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.
Dated:
July 26, 1984 e*
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APPENDIX C U. S. NUCLEAR REGULATORY COPHISSION REGION IV NRC Inspection Report: 50-445/84-08 50-446/84-04 Dockets: 50-445; 50-446 Construction Pennits: CPPR-126 CPPR-127 Licensee: Texas Utilities Electric Company (TUEC)
Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES), Units I and 2 Inspection At: Glen Rose, Texas Inspection Conducted: November 14, 1983 through Parch 31, 1984 Inspec ors:
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/ Date j (c. E. Cummins, Senior Resident Inspector-Construction aragraphs 1,2,3,5,6,7,8,9,10,13)
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=rY'W Sf/D/8f W. F. Smith, Resident Inspector-Operations
' Da te (paragraphs 1, 4, 13) l be/ V L.1. Martin / Reactor Inspector. Engineering Section
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C. R. Oberg, Reactqq Inspector, Reactor Project Sec. A Date (paragraphs 1,11, Y3) l
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D. M. Munhicutt', Chief Reactor ProA ct Section A Date*
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D. M. iunnicutt, Chief, Reacto Frofect[5ection A Dete' Inspection Sumary 1
Inspection Conducted November 14, 1983 through March 31, 1984 (Report 50-445/84-08) i Areas Inspected: Routine, announced inspection of licensee action on previous findings,10 CFR Part 50.55(e) report followup,10 CFR Part 21 followup, allegation followup, independent inspection of coatings, training of protective coatings inspectors, review of safety-related systems, inventory of audit material in custody of NRC, plant status, and plant tours.
The inspection involved 190 inspector-hours onsite by five NRC inspectors.
Results: Within the ten areas inspected, two violations (gaps on Unit 1 l
polar crane bracket and seismic connections exceed design requirements, paragraph 3 and failure to perfom required inspections, paragraph 11) and one deviation (deviation from FSAR design requirement, paragraph 11) l were identified.
Inspection Sumary Inspection Conducted November 14, 1983 through March 31, 1984 (Report 50-446/84-04)
Areas Inspected: Routine, announced inspection of licensee action on previous findings, ID CFR Part 50.55(e) report followup, 10 CFR Part 21 report follow-up, independent inspection of coatings, training of protective coatings l
inspectors, inventory of audit material in custody of NRC, and plant tours.
The inspection involved 44 inspector-hours ensite by two NRC inspectors.
Results: Within the seven areas inspected, no violations or deviations were icentified.
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3 DETAILS 1.
Persons Contacted Principal Licensee and Contractor Employees
- 8. R. Clements. Vice President Nuclear Operations
- J. C. Kuykendall, Manager Nuclear Operations
- J. T. Merritt Site Project Manager
- R. A. Jones, Manager, Plant Operattors
- T. L. Gosdin, TUGC0 Public Infomation Coordinator
- R. T. Jenkins, Operations Support Superintendent
- M. Mc8ay, Engineering Manager, TUGCO, Engineering and Construction (E&C)
- R. P. Baker, Staff Engineering Manager, TUGC0 E&C
J. Marshall, Licensing Supervisor (Corporate Office)
- D. E. Deviney, Operations QA Supervisor
- T. P. Miller Lead Startup Engineer TUGC0
- C. H. Welch, QA Services Supervisor
- H. A. Lancaster, Startup QA Specialist
- J. C. Smith, Operations QA
- M. Riggs, Operations Support Engineer B. C. Scott, QA Supervisor A. Vega, CA Services Supervisor R. Kissenger, Project Civil Engineer J. D. Hicks, Assistant Site QA Supervisor R. L. Moller, Westinghouse Site Project Manager G. Purdy, Site OA Manager Brown & Root (B&R)
H. Hutchinson, Project Control Manager G. L. Morris, Site Mech. Level III ASME Quality Engr., B&R The NRC inspectors also contacted other plant personnel including members of the construction, operations, technical, quality assurance, and admin-istrative staffs.
2 1
- Denotes those attending one or more exit interviews.
2.
Plant Status Construction of Unit 1 is approximately 97% complete with fuel loading scheduled for July 1984. There is presently a great deal of effort to complete areas and then turn the completed areas over to Texas Utilities Generating Company (.TUGCO) operations. The turnover process requires two phases. The first phase takes place when construction I
completes a specified area and turns that area over to the startup
(
group. The second phase of the turnover process is when TUGC0 opera-tions completes final acceptance of the area from the startup group.
The licensee has identified 422 distinct areas which are to be turned over.
As of March 9, 1984, 158 of these 422 areas had been turned e
y
4 over from construction to the startup group. TUGC0 operations has made final acceptance of 66 of the 422 areas. The 422 distinct areas identified by the licensee to be turned over vary greatly in size and complexity; therefore, the number of areas turned over pro-vides an indicator that progress is being made, but to make a determina-tion as to the degree of progress, the size and complexity of each area must be evaluated.
Construction of Unit 2 is approximately 65% complete. Fuel loading is scheduled for January 1986.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation (445/82-11): Failure to Perfom Inspections of Installation Activities Related to Unit 1 Containment Polar Crane.
The licensee's Nonconfonnance Report (NCR) M-82-00894 documents the above violation. The disposition of NCR M-82-00894 directed that the polar crane girder connection finger shims previously installed per DCA 9872 were to be removed and inspected and any deviations from the requirements of DCA 9872 were to be identified to engineering for resolution. The licensee removed and inspected all of the finger shims associated with the Unit 1 polar crane bracket and seismic connections. Durir.3 this inspection, any shim that did not meet the design requirements of DCA 9872 was replaced.
This included the replacement of ten finger shims that were found to havs clipped fingers. Operational traveler CE-82-370-8104 was issued to accomplish and document the shim inspection and rework directed by NCR M-82-0094. Traveler CE-82-370-8104 also instructed that the new shims were to be installed per the requirements of DCA 9872.
The shim inspection and rework was inspected and documented by quality control (QC) inspectors on NCR M-82-00894. This NCR was closed on January 24, 1983. The quality control inspection of I
the shim rework satisfies the requirements which were previously not met and which resulted in the original violation. This item is closed. However, the NRC inspector perfonned a random inspection of the polar crane girder connection shims and had the following two concerns:
l (1) Design Change Authorization (OCA) 9872 required that all gaps greater than 1/16 inch be shimed. In addition QC personnel verified that the gap for each polar crane girder connection was less than 1/16 inch and documented this on a shim documentation card which was attached to Traveler CE-82-370-8104. However, the NRC inspector observed that the following randomly selected girder connections had gaps that exceeded 1/16 inch:
l l
5 Connection Location on Girder (looking Approximate Girder Number from inside containment)
Gap 23 center 1/8" 23 right 1/8" 26 right 3/16" 20 center 5/32" 20 left 3/16" 19 right 3/16" 17 center S/32" 16 right 1/8" This is an apparent violation (445/8408-01).
(2) DCA 9872 required that the shims be tack welded as shown on Gibbs and Hill sketch SK82032 (Sheet 3 of DCA 9872). General Note 4 of SK82032 states that shims in the seismic connection may be welded to either vertical plate; however, on the seismic connections for girders 18, 22, 26 and 27 the tack welds which welded the shims together also tack welded the vertical plates together. This concern was discussed with licensee personnel. This is an unresolved item (445/8408-04).
b.
(Closed) Severity Level IV Violation 445/8323-02: Instructions.
The five jam nuts identified as being loose were reworked and verified by QC to be " snug tight." The inspection checklist of procedure CP-QAP-12.1 was revised so that jam nut tightness is verified.
c.
(Closed) Unresolved Item 446/8309-01: NDE Level III Certification The licensee inspector's NDE Level III certification was rewritten on May 27, 1983, to show that his certification was based, in part, on successful completion of examinations.
4.
10 CFR Part 50.55(e) Report Followup Inspection The RRI (Operations) conducted a review of all reports made by the licensee pursuant to 10 CFR 50.55(e) since the CPSES construction pennit was issued on December 19, 1974. During the period between December 19, 1974, and February 17, 1984 NRC reading files showed that 103 reports were transmitted to the Commission. TUGC0 logs were in agreement. Of these, subsequent correspondence indicated that the licensee, upon further investigation, concluded that 57 reports did not meet the reporting criteria of 10 CFR 50.55(e) and thus were "not reportable."
The balance of 46 10 CFR 50.55(e) reports appear to be reportable except for three recent items, which were under investigation at the time of the inspection.
1 6
The RRI noted that 26 10 CFR 50.55(e) reports had been closed by the licensee. However, the status report published weekly by the site QA secretary indicated that they were awaiting NRC action for closure.
The licensee's representatives stated that the item would be closed and removed from the weekly report as soon as the SRRI (Construction) reviewed the records submitted to him and specifically addressed each in an inspection report as satisfactorily closed. At the exit interview of March 2,1984, the RRI pointed out that this is not a requirement of the NRC and as such the NRC should be removed from the status report as actionee for closure of each item. The records subnitted to the SRRI (Construction) should be retrieved and placed in the appropriate licensee-controlled file, subject to future NRC audits. During the exit interview the licensee stated that this would be done.
The RRI reviewed eight of the 10 CFR 50.55(e) report folders in detail.
The licensee refers to them as "Significant Deficiency Analysis Reports" (SDARs). Attributes evaluated included followup correspondence, depth of investigation, and ccmpliance with reporting requirements. The eight folders were numbered SDAR 81-07, 82-03,82-07, 82-09, 82-13, 82-14, 83-03, and 83-20. Half were ruled "non-reportable" by the licensee, and half were " reportable." The RRI did not observe any deficiencies in any of the folders.
In addition to reviewing specific SDAR records, the RRI reviewed the following applicable procedures:
" Control of Reportable Deficiencies" DQP-CS-6
" Reporting of Significant Deficiencies" CP-QP-16.1 "Significant Construction Deficiencies" CP-QP-15.6 "SDAR Status Tracking" l
l The above procedures appear to meet the requirements of 10 CFR 50.
l The condition and tracking of each of the SDAR packages substantiate this.
l However, the RRI noted that the corporate office in Dallas, Texas, has one numbering system with their own log for SDAR's originated in the corporate office. The CPSES site QA office has another nmnbering system, with their own log, for SDAR's originated at the site. The corporate office tracks all SDAR's, but CPSES tracks only the SDAR's originated at the site. At the exit interview of March 2, 1984, the RRI commented that Site status report addressees could be led into believing the site tracking system is complete when such is not necessarily the case.
No violations or deviations were identified.
l l
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7 5.
Followup of Part 21 Report On February 3, 1984, a licensee audit of one of it's suppliers, Gulfalloy, Inc., identified an apparent falsification of inspector's eye examination records. This apparent falsification of records was reported to the NRC by Gulfalley, Inc., in accordance with the reporting requirements of 10 CFR Part 21. The falsification of eye exam records occurred when the eye exam records from an eye exam given to three inspectors on
, November 13, 1980, were photocopied and the date changed so that it would appear that the three inspectors hsd also received eye exams on October 22, 1981. Additional eye exams were given to the inspectors on September 15, 1982, and again on January 16, 1984. The Gulfalloy, Inc.,
employee responsible for ensuring that the inspectors received the required eye exam was also responsible for reviewing material manufac-turers chemical and physical test results.
The NRC inspectors discussed this event with licensee personnel and were infomed that corrective action would include a review of the records of material received from Gulfalloy, Inc. The NRC inspector will continue to monitor the licensee's corrective action.
No violations or deviations were identified.
6.
Followup of Allecation The following allegation was relayed from the NRC Region IV office to the NRC inspector for followup: " Fork lift ran into guide rods by missile shield. Rods were approximately 2h" diameter stainless steel." Represen-tatives from the Office of Investigations interviewed the alleger in order to obtain more details regarding this allegation, but were unsuccessful in this effort.
/
The NRC inspector was unable to identify an event that fit all the i
D specifics in the above allegation. As far as the NRC inspector could (p'$
determine from discussions with personnel familiar with work in the reactor building, fork lifts have not been used in the reactor building.
However, the following event could have been what was observed by the alleger:
On October 14, 1983, the refueling crane struck and bent a themocouple column. This incident and subsequent corrective action were documented I
on Westinghouse Field Deficiency Report TBX-10285 and Brown and Root NCR M-11438. The themocouple column that was bent is a long (approxi-mately 17 feet) tube that provides support for incere thermocouple l
tubing between the upper core internals and the reactor vessel head.
The lower end of the thermocouple column is attached to the upper core I
assembly.
i 8
The refueling crane is a bridge type crane that spans the refueling cavity.
At the time the incident took place, the upper core, assembly was mounted on extension legs and stored in its normal storage location in the re-fueling cavity. The extension legs elevated the upper end of the thermo-couple column.high enough to place it in the path of the refueling crane.
The bent thermocouple was reported, evaluated, and straightened as reported in the two documents identified above. This allegation is closed.
No violations or deviations were identified.
7.
Independent Inspection of Coatings Brookhaven National Laboratories (BNL) has been contracted by the NRC to conduct an independent inspection of the CPSES protective coatings program and its implementation, and to investigate allegations of improprieties in the protective coatings area.
During this inspection period BNL inspectors performed three onsite inspec-tions at CPSES.
The scope and findings of this ongoing inspection will be documented in a subsequent NRC report.
8.
Training of Protective Coatings Inspectors l
On March 8, 1984, the NRC inspector attended a training session given for l
protective coatings quality control inspectors. The purpose of the training session was to review and discuss recent changes to protective l
coatings Procedure QI-QP-11.4-26, " Inspection of Steel Substrate, Sur-face Preparation, Primer Application, Primer Repair Seal and Finish Coat Application and Repair". The lesson plan for the training session was followed and the attendees were allowed ample opportunity to discuss the topics covered.
I No violations or deviations were identified.
9.
Inventory of Audit Material in Custody of NRC On March 9,1984, the NRC inspector took custody of a box containing file l
folders from the site quality assurance supervisor. The box of file l
folders had been collected by licensee personnel during an audit of quality control inspectors conducted on March 8, 1984. An NRC repre-sentative subsequently made an inventory of the contents of this box.
- 10. Plant Tours At various times during the inspection period, the NRC inspector conducted general tours of the reactor building, fuel building, safeguards building, l
t 9
electrical and control building, and the turbine building. During the tours the NRC inspector observed housekeeping practices, preventive maintenance on installed equipment, and ongoing construction work.
No violations or deviations were identified.
- 11. Review of Safety-Related Systems (Unit 1)
, a.
Platfoms Inside Containment On December 14, 1983, the NRC inspector observed loose bolted connections on platform OP-11 in the pressurizer compartment.
Platfom OP-11 supports safety-related instrument tubing for two channels of pressurizer level on the under side of the platform. A review of the design documentation including Gibbs & Hill Drawing 2323-S1-0556, Revision 4, DCA 9764, Revision 3, and DCA 1090 indicated that this platfom was originally designed as nonsafety-related. It was upgraded to Seismic Category II with the particular beams in question being Seismic Category I as they were supporting safety-related instrument tubing for two channels of pressurizer level. DCA 1090 required that the bolts be " hand tight only" to allow for lateral expansion of the platfom, but it did not address any locking device or thread upset to prevent nut backoff. DCA 9764 upgraded the platfom to Category I and changeout of material but did not change the connection requirements specified in DCA 1090. Subsequent to identification of this problem by the NRC inspector, a DCA was initiated requiring the use of Jam nuts or upset threads to correct this problem with the platforms shown on G&H Drawing 2323-SI-0556. The NRC inspector advised the licensee that DCA 1090 affected more than one drawing l
and that engineering would have to look at all similar connections for general application and corrective action.
This is a deviation (445/8408-03).
b.
Main Coolant Loop Restraints During an inspection inside containment, Unit 1, the crossover leg restraints of main coolant loop No. I were examined for con-formance to applicable drawings for materials, construction, and installation. Materials and welding were found to be as specified j
on the drawings.
There are two similar restraints on each main coolant loop made of ik inch ASTM A36 carbon steel. The restraints were manu-factured by AFC0 Steel Corporation in accordance with G&H 0550, e
+
10 Revision 4.
The restraints are massive, approximately 11 feet long 3 feet wide and Sh feet tall. Each restraint is fastened to the base mat by 16 prepositioned 2h inch diameter anchor bolts as specified on G&H drawing 2323-51-0551, Detail B.
Drawing $1-0550 required that each anchor bolt be pretensioned to "90 plus or minus 10 kips" and utilize a washer, two regular nuts and a jam nut made of ASTM A 540 material. The bottom nut and the washer required a tack weld as noted in the drawing.
The tack welds were not found on any of the anchor bolts inspected.
In addition, no record of a QC installation inspection of the restraints for loop No.1 or any other loop of Unit 1 could be found.
Thus, pretensioning of the anchor bolts could not be confinned.
The crossover leg restraints are major components of the main coolant piping seismic restraint and support system. Appendix B of 10 CFR 50, Criterion X, requires that inspections of activities affecting quality shall be established and perfonned to verify confonnance with documented instructions, procedures, and drawings for accomplishing the activity.
TUEC QA Plan, Section 10.0 requires that planned written inspection procedures be used. No requirement for inspection of the crossover leg re traints had been issued. This is also contrary to 10 CFR 50, Appendix B, Criterion X.
This is a violation (445/8408-02).
- 12. Unresolved Items Unresolved items are matters about which more information is required in order to determine whether they are acceptable items, violations or deviations. One unresolved item related to polar crane shims (Unresolved Item 8408-04) is discussed in paragraph 3.
l
- 13. Exit Interviews The NRC inspectors met with members of the TUEC staff (denoted in para-graph 1) at various times during the course of the inspection. The scope and findings of the inspection were discussed.
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5.
Followup of Part 21 Report On February 3,1984, a licensee audit of one of it's suppliers, Gulfalloy, Inc., identified an apparent falsification of inspector's eye examination records. This apparent falsification of records was reported to the NRC by Gulfalloy, Inc., in accordance with the reporting requirements of 10 CFR Part 21. The falsification of eye exam records occurred when the eye exam records from an eye exam given to three inspectors on November 13, 1980, were photocopied and the date changed so that it would appear that the three inspectors had also received eye exams on October 22, 1981. Additional eye exams were given to the inspectors on September 15, 1982, and again on January 16, 1984. The Gulfalloy, Inc.,
employee responsible for ensuring that the inspectors received the required eye exam was also responsible for reviewing material manufac-turers chemical and physical test results.
The NRC inspectors discussed this event with licensee personnel and were informed that corrective action would include a review of the records of material received from Gulfalloy, Inc. The NRC inspector will continue to monitor the licensee's corrective action.
i No violations or deviations were identified.
6.
Followup of Allegation The following allegation was relayed from the NRC Region IV office to the NRC inspector for followup: " Fork lift ran into guide rods by missile shield. Rods were approximately 2h" diameter stainless steel." Represen-tatives from the Office of Investigations interviewed the alleger in order to obtain more details regarding this allegation, but were unsuccessful in this effort.
The NRC inspector was unable to identify an event that fit all the specifics in the above allegation. As far as the NRC inspector could detennine from discussions with personnel familiar with work in the reactor building, fork lifts have not been used in the reactor building.
However, the following event could have been what was observed by the l
alleger:
On October 14, 1983, the refueling crane struck and bent a thermocouple column. This incident and subsequent corrective action were documented on Westinghouse Field Deficiency Report TBX-10285 and Brown and Root NCR M-11438. The thennoccuple column that was bent is a long (approxi-mately 17 feet) tube that provides support for incore thermocouple tubing between the upper core internals and the reactor vessel head.
The lower end of the thermocouple column is attached to the upper core assembly.
F0lA-85-59 3316 i
8 The refueling crane is a bridge type crane that spans the refueling cavity.
At the time the incident took place, the upper core assembly was mounted on extension legs and stored in its normal storage location in the re-fueling cavity. The extension legs elevated the upper end of the thermo-couple column high enough to place it in the path of the refueling crane.
The bent thermocouple was reported, evaluated, and straightened as reported in the two documents identified above. This allegation is closed.
No violations or deviations were identified.
7.
Independent Inspection of Coatings Brookhaven National Laboratories (BNL) has been contracted by the NRC to conduct an independent inspection of the CPSES protective coatings program and its implementation, and to investigate allegations of improprieties in the protective coatings area.
During this inspection pcriod BNL inspectors performed three onsite inspec-tions at CPSES.
The scope and findings of this ongoing inspection will be documented in a subsequent NRC report.
8.
Training of Protective Coatinas Inspectors On March 8, 1984, the NRC inspector attended a training session given for protective coatings quality control inspectors. The purpose of the training session was to review and discuss recent changes to protective coatings Procedure QI-QP-11.4-26, " Inspection of Steel Substrate, Sur-face Preparation, Primer Application, Primer Repair Seal and Finish Coat Application and Repair". The lesson plan for the training session was followed and the attendees were allowed ample opportunity to discuss the topics covered.
No violations or deviations were identified.
9.
Inventcry of Audit Material in Custody of NRC On March '9,1984, the NRC inspector took custody of a box containing file folders from the site quality assurance supervisor. The box of file folders had been collected by licensee personnel during an audit of quality control inspectors conducted on March 8, 1984. An NRC repre-sentative subsequently made an inventory of the contents of this box.
- 10. Plant Tours At various times during the inspection period, the NRC inspector conducted general tours of the reactor building, fuel building, safeguards building,
/
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Miscellaneous P. 4 e
CONTROLLEO COPY COMANCHE PEAK NUCLEAR POWER PLANT ALLEGA110NS AND/0R INVESTIGATIONS SUP94ARY CROSS REF./0R COMPLETION SOURCE TRACKING CATEGORY 1-7**
SCHEDULE ALLEGER-DATE RECEIVED NO.
ALLEGATION OR CONCERN ACTION /ST ATUS ANON CONFID 8N/DATE SYSTEM NO.
LEAD OPEN COMPLETE SOURCE 00CUMEN1 PAGE TASK A-45 2/28/84 RIV 84-A-0029 1
AM-24 Osmage to stainless steel Initial dispo-RIV Q4-84-016 P. I rods in upper internals sition in 01 Rpt.
IR 84-08 components of reactor Q4 84-016 and vessel (Thermal couple IR 84-08 volume)
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Page 1 of w
COMANCHE PEAK STEAM ELECTRIC STATION DESIGN CHANGE AUTHORIZATION (M tQ (WILL NOT) BE INCORPORATED IN DESIGN DOCUMENTS DCA NO.11.311 Rev. I 1.
SAFETY RELATED DOCUMENT:
XX YES NO 2.
ORIGINATOR: CPPE xx ORIGINAL DESIGNER 3.
DESCRIPTION:
A.
APPLICABLE EFII/DWG/ECEWXENI 2323-S1-0515 REV.
6 B.
"ETAILS THIS REVISION VOIDS AND SUPERSEDES DCA-11.311 Rev. O.
Durina coerstion the uclift lues on the colar crane have struck and damaced acerovimatalv ?? stiffenar olatos en tha colar reaaa cirdor Solution: Notches on damaced stiffeners are to be repaired by fillina with weld metal and crindinc smooth or by reolatino the stiffener. Bent stiffeners shall be reolaced. The Uclift lues have been modified s
to allaviato tho intar#aranco.
w 4
SUPPORTING DCCUMENTATION:
NCR M-81-0006d 5.
APPROVAL SIGNATU % DC/sgf 3-22-82 A.
ORIGINATOR:
_ j um
/C DATE J-2 2 -8 2 DESIGNREPRESENTA!IV MD DATE 2 2.2.YL B.
g 6.
VENDOR TRANSMITTAL REQUIRED: YES NO XX 7.
STANDARD DISTRIBUTION:
JOB NO. 35-1195 DCA FORM 11-80 ARMS (Original)
(1) f E C EIV E R Quality Enaineerinc (1) t
..SM 23 l932 TS for Orig. Desigii.
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1 COMANCHE PEAK STEAM ELECTRIC STATION lD AS UTtLITIES
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GENEftATING CO.
NONCONFORMANCE REPORT (NCR)
M-61-00064 i
i UNIT STRUCTURE /SIST EM UE M 'COM PON[N T TAGbbNUMBhR LbCATION OR ELEVATIOt[
~ hlR NO
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Polar Crane 1
RB #1/ 8100 Girder cpl-MESCCP-01 RB. #1 950'7" 1 _ N/A NONCONFORMING CONDITION iIj During operation of the polar crane, the up-lift plate strikes approximately j
32 gusset plates welded to the crane runway girder. The gusset plates have o
been deformed (notched) ranging from 3/4" to approximately 1 1/4" in depth.
E E
See attached drawing details for notch locations.
g E
O CL i
REFERENCE DOCUMENT:
REPORTED BY:
DATE:
R.D. Ice 3
18, 81 l f
I OE REVIEW / APPROVAL:
DATE:
b /]Cl$
O ACTION ADDRESSEE DEPARTMENT J. T. Merritt/C. Moehelman Engineering REWORK REPAIR USE AS fS SCRAP l
The stiffener plates are to be repaired or replaced as shown on DCA 11,311.
Traveler fi-81-2129-8100 will modify uplift lups on the Polar Crane to alleviate g
the interference.
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Page 1 of 1
COMANCHE PEAK STEAM ELECTRIC STATION DESIGN CHANGE AUTHORIZATION
{ty,tti(WILLNOT)BEINCORPORATEDINDESIGNDOCUMENTS DCA NO.
11,311 1.
SAFETY RELATED DOCUMENT:
XX YES N0 2.
ORIGINATOR: CPPE xx ORIGINAL DESIGNE".
3.
DESCRIPTION:
A.
APPLICABLE BMEs/DWG/32C3MENR 2323-si-osis REV.
6 B.
DETAILS During operation the uplift lugs on the polar crane have strark and damaced aonroximately 32 stiffener olates on the rolar crane cirder.
Solutient Notches on daraced stiffeners are en ba ran,4*ed hv fillin-i*h weld metal and crindinc e-noth nr by repla-in- *hn ceiffonor_
Rane c* 4 f fn-c' mhn11 be repin-nd.
The unl i f e in n havn hon- ~naifinA en n11avimen +ho 4-a-Farnmen 4.
SUPPORTING DOCUMENTATION:
NCR M-81-00064 5.
APPROVAL SIGNATURE
- /sgf 10-15-81 A.
ORIGINATOR:
MmAJ -
4 DATE to r T 8 /
B.
DESIGN REPRESENTAT VE
[///
4 W-DATE /t:7-/4"8/
6.
VENDOR TRANSMITTAL REQUIRED: YES NO xx 7.
STANDARD DISTRIBUTION:
DCA FCR1 11 -80 ARMS (Original)
(1)
Quality Engineering (1)
TS for Orig. Design.
(1)
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Title:
MEGGEK TEST
- A 45573 DATA SHEET 1 ARMS Applicable Prerequisitas of aragraph 4 9 9 flo f E3 are Complete: O w@
Date System Designation:
04: TI Pct AR CCAe/F Systen No: E (GL/
CABLE OK Ey0IPMENT KATED TEST TEST DESIGN ATION VOLTS CONNECTION VOLTS HEG0HMS AM Tl [ AOK MC6T MLTLQ \\
600 ANT /f f,db 500 toD+
hHT2 god PMT2 f(,db 6 C C, 100 +
nnn see 4ar2/ra sec 300 +
N N
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patui /m est umuacA goo g uariic.c 8 sco i cc 4 pgm2 yo eur2/946 sec loo +
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EOR INFORETI:N ONLY uma s
Identification No.
Mrc. 2319 NNn w\\ n u NA Calibration Due Date fo/ >/; 3
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KIL! ARKS :
9[tl ff'd WITNESSED BY:
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DATE:
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DATE: lo-2.d h TEST KESULTS: LXSAT UNSAT REVIEWED BY:
V
- M. -
DATE: o 4 /M1 APPROVED uY:
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Hevision 7 MSC: P 1 E t' * "
Date Anproved: -dG ee /7 Drtianiza t ion: Id3 Page 7 of 8
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Doc.
Title:
?!6GGCd TLST DATA S:lE-;T 1 57828
^iets Applicable Prerequisites of Para:(/rppo I..D are Coaplete: Gd k$4 Date: /O 29-P3
.2.
v' Systen Des 1:; nation: MA//7 7
[ct g f C/24 A [
Systen ;;o: M/OM l
CA3LE OR EQUIN1f.::T RATF.a TdST TF.ST DESIG'; ATIO:;
VOLTS Ca;;.;ECT10:;
VOLTS
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Iw f w
N NN N
ANN 72 f
- f. o o B b SA B "'o
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AHMT3 Y Gc6 e L &J Eica sco' N N N
0 N N
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ng% snow l0N ORY N-m TEST EQUIPHENT:
Type re c ee r A
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Identification No.
md 6 3 /6
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Calibration Due Date f5 fA. O N
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RE:!ARl*S : ANN 7/
f5 Mcg/ iWFn/. /d a5 # /[ /cd e He,d,Ja-> dm nd redad Ad were cdecAed ""* * ""
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uATE:w.mc uIT;;ESSED an._
utux.
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Mhb TEST RESULTS: M AT U:; SAT REVIE.JED BY:
DATE: /O-27 82 APPROVED SY: 8d-DATE: #/N'2 wy /
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>>=iste:
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M ES Anh 14nys s "n;: Nc..
l 5:artu: Syste: S o'. : 1-8IO4 Au:ncrs:
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tesare::e : a.- =ss: E/-0033 d 8 CI-ori(-08 Uc:t *::a: 1:= (Ildg., eleva:".:n
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Ieasen f:: Uc;k:
(i.e.,
- 3. O:0, ::,".. e::. ) E.O O *2.' q2, b :::a:ad ti=a required : ::=;1ste u k: 3 DAYS
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v.:k assuas:ee sy: Les IMans 32.8 44-13-8'4
.sa=e/.5 =ne i=:::s:=nt.;a:e 1
7TagsRequired:d!73 _ NC If Yes, C?-SA?-5 Au:acri: :1:: Nc.: M/A 54fe:
STA-o05 Cleara= e No: /%f-o 75 +
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4/ 7$Y Placed cc E=ld 'my:
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1e:esting Locuired:
EN~l $6-8 ON Gl-ebfg y y fy y p3 ff-ggy 5 H 9, A $EW l AND EG-9 S GPS 7,2,7 4. ),7 pn 1.9. Sep Au Mc2<, 0; tho 2 (b4 n
Re:ese ce=.le: d N d -
c;/sg sta =, m eerm. e lequired Ke:ests and, Ke:es: Da:a A::: ved Sy:
M
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. ORIGINALF0lA-85-59 5'725
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k DC;i: VIPiu y Proc. So.: XCP-ir.- i Pade: i Kev.: 7 XCP-EE-1 LISC : P 1:P**
Jaglio.:
CP P MESCC9-O Revision 7 Date Approved: 7/Cf/,f Organization: n,s Page 7 of B
(
Doc.
Title:
?!fGCER TEST DATA SdEET 1 h
AR'tS Applicable Prerequisiteg of Pa agraph 4.0 i
f are Complete:
W' (X
(
Date: 4 2M N 2-I Systen Designation:
OLb $ANb Systen No:
C)k CA3LE OR EQUIPMENT RATED TEST TEST DESIGNATION VOLTS CONNECTION VOLTS HEG0HMS V \\DO%U
'e ': O A -f<
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f, r, r R b('
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Sec
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l 6GO
/3b 8v0 300
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RETEST TEST EQUIPMENT:
l Ty pe um. c f
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ggg Identification No.
- C.m ir e4 A e4 /A 4 /A es 5,,,$u
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Calibration Due Date l
clCIAR1'S :
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DATA RECO CED j
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DATE:4-1ta M WITNESSED 3Y:
4!2 ES-TEST RESULTS: / SAT UNSAT REVIE'.iED JA DATE:
l APPROVED BY:
AM' b
DATE:
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Rev:
XCF-EE-9 lLCh: !? REC ?:o, :.e: XCP-EE--
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th M C C.J C Y.c.y, C, age:
2 Eevision 9 iMSC: ?IEF**
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Title:
IN!!'.A'. MOTO:- ROTA!!CN AND I"N-LN
[h g 3 DATA S'dII ARw.S MC~CE DISIONA'"CN:PeuCL CQ4 RE > ANN HmW Ntch voit f al SYSTIM NC. : b)Od SCCRCI ?ID: Sus i C-gu Cue:c.e TOR N>_VI?'.J.7I DA~A:
Manuf.
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Eev4 9 IO?-II-9
('9\\. u g(:,CC P.'nl Revisice 9 6
IXSC: ?: I?**
!ag,So.-
Date A;;;;ved: 8f Of//
Orga :a::::: TOS Page 11 cf ;1 Loc.
Title:
".N!!!AL.w.0!OR RC A!!CN AND K;"N-;N
(
h 3
DATA SEEIT ms MC~CE CIS CNA 20N:htAR CR AG. Mmid wcc MirPo NrTtf er 2 SYSTIM NC.: 9\\OLI SOCICI TID: Bus i s.th e Cumicle t Of; NA.VI?LA I DATA:
- Medal No.
N/A Serial Sc.:
n;/A Ma=uf.
N /g E?
ed /,s
- RPM n /4
- Vol
- s N/A F.L. A=as u f,a Ccce win
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Date:
MCC?. SPACI E7_CII:
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IDCS: VT?RIC ? ::. Sc: X~?-EE-9 Page:
Rev: i IC?-II-9 2
I MSO: ?IEF**
!ag Sc.*
(' N. bA G 5 ( C P..n t Revis* : 9
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M/A Serial Nc.:
N /A I?
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Date:
OF ?LE.AC7.'I I. 0 4,f 24,!FL./
LI.I COMPLI I:
MO*CE S?ACI IICIR:
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4In A=ps 3"5 TCLTAGE:
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?h. C4lA
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Wla A=ps 7~.IEA-*!CN CA-'A:
(C :ss cut :. applicable diagra=)
Masi.===.C1:vable 71 -ra:1 :: 0.314.1:/see vel: city or Ala ils displace =es pe: :::c: asuf.
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Rev: f l
XO?-II-9
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n MSO: ?IE?**
Jat No.:
(' N - M E S CC P -o,n Revisien 9 Oa:e A;;; ved: ~/ ' f 3 / ~l C:sts :a::::: g Page ;l cf.1 Loc.
Title:
IN ;A:..w.0 0R ROTA!!CN AN"' R1"S-I.S
., A. a. a. re.
bot 1 u
(
A??.S MC~01 OIS*05A'" 0N:PeuCL CR A4 ~ BCttAC hAtTc.C
- i SYS:IM N0.: F.)osa SCCRCI FID: Sus 1 C-A a Cusicle e tOB NAMI?' ATI OA~A:
Ma=uf.
N /g
- Model No.
N/A Serial Sc.:
n, /s.
I?
- 4 in
- ?JM nla
- Vel
- s N/A F.L. A=ps av f a Ccce ain
- insula
- ::: Class wfa
- Se
- rice Fae:c:
,, m JJ?L;CA3LI ?II?.IO !S!!' f[CF ?AIA*J.A?E.0 AII COMPLI h f f a 4-<
Oa:e: 4 2V FV i
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Wlp Vel:s:
4)a A=ps 3US 70LTAGE:
A-3 wla 7el:s; 3-C N/A Vel:s; C-A W/H 7cl:s;
?-N g /A 7cl s
'MC"01 RO~.CICN:
07;
/ C07 (Vieved f := :::-bea:d :: ::p and)
MC~01 S?ID:
sin I?M FAN.CI FLOW: Desig: NlA SCTM; A::ual C/9 SC7M 3 N530 COJZ; :
?h. A m l., A=ps; Ph. 3 NIA A ps:
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Annex 3 Conversation Record Allegation Number A M M Time ID AM Date 9 l'8 Type
/ Visit Conference Telephone Incoming Outgoing Name of Person (s) Contacted or in Contact With You Organization Telephone Number GTE\\M 4 CHME.F F E G2L 68 %
t$ LECT r2)(AO
SUBJECT:
Fese,Too06O & A E>t Ch l52Ol LEO W1125S
SUMMARY
M f2. 4/N AGFFElz CPEMEE'D THE ('2) JOMd.T100 DC)X E 9 AMD N E TOO WITME.4 ssp AMD A6T2EEP THEf25 ARE Mo brzoRER Wires,
O Name of Person Documenti c Conversation A c.kL Q'G ETT Signature
- L!d
)
Date h / !N Name(s)of ther Persons Who Were Present During Conversatice.
1bom LOAM 4 I have reviewed the sumary of the. conversation with the individual (s) named below and agree that it accurately represents the conversation.
Signature of Person Providing Infonnation File: Allegation Work Package cc: Project Director Group Leader Additional pages may be attached as needed. Additional pages should be identified, signed, and dated.
F0lA-85-59 8/ne
Annex 3 Conversation Reco-d Allegation Number Ak{-6 Time _10 Ald Date4[lff84-t i
Type V Visit Conference Telephone I.ncoming Outgoing Name of Person (s) Contacted or in Contact With You Organization Telephone Number Y)nlb hDAM 6
%b%.
Y-$30 6d 12 y LfCTT216A L, GCs
SUBJECT:
faToo"5 C^*'5 3 r # K *'" * ' "'
SUMMARY
Mr. A[7AMG kW MPA>J1ED TH E WRITER To d'*"^' 'T I O G P ECT Te ALLa s e p erzogse:u w i p es i ro ru s J t)M c-T ' oM Box cm 1= EEpiM 6 TR E5 FesTooO SD CAf5 LEG, M R., A DAMG GTATED TH AT 145 PlO Noy GE TEE AM't'
{3%2ci<' Ef0 WIFEEG J M T ITH E12-P>oN Name of Pers Documen g Convg sation J Acre-- QGIE~'TT Signature L !h r./
/
Date d 9[/'2[Sd-Name(s) of her Persons Who Were Present During Conversation 4Tts.v't$ GCH ABFF6GL_
l I have reviewed the sumary of the conversation with the individual (s) named below and agree that it accurately represents the conversation.
Signature of Person Providing Infomation File: Allegation Work Package cc: Project Director Group Leader Additional pages may be attached as needed. Additional pages should be identified, signed, and dated.