ML19339B407
| ML19339B407 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/11/1962 |
| From: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8011060854 | |
| Download: ML19339B407 (22) | |
Text
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Pronosed Chance No.15 YANKEE ATOMIC ELECTRIC COMPANY Y
MI STUART STREET. BOSTON 16, MASSACHUSETTS January 11, l'962
.y U. S. Atomic Energy Commission
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N Washington 25, D. C.
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Attention: Division of Licensing and Regulation
Reference:
License No. DPR-3 (Docket No. 50-29)
Dear Sirst p file Cc;I
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Pursuant to paragraph 3.A of License No. DPR-3, as a= men. dded, m
Yankee Atomic Electric Company hereby requests authorization to make the following change PROPOSED CHANGE:
In preparation for the first refueling of the Yankee reactor we have reviewed and revised the pertinent maintenance instructions. The fol-lowing revised instructions are attached:
F.AINTENANCE INSTRUCTION 506E2 REACTOR REFUELII:G - Preparation of Reactor Systems for-Refueling fl.AETENANCE INSTRlCTION 5C6E4 REACTCR REFUELI!!G - Fuel and Control Rea Replacement s.e propose that these instructions be substituted for the earlier versions currently included in the license application. t;e further propose that item D.2.a.(2) of the technical specifications be amended to read as follows:
"During the refueling operation a record will be made of the neutron count rate before-and after any change in core geometry.
If an unexpected increase in the count rate by a factor of two on two of the three channels occurs after addi-tion of a new fuel assembly or removal of a centrol rod, the fuel loading operation will be suspended until the situation can be reviewed by plant technical supervisory perscnnel.
If necccsary to establish the shutdown margin of the core, a single control rod will be withdrawn using the manipulator crane and regulated by a plot of control rod position vs. inverse count rate multiplication. Using the inverse count rate data obtained in thic manner, the shutdown margin will be calculated.
If these calculations indicate that there will be lots than 5* dr/i; shut-4 do.:n with all contrcl rods insertcd in the fully loaced core, the boron concentration uill be increased to previc.e the required 59.,
dK/Kshutdownmargin."
rn 8011060pgy D
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U.S. Atomic Energy Commission Proposed Change No. 15 Attn.: Div. of Lic. and Reg.
January 11, 1962 Reasons for Chanae: As a result of the experience gained during the initial loading of the reactor in July and Augast of 1960, we have completely revised the Maintenance Instructions covering the refuel-ing operations. The versions presently contained in the license application were prepared in 1959.
Item D.2.a.(2} of the Technical Specifications is, at best:
applicable only to initial loading of a reactor or to a reloading arrangement in which all used fuel assemblies are removed ~before new fuel is added. During our initial loading we were delayed excessive-ly by the requirecents of this paragraph end found that it was unreal-istically restrictive. Our present plan for reloading is to remove approximately cne quarter of the old fuel and to proceed from that point with the addition of one new fuel assembly for each used assem-bly removed. The exchange would be made in such a way that the entire 1cwer core support plate is gradually uncovered for examination during the refueling operation. The proposed substitute fur Item D.2.a.(2) is suitable for any reloading arrangement but, more important, provides a means for the actual determination of shutdown margin at any point in the refueling operation.
Safety Considerations:
In our opinion, the proposed changes do not present significant hazards considerations not described or im.plicit in the license application, as amended to June 23, 1961, the date of issuance of Amer" ment No. 3 to license No. DPR-3, or as amended to the date hereof, and does not affect the accident analysis set forth in Section 4 of the licente application.
Echedulino of Chance: Reactor refueling is presently scheduled to take place during February or !!.crch,1962. The exact date is uncertain, in that it depends upon the extended lifetime available from Core I.
Upon apprcval of these revised liaintenance Instructions, additional copies will be submitted as an amende.ent to the licente application.
The proposed changes require authorization by the Commission pursuant to paragraph 3.A of the license, since they involve changes in the Technical Specifications.
(See paragraphs D.1 and D.2 of I.ppendix A to Li-cente No. DpR-3.)
Respectfully submitted, YANKEE ATGAIC ELECTRIC CCEP/LY g
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), "cr Roger J Cce,VjtePIccident.
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e' U.S. Atomic Energy Commission Proposed Change Io. 15 Attn. : Div. of Lic and Reg.
January 11, IS62 Cou.onwealth of !.iassachusetts January 11, 1962 Suffolk, ss Then personally appeared before me Roger J. Coe, who, being duly sworn, did state that he is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Yankee Atomic Electric Corpany, and that the statements therein are true to the best of his knowledge and belief.
ce fc6. A-Le n Donald G. Allen
!;otary Public My Coraission Expires Jan. 21,1%7 9
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MAINTENANCE INSTRUCTION NO. 506E2
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REACTOR REFUELING
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PhEPARATION OF REACTOR SYSTEMS FOR REFUELING I.
Objective To provide a safe and efficient method of preparin'g "5
the reactor systems for refueling and subsequently as-sembling the reactor vessel after refueling.
.h.
. i r-II. Conditions Prior to Head Removal
... s 1.
The reactor is shut down and depressurized; all main coolant' d ! %i y
~ ~ ~ ~ '
stop valves am closed.
2.
The reactor has been borated to shutdown concentration and cooled down in accordance with 0.I. No. 50hC2, PLANT SHUTDOW-REACTOR AND PRIMARY PLANT C00LDOWN.
3.
The pressurizer is filled with borated water and is prepared for draining.
h.
The main coolant system temperature is below 1h00F.
5.
The spent fuel storage pit is filled with demineralized water i
to a depth approximately even with the top of the spent fuel storage rack.
6.
Approximately 38 new fuel elements have been moved into under-water storage in fuel transfer pit using one temporary neutron channel to Ironitor the transfer into the fuel storage racks.
i 7,
A mixed bed resin is in place for fuel transfer pit demineral-ization as soon as water level allows operation.
l 8.
Pertinent auxilary systems are in the following status:
System Status Component Cooling System In operation, (Refer to 0.I. No. 50hI) as required Shutdown Cooling System In operation (Refer to 0.I. No. 50hM)
Nuclear Instrumentation System In operation (Pefer to 0.I. No. 50h0) if
506E2:2 1/11/62 System Status Vapor Container Atmosphere Control In operation Systems (Refer to 0.I. No. 50hQ)
Radiation Monitoring System In operation (Refer to 0.I. No. 50hP)
III. Precautions 1.
The radiation level above the surface of the refueling water will be continuously monitored by a gamma guard m9unted on the fuel handling crane.
2.
Minimum depths of water over the various reactor internals should be maintained to limit radiation level abcve the refueling water.
3.
The tools and equipment used should be kept free of dirt, grease, and foreigh matter.
h.
Personnel must wear special work clothing in all radiation and contamination areas. Refer to Section 507, RADIOLOGICAL HEALTH AND SAFETY.
5.
A pe-itive pressure must be maintained in the isolated loops, or the loops must be open to atmospheric pressure, so as to prevent main coolant pump stator can damage.
1 6.
For action to be taken in the event of a refueling accident, I
refer to Emergency Instruction 505B21, RE UELING ACCIDENTS.
7.
Foreign material must be prevented from falling into the reactor vessel while the reactor head is off, and no un-authorized or unnecessary personnel are to be allowed on the manipu'iator cranes or in refueling areas.
8.
Equipment such as MC valves which might cause inadvertent changes in reactivity shall be tagged out of service.
Date IV.
Instructions Complete Initials 1.
Enter the vcpor container.
Comply with M.I.
No. 506D, VAPOR CONTAINER ACCESS.
2.
Remove missile shiel? and store on steam generator cubicles '. and 1.
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i So6E2:3 1/11/62 Date Completed Initials 3.
Ready manipulator crane, a.
Install control cabinets b.
Install trollc y resistors c.
Check guide rods d.
Install pointer and stops and provide targets for frive rod and guide tube storage racks e.
Change lubrication in gear boxes f.
Replace SS boom guide bearings with C.S. bearings g.
Install warning bell h.
Add lights 1.
Install bracket for in-core instrumen-tation locking rod
- j. Install universal handling tool k.
Install T.V.
1.
Get elevations for guide tube plugs in rack
- h. Remove grating and beams over equipment hatch 3
and store on #h steam generator cubicle.
- 5. Remove equipment hatch cover and store on #3 steam generator cubicle.
6.
Remove rod drive air supply ducts and store on flat car.
7.
Remove flux vire tubes between reactor head and cavity edge, thernocouple connections, and intercom.
8.
Remove rod drive cables.
9.
Remove rod drive cable trays and store on flat car.
- 10. Remove rod drive coil stacks and store in racks.
- 11. Remove shield tank shielding blocks and store on #1 steam generatcr cubicle.
- 12. Remove reactor head thermal insulation and store on flat car.
506E2:h 1/11/62 Date Completed Initials
- 13. Remove top hat air duct and baffles.
a.
Eaffles bolted to top hat should be marked fcr reassenh!.y b.
Southeast setment of upper top hat must be removed first c.
Lower section of top hat must be modified to facilitate removal d.
Baffles bundled and stomd on charging floor Top hat sections stored on flat car e.
lb.
Install centrol rod and follower disengaging mechanism.
15.. Install track for bolt stretcher.
- 16. Install parts of guide tube rack.
- 17. Install jacking mechanism. Rig level in order or set into dowel pins.
18 Complete jacking pump changes.
a.
Install prefabricated gage and accumulator board b.
Install suction and discharge piping to cavity
- 19. Renove fuel chute blank.
(Cable car now rests against blank)
- 20. Complete vinch changes and check out:
a.
Wire DC motor b.
Check rotation of motor c.
Check proper operation of following:
1.
Stop and wait positions 2.
Slow down point 3.
C u riage speeds (loaded and light) h.
Lower lock valve 5.
Proper operation of dewatering system so far as possible in dry condition of shield tank cavity and fuel pit about storage rack t
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506E2:5 1/n/62 Date Completed Initials 6.
Check upper lock valve for water tightness d.
Install stand pipe float and remove jumpers
- 21. Add fuel assembly support block to carriage.
- 22. Operate fuel handling system with new fuel element through 5 complete cycles with shield tank cavity dry and only bottom of fuel transfer pit wet.
- 23. Complete filling of fuel transfer pit and place demineralization in service as required by water quality.
2h.
Tighten neutron shield tank expansion joint rings,
a.
Check condition of gasket b.
Replace missing washers removed placing shielding block racks c.
Install hooks on shield tank rim
- 25. Check that h BF, counters are operable and are indicating counts in the control room.
26.
Install kidney covers with new gaskets.
- 27. Place caps with 0 rings on valves on reactor head.
28 Install extension on reactor head tell tale valve to bring to operating position above insulation.
- 29. Paint the following carbon steel parts:
a.
Welds and clips added to head lifting rig since original painting b.
Nuts and washers of expansion joint ring c.
Moat between expansion joints d.
Bracket of temperature indicator
- 30. Set up internals stacking plate to scribe marks on cavity floor and add guide tubes.
506E2:6 1/11/62 Date Completed Initials
- 31. Start to lower reactor vessel water level to desired height.
a.
Check that hydrogen pressure has been reduced to approximately 2 psig of H n LPST 2
b.
Open pressurizer vent valve c.
Check solenoid relief valve and motor operated isolation valve closed d.
Open pressurizer drain valve and assochted valves in line to LPST e.
When the water level in the pressurizer falls below 150", open the vent connections on all the control rod drive mechanisms f.
Close the pressuricer drain valve 3n minutes after the water level in the pressurizer has reached 20" on the wide range water level indicator
- 32. Remove reactor head studs (see B&W Instruction Book, Pages h-9).
a.
Place numbered sets of stud, washer, and nut in stud carrier b.
Store carrier on charging floor c.
Remove unground studs to shop for completion of nachining d.
Install h8 stud hole seal plugs and "0" riras e.
Install h guide studs at hole numbers 9, 21, 33,h5 33.
Install head lifting fixture, a.
Observe point markings on legs b.
Weld bails on lifting rig and on polar crane hook c.
Clean and paint turnbuckle threads (after Step 39) 3h.
Install platform on side of cavity manipulator crane.
- 35. Cut instrumentation port welds, remove thimbles and Conoseals, a.
Smaller veld cut first by Yankee cutter i
506E2:7 1/11/62 Date Completed Initials b.
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See Lutruction Book, IN-CORE INSTRUME!TATION Section IV. P.2 36.
Place bullet nose covers on in-corc instrumentation thimbles.
- 37. Clean cavity, head, meat, etc.
- 38. Open 3/h" vent valve on the reactor head.
- 39. Lift reactor head 1/2 to 1 inch to check level-ness of head. Fasten line to bail of lifting rig.
h0. Fill shield tank cavity to level of tuo feet of borated refueling water. Refer to M.I. No. 506E3, REACTOR REFUELING, SHIELD TANK CAVITY-FILL DRAIN.
hl, Check shield tank cavity for leaks via the tell tales, compartments, and fuel chute.
h2. W.cinue to fill the shield tank cavity to a level of ten feet while running a capacity test on both SI pumps.
h3 Open the equalizer valve in the fuel transfer i
chute equalizer line in order to fill completely the upper portion of the fuel transfer chute with borated water from the shield tank cavity.
hh, Make several trial runs with a new fuel element for final check of operability of fuel h:ndlirg system in wet conditon.
h5. Check TV for underwater operation.
h6. Position and turn on underwater lights. Lights must not be turned on until submerged in water.
h7. Remove head and store in allotted position.
a.
Ms.nipulator crane must be in extreme south position b.
Reactor centerline position for polar crane is marked with balck paint on primary shielding, bridge and trolley
1 706E2 8 1/11/62 Date Completed
, Initials h8. Remove guide tube hold down plate and hold down ring using plate and' barrel lifting fixture.
a.
Install 2 levels on plate and barrel lifting fixture b.
Install air hose and control valve on lifting fixture c.
Use lifting fixture in proper orientation as marked on guide holes d.
Store plate and ring on internals stacking plate
'd. Remove h guide tube support plate plugs and store in rack.
a.
Three section boom is required to be on manipulator crane. For details of installing third boom section, see Instruction Book, FUEL HANDLING AYSTEM USMC, Page 61 b.
See rack elevations taken previously 50 Remove one guide tube.
a.
So section boom is required on manipulator crane, For detail.s of removing third section, see Instruction Book, FUEL HANDLIN3 SYSTEM, USMC Page 61 b.
For operation of Universal Tool, see Instruction Boc'.cs, Fuel Handling System, USMC, Page 62, UNIVE' GAL HANDLING TOOL, West. Page 3h c.
See elevation data tchen on installation of first core d.
Maintain positive identification of guide tubes i.e., reccrd core positions and rack positions
- 51. Remove one unsupported drive shaft.
a.
Two section boom is required on manipulator crane b.
See Instruction Books, FUEL HANDLING SYSTEM, US}C, Page 63, UNIVERSAL HANDLIN3 TOOL, West.
Page 26, 27, 36 c.
See elevation data taken on installation of first com
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506E2:9 1/11/62 Date Completed Initials d.
Maintain positive identification of drive rods, i.e. record core positions and rack positions
- 52. Repeat above two steps until all 2h guide tubes and drive shafts have been removed.
- 53. Remove guide tube support plate and store on top of guide tube hold down plate, with plate and barrel lifting fixture observing levelness and proper orientations (during removal.).
$h. Retract in-core instrumentation thimbles from fuel elements. See Instruction Book, IN-CORE INSTRUMENTATION, west. Page 29. Welding called for on locking tool See Instruction Book, IN-CORE INSTRUMENTATION, West. Page 19.
- 55. Ready the upper core support barrel with attached core support plate and contained in-core instru-mentation structure for renoval.
NOTE: Use plate and barrel lifting fixture observing levelness and proper orientation, longer slings may be required for this operation.
- 56. Fill the shield tank cavity to the upper level limit.
- 57. Remove charging pumps from main coolant loop pressure maintenance service and establish water level equilibrium between shield tank cavity, pressurizer and steam generator through pressurizer and loop drain lines.
- 58. Momentarily shut down flow in the shutdown cooling system while doing Step 59 below to avoid cocking of upper core support barrel by hydraulic pressure.
- 59. Remove upper core support barrel with attached core support plate and contained in-core instrumentation structure.
)
506E2810 1/11/62 Date Completed Initials 60 Disengage polar crane hook leaving lifting fixture attached to core barrel.
- 61. Remove control rods, fuel assemblies, and shim rods as described in MI 506Eh,
- 62. Inspect lower core support plate using portable viewing equipnent.
- 63. Install vessel radiation specimens.
6h. Replace control rods, fuel assemblies, and shim rods as described in 506Eh.
- 65. Replace upper core support barrel containing upper core support plate and in-core instrumentation.
(Make momentary shutdown of shutdown cooling system while lowering into place).
- 66. Insert in-core instrumentation thimbles into fuel assemblies. See Instruction Book.
IN-CORE INSTRUMENTATION West. Page 32
- 67. Replace guide tube support plate using plate and barrel lifting fixture.
- 68. Replace 1 drive shaft.
(If the drive shafts are to be reused, they must be replaced in the core location from which they were taken.
- 69. Replace 1 guide tube en the unsupported drive shaft. The guide tube must be replaced in the core location from which it was taken.
70 Repeat above two steps until all 2h drive rods '
and guide tubes are placed in the vessel.
- 71. Replace h guide tube support plate plugs. 3 section boom of manipulator crane is required.
72 Replace guide tube hold down plate using plate and barrel lifting device.
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506E2:11 1/11/62 Date
' Completed Initials a.
The tool requires installation of air hose and control valve b.
Care should be taken not to damage gasket grooves in any way 7h. Clean gaskets grooves with a plastic nosed underwater pipe water jet.
75.
Place new head gaskets into grooves using gasket tool.
- 76. Replace reactor vessel head in its original orientation.
77.
Turn off and remove underwater viewing lights and viewing equipnent.
78 Drain pressurizer and refueling water from shield tank cavity complying with M.I. No. 506E3, REACT 3 REFUELING-SHIELD TANK CAVITI - FILL AND DRAIN, Section V-B.
CAUTION: Check radiation and contamination level of shield tank cavity prior to personnel entry.
- 79. Dewater the upper portion of the fuel transfer chute, remove ring and replace with solid plate.
- 80. Drain the dewatering system.
- 81. Decontaminate tools, equipment and shield tank cavity, when necessary, by scrubbing and flushing.
- 82. Lower necessary vessel head replacement equipment and tools from the charging floor to the reactor level.
- 83. Remove head lifting fixture mark legs 3 for future identification.
8h. Remove guide studs and stud hole plugs. Clean and dry stud holes as required.
506E2:12 1/11/62 Date Completed Initials
- 85. Install reactor head studs. See B&W Instruction Book, Page h-5.
- 86. Install Conoseals, using gasket seals only -
Do not weld. See Instruction Book, DI-CORE INSTRUENTATION.
- 87. Fill and vent main coolant system in accordance with 0.I. No. 50hD1, PJdN C001 ANT SYSTEM -
FILLING AND VENTIIG OF COMPIETE SYSTEM.
88 Leak test pri: nary system complying with M.I. No.
506B3, PRIPARY PLANT - COLD LEAK TEST.
- 89. Lower pressurizer water level to below Conoseals.
(This step may not be necessgry if Conoseal gaskets are tight).
90 Weld Conoseal seal caps.
Larger diameter seal weld may be done by the a.
AMF machine or by hand.
b.
Smaller diameter seal weld will,be made by hand.
- 91. Install thermocouple junction assemblies and flux wire tubes.
See Instruction Book, IN-CORE INSTRUMENTATION, Page 22.
- 92. Refill and Vent Main Coolant System (OI 50hD1).
93.
Install top hat air duct and baffles.
9h. Install reactor head thermal insulation.
- 95. Rep 3 ace shielding.
- 96. Install cable tray on north side of cavity and position manipulator crane on north side of cavity with boon to west of cable tray.
97.
Install south cable tiay.
- 98. Install rod drive air supply ducts.
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j 506E2:13 1/11/62 4
Date Completed Initials 99.
Install coil stacks.
100 Install coil stack cables.
101. Install equipr.ent hatch cover.
V.
Final Conditions 1.
The reactor has been refueled and reassembled for operation.
2.
The complete main coolant system has been leak tested and is ready for normal startup from cold condition. Refer to 0.I.
No. 50hDh, MAIN C0gLANT SYSTEM - STARTUP OF COMPLETE SYSTM.
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MAINTENANCE IN RUCTICN NO. 506Eh EEACTOR REFUELING FUEL AND CONTROL RCD REPLACEME!U I.
Objec';ive To provide a safe and efficient method for replacing fuel assemblies, control rods, and shim rods during Core.I refueling.
C II.
Conditions
- = -
rs 1.
MI 506E2, Preparation of Reactor Systemt for Refueling, is
- g. M,],g; completed through step 60.
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In addition to the public address system, 3-way sound powered
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phone communications have been established between the control center, the shield tank cavity manipulator crane, and the spent fuel pit.
3.
Two of the charging pumps are in ready standby condition for addition of concentrated boric acid to the pressure vessel when-ever the reactor vessel head is removed.
h.
A channel for continuous gamma monitoring is installed near each manipulator crane whenever spent control rods or spent fuel assemblies are being handled.
II'_.
Precautions 1.
At least two of the three channels of nuclear instrumentation must be in operation whenever the core geometry is being changed.
One channel will be equipped with a high count rate alarn which will sound both in the control center and in the Vapor Container.
2.
The shield tank cavity water must be sampled at 16ast once a day and analyced for boron concentration to assure that the minimum shutdown boron concentration of 1150 ppm is maintained.
3.
A record of the neutron count rate before and after any change in core geometry must be maintained at the control center and the manipulator crane operator notified of any significant changes in count rate.
h.
At least one AEC licensed person shall be present at the control center at all times, and at least one AEC licensed person shall be in the vicinity of the fuel handling system whenever fuel is being moved. At all tines there shall be one AEC licensed person fr
b.
L 506Eh:2 i
1/11/62 designated as being in overall charge of operations. Normally, this person will be the Shift Supervisor.
5.
If an unexpected increase in the count rate by a factor of two on two of the three channels occurs after addition of a new fuel assembly or removal of a control rod, the fuel loading operation will be sus-pended until the situation can be reviewed by plant technical super-visory personnel. If necessary to establish the shutdown margin of the core, a single control rod will be withdrawn using the manipulator crane and regulated by a plot of control rod position versus inverse count rate multiplication. Using the inverse count rate data obtaincd in this manner, the shutdown margin will be calculated.
If these calculation indicate that there will be less than 5% A K/K shutdown with all control rods inserted in the fully loaded core, the boron concentration will be increased to provide the required 5%
8 K/K sh tdown margin.
6.
Foreign material must be prevented from falling into the reactor vessel while refueling and no unauthorized or unnecessary personnel (or objects) are to be allowed on the manipulator crane.
7.
All personnel should limit their time in the vicinity of the fuel chute when a spent fuel element is in or passing through the chute as radiation levels can possibly reach 100 mr/hr.
i IV.
Operating Instructions The detailed instructions and operational check off are prepared l
in the form of a book 'of index file cards which detail the steps to be performed in removing and inserting each core element. A core element is considered to be either a control rod, shim rod, fuel assembly, or source vane.
There will be a separate card for each core position which details the steps involved in removing and inserting the core element in that position. The operator will note on the card the completion of each step so as to maintain an up to date record of the operation as it progresses and to provide a final record of the disposition of all spent, as well as new core elements.
The general sequence of performing the refueling is as follows:
1 After reactor internals are removed and stored as outlined in MI 506E2, prepare to replace core elements.
2.
Selected control rods will be removed, one at a time, fran the core for inspection. Coupling will be measured and the absorber section checked with the underwater boroscope for distortion and
So6Eh:3 1/11/62 surface condition, Drive shafts and absorber seccions will be reused or replaced depending on the results of these inspections.-
3.
Unload the spent fuel from one quadrant-of the core following the operating instructicns for renoval of a fuel element from reactor to storage pit as outlined in USMC Instruction Book, Pages h7-57.
(Two to eight old fuel assemblies may be left in the core to achieve higher burnup of these elements. If left in the core, these elements will be visually inspected for crud buildup and structural integrity, using the boroscope and underwater TV viewing.) Selected control rods may also be unloaded from this quadrant if required for improved visibility of the structural materials.
h.
Inspect sources for structural integrity using boroJc0pc and underwater TV viewing equipment.
5.
Inspect the lower core support plate in the quadrant which was unloaded using the boroscope and TV.
6.
For moving new fuel elements from the storage pit to the reactor, follow instructions in USMC Instruction Book, Pages 57-58 7.
Should a fuel element be damaged to the extent it will not fit the fuel chute or should the normal fuel handling systems become in-operative such that repair requires unwatering of the shield tank cavity, place the fuel element into the damaged fuel element container. Remove the fuel elenent to the spent fuel storage pit via the shipping hatch using the polar and yard cranes.
8.
Should a spent fuel element become stuck in the fuel chute, the design of the chute and its dewatering system is such that no immediate acticn is required by the operater. Accessible areas adjacent to the chute should be checked for high radiation levels, and posted and barricaded as appropriate.
NOTE:
The most crf.tical condition would be with the element in the wait pocition and the lower lock valve stuck closed.
The operator would be unable to recognize this cond3 tic until the following actions had been completed:
a.
Equalizing valve closed b.
Upper portions of the fuel chute pumped cut c.
Attempt made to open the valyc Since the fuel clement under the above condition will be covered with only a small isolated volume of water, the equalicing valve should be opened immediately after as-certaining that the lower lock valve is in the stuck closed position.
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506Eh:h
.1/11/62 1
9.
The remaining core elements will be unloaded and replaced in-i dividually in a sequence that will effectively rotate the open quadrant so that other portions of the lower core support plant j
can be inspected as desired.
(New assenblies will be added to one side of the quadrant and. spent assemblies renoved from the other side.)
- 10. Load the remaining assemblies into the open quadrant until.the core is completely refueled.
- 11. Recheck all index file cards with the Reactor Engineer for accountability and completeness.
12 Reinstall internals in accordance with MI So6E2.
V. Final Conditions The reactor is ready for assembly of remaining internals and preparation for cold startup according to steps 59.-92 of MI So6E2.
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