ML18113A549
| ML18113A549 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/09/1978 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR 518, NUDOCS 7810120034 | |
| Download: ML18113A549 (38) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RrcHMOND,VIRGINIA 23261 October*9, 1978 Mr. Victor Stello, *Jr.; Director Division of Operat~ng Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
- 20555 Serial No. 518 PO&M/DLB: scj Docket. Nos. *. 50...:280 so...:281 License Nos.
DPR--3t.
- DPR-3T.
SUBJECT:
MOVEMENT.OF.HEAVY LOADS NEAR*sPENT'FUEL
Dear Mr. Stello:
This is in.response to your letter of June 12, 1978 which requested*
information r.egarding the* movement of.heavy loads.near spent fuel.
The**
information requested* for Surry Power* Station Unit Nos. 1 and 2, is in-cluded in the attachments.
FollowiitJ~is a list of the* attachments
- Movement of Heavy Loads 'Near Spent*Fuel~
Surry Power Station Unit Nos.* 1 and 2 (9.*pages)
Surry FSAR Drawings FSAR Figure 15.* 1-3 FSAR Figure 15.1-4 FSAR Figure 15.1-5 FSAR Figure '15.1-6 FSAR ~igure 15.1-7 FSAR ~igure 15.1-8 FSAR Figure 15.1-9 FSAR Figure 15.1~14 FSAR Figure 15.1-15 Figure 1: Fuel Handling Tools Figure 2:
Irradiation Specimen Shipping Cask, Model BCL~4
~igure 3: *Irradiation Specimen Shipping Cask, Model BMl-1
e v1*Horn1A EL~cTRrc AND PowEH CoMPANY To *Mr~ Victor Stello, Jr*., Director.
- PROCEDURES:
Enclosures*
MMP-C-RC-039, Removal and Installation of Upper Internals (t pages with 1 page.attachment)
MMP-C-RC-040, Installation and Removal of*Head Lifting ~ig
- (3 pages* with 1 page attachment)
OP-4.18 Movement of Transfer Canal Door (3
- P.ages)
- Very* truly yours,*
. 'Zf;' ):?2, ~t?,1!1 /1 ja/
C.
- M. S tall1:ngs Vice President-Power* Supply and Production Operations
e MOVEMENT OF HEAVY LOADS NEAR SPENT FUEL SURRY POWER STATION UNIT NOS. 1 AND 2 The following information is provided in response to a request from the Nuclear Regulatory Commission dated June 12, 1978.
Information Requested
- 1.
Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.
Response
Attached are the following diagrams from section 15 of the Surry FSAR.
L. Machine Location Reactor Containment, EL. 47'4", (FSAR Figure 15.1-3).
2; Machine Location Reactor Containment, EL. 18'4", "(FSAR Figure 15.1-4).
- 3.
Machine Location Reactor Containment, EL. 3 1 6 11,
(FSAR Figure 15.1-5).
- 4.
Machine Location Reactor Containment EL. 27'7", (FSAR Figure 15.1-6).
- 5.
Machine Location Reactor Containment, Vertical Section Sheet 1, (FSAR Figure
- 6.
Machine Location Reactor Containment, Vertical Section Sheet 2, (FSAR Figure
- 7.
Machine Location Reactor Containment, 15.1-7).
15.1-8).
Vertical Section Sheet 3, (FSAR Figure 15.1-9).
- 8.
Fuel Building Arrangement, Sheet 1, (FSAR Figure 15.1-14).
- 9.
Fuel Building Arrangement, Sheet 2, (FSAR Figure 15.1-15).
Note that the fuel building drawings do not reflect the installation of higher density spent fuel racks which was completed in the spring of 1978.
Details of the new spent fuel storage racks were submitted in our Request for Operating License Amendment dated March 27, 1977 (Serial No. 186).
- l.
...:2-
~Information Requested
- 2.
Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool.
For each object listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying height) and the frequency of movement.
Resoonse
- Following is a list of objects which are moved over the reactor core or the spent fuel storage pool during refueling.
The objects are listed in the approximate order in which their movement occurs during the refueling process; A general description of the refueling procedure is given in Section 9.12 of the Surry FSAR. The Surry units are currently on an 18 month refueling interval.
- 1.
Reactor Vessel Head The reactor vessel head is lifted by the containment polar crane.
Its movement path includes a vertical rise of approximately 40 feet from its initial position, a horizontal movement of approximately 40 feet and a vertical descent* of* approximately 100 feet to the reactor.head,storage area.
The movement path can be seen on FSAR Figures 15.1-7 and 15.1-3.
The size and shape of the reactor vessel head is shown on FSAR Figure 15.1-7.
The weight of the reactor vessel head is approximately 250,000 lbs.
- 2.
Reactor Vessel Upper Internals The reactor vessel upper internals are removed from the vessel by the polar crane and placed in the "Upper Internals Lifting Rig Storage Area".
This involves a vertical lift of approximately 25 feet and a horizontal motion of approximately 15 feet.
The reactor vessel upper internals weigh approximately 85,000 lbs.
The upper internals are de-scribed in Section 3~0 of the Surry FSAR.
- 3.
Fuel Handling Tools A variety of fuel handling tools are used during the core alteration process in the containment *or in the fuel building.
In the containment, movement will be between core locations and/or the fuel upender and/or the RCC change fixture.
The locations of these components are shown on FSAR Figures 15.1-4 and 15.1-7.
In the fuel building, movement will be between the upender and/or fuel storage locations and/or the new fuel elevator.
These tools and their approximate weights are listed below, Sketches of these tools are included in Figure 1.
- 1.
Spent Fuel Assembly Handling Tool, 350 lbs.
- 2.
Thimble Plug Handling Tool, 235 lbs.
- 3.
Burnable Poison Rod Assembly Handling Tool, (two types):
mechan-ically operated type, 610 lbs; air operated type, 800 lbs.
- Thegreatest total weight carried over the fuel during the fuel handling process is as follows:
Fuel Assembly Spent Fuel Handling Tool Rod Cluster Total Weight 1470 lbs.
350 lbs.
150 lbs.
1970 lbs.
In the containment, at the highest point during fuel movement, the bottom of the lifted fuel assembly will be approximately 18 feet above the top of the installed fuel assembly.
In the fuel building, at the highest point during fuel movement, the bottom of the fuel assembly will be approximately 7 feet above the top of the stored fuel *assemblies.
- 4.
Reactor Irradiation Sample and Sample Handling Tool.
In accordance with our Reactor Vessel Radiation Surveillance Program, at approximately 10 year intervals, reactor irradiation sample assemblies are removed from the vessel for examination and testing.
The sample assemblies are approximately 10 feet long, 1 1/4 inch square in cross section *and weigh approximately 25 lbs.
To remove the sample, a specimen handling basket is placed in the fuel upender in the fuel building.
The upender is then transferred to the containment and placed in the upright position.
The sample assembly is then removed from the vessel using the Irradiation Sample Handling Tool, and placed in the specimen basket.
The specimen basket and irradiation sample are then returned to the fuel building for storage in the spent fuel racks.
The irradiation sample will then be shipped for analysis.
Weights of these components are as follows:
- 1.
Irradiation Sample Assembly, 25 lbs.
- 2.
Specimen Handling Tool*~ 240 lbs.
- 3.
Specimen Handling Basket, 251 lbs.
- 5.
Core Mapping Equipment Following core alterations a T. V. camera and video-tape equipment are used to verify the proper location of fuel assemblies.
The*,camera,;.;reighsapproximately 10 lbs. and is suspended less than 1 foot.
above the fuel during the mapping process.
- 6.
Irradiation Specimen Shipping Cask The irradiation specimen is shipped to the test laboratory in a shipping cask provided by the laboratory.
At the present time, the laboratory services and shipping casks are provided by the Battelle Memorial Institute.
The casks used are model numbers BCL-4 and BMl-1.
Sketches of these casks are included in Figures 2 and 3.
The BCL-4 cask weighs approximately 13,000 lbs.
The BMl-1 cask weighs approximately-22,550 lbs.
- e An irradiation sample shipping cask is never carried over spent fuel.
,rt is lowered into the spent fuel shipping cask area of the spent fuel pit.
- 7.
Transfer Canal Door At the spent fuel pool end of each fuel transfer canal is a transfer canal door.
These are ma*rked "Gate" on FSAR Figure 15.1-14.
The weight of the canal door is approximately 3800 lbs. Prior to refuel-ing, the units transfer canal door is removed from the canal position and transferred either to the other units canal or to the gate storage posi-tion.
This requires carrying the door over the southern most row of fu~l storage positions.
Administrative controls prohibit the movement of the door over spent fuel.
Additionally the spent fuel positions will be utilized in such an order that the southern most row will be the last filled.
Information Requested
- 3.
What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?
Response
The spent fuel cask(s) which will be used to ship fuel from Surry Power Station have not been selected at this time.
Information Requested
- 4.
Identify any heavy load or cask drop analyses performed to date for your facility.
Provide a copy of all such analyses not pre-viously submitted to the NRC staff.
Response
A spent*'fuel cask *drop 1 analysis has been performed for Surry* Power Station by Nuclear Energy Services, *Inc. (NES).
However, the NES analysis is limited in scope and has not been completely reviewed or accepted by Vepco.
For this reason, the results of the analysis pre considered preliminary.
Accordingly, no copy of the.analysis has beE!n enclosed.
Where results of this analysis are referenced herein, theywillbe identified as preliminary.
Information Requested
- 5.
Identify any heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved.
Identify what equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc.),and discuss the feasibility of such an accident affecting this equipment.
Describe the basis for your conclusions.
Response
Maintenance activities requiring the movement of heavy loads would generally occur only during the cold shutdown condition.
At that time,
- only the residual heat removal system is necessary to maintain the plant in a safe shutdown condition.
Operation of the RHR system requires elec-trical power and the supply of component cooling water to the RHR heat exchangers.
The possibility of a heavy load accident which would render the RHR system inoperable is negligible for the following reasons.
- 1.
The locations of the residual heat removal system and other equip-ment are shown in the attached reactor containment machine location drawings.
The location of the RHR system is most clearly shown on Figures 15.1-6 and 15.1-9.
Generally, a heavy load would be in motion for; (1) movement for access (as with removable slabs), (2) removal to an open area for ease of maintenance, or (3) removal from or entry to the con-tainment via the equipment hatch.
A review of the reactor contain-ment machine location drawings will show that all postulated acti-vities of this type for all components can be accomplished without carrying the load over the area of the RHR system.
- 2.
As required by Surry Power Station Technical Specification, all main-tenance activities which could affect reactor safety are procedural-ized and reviewed by the Station Nuclear Safety and Operating Committee.
This review ensures the *consideration of all. implications of the move-ment of a heavy load and the selection of a safe movement path.
Information Requested
- 6.
If he*avy, *loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could 11.esult in water leakage severe enough to uncover the spent fuel.
Describe the basis for your con-clusions.
Response
In addition to the items and movement paths listed in the response to item 2, the spent fuel shipping cask is moved over the east end of the spent fuel pool.
The spent fuel shipping cask is not moved over spent fuel. It is lowered into the spent fuel shipping cask lay down area as shown on FSAR Figures 15.1-14.!& 15.
The NES study addressed the consequences of cask drop accidents for a wide variety of casks.
In the worst type of accident for the heaviest cask available, the report concluded that," ***
there will be a moderate amount of local and overall damage to the spent fuel pool floor; however, there will not be any gross structural failure of the pool floor.
Loss rate of pool water through the cracked concrete pool floor resting on a soil foundation is difficult to estimate, but it is expected that an adequate pool water level can be maintained with a modest makeup capability."
As explained below in response to item 8, a substantial makeup capability exists.
Thus, preliminary results for the heaviest cask, worst accidents are acceptable.
Note that this conclusion is for the heaviest available cask, which is not necessarily the cask which will be used at Surry.,
The eventual selection of a spent fuel shipping cask will be based on numerous considerations including the results and implications of the NES study.
The cask
- e selection will be such as to preclude a handling accident which could re-sult in a water loss severe enough to uncover spent fuel.
Accordingly, we conclude that a handling accident which could result.in water leakage severe enough to uncover the spent fuel is not feasible.
Information Requested
- 7.
Describe any design features of your facility which affect the potential for a heavy load handling accident involving spent fuel e.g., utilization of a single failure-proof crane.
Response
The following design features minimize the possibility of a heavy load handling accident involving spent fuel.
- 1.
The spent fuel pit cooling and purification system components are located west of the fuel pool and at low levels in the fuel build-ing.
These components as well as new fuel containers are handled by the new fuel crane and monorail as shown in FSAR Figure 15.1-
- 15.
Therefore it will never be necessary to move these components over the stored spent fuel.
- 2.
The motor driven platform is** the only* crane which travels* over the spent fuel.. The'only objects which are carried by. this crane.are new*and spent fuel, the irradiation sample ba_sket::cind specimen, and the transfer canal door.
- 3.
The 125 ton capacity spent fuel shipping cask crane is on its own trolley such that it cannot carry a heavy load directly over spent fuel.
- 4.
The Spent Fuel Handling Crane was manufactured by Harnischfeger, Inc. It is a 125 ton capacity, seismic Class A, and meets Electric Overboard Crane Institute Specification No. 61.
The crane capacity exceeds the weight of the heaviest cask considered by approximately 25%.
A motor brake capable of holding 200 percent motor torque is provided.
The brake will hold the load when the motor is deenergized.
Information Requested
- 8.
Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refuel-ing,* the spent fuel* storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.
Response
Enclosed are copies of the following procedures:
- 1.
OP-4.18, Movement of Transfer Canal Door
- 2.
MMP-C-RC-039, Removal and Reinstallation of Upper Internals
- 3.
MMP-C-RC-040, Installation and Removal of Head Lifting Rig
- A general refueling procedure is given in Section 9.12.5 of the Surry FSAR.
The detailed refueling procedure is not included because it is of great length and, in regard to heavy loads, simply refers to the above listed procedures.
No procedures have been developed for the,;. movement and use of the spent fuel shipping cask.
Information Requested Q.
Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Rev1sion 1, December, 1975) regarding Spent Fuel Storage Facility Design Basis.
Response
A discussion of Surry Power Stations compliance with Regulatory Guide 1.13 follows, with responses numbered as in the Regulatory Guide, section C.
Regulatory Position.
- 1.
The spent fuel storage facility, including structures and equip-ment, is designed to category I seismic requirements.
- 2.
As stated in Section 15.2 of the Surry FSAR, Table 15.2.1-1; the design criteria for the fuel building pool and structure are as follows.
The fuel building reinforced concrete structure is designed to withstand tornadic winds and horizontal missiles generated by tornadic winds.
This design ensures that there will be no sig-::
nificant loss of watertight integrity due to tornadic wi.nds or missiles generated by such winds and will prevent missiles generated by tornadic winds from contacting the fuel within the pool.
- 3.
The motor driven platform is the only crane which travels direct-ly over spent fuel.
The motor driven platform and cranes are in use only,during refueling. operations.-. For,this, reason-*inter-locks would -serve _no purpose~*
,:*,;;,:I
- ,. '! (*1 1
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.. 'rhe spent fuel shipping cask crane is located such that, if the crane failed, the cask could tip over on stored fuel.
As explain-ed in.the response to position 5 below, the.cask tipping._accident has been analyzed.
Preliminary results of the cask tipping acci-dent are discussed under item 5*on.page 8.
- 4.
The fuel building ventilation system provides heating to inhibit the build-up of condensation, high efficiency filtration,tci reduce the possibility of clouding of the spent fuel pit and an excess exhaust flow to maintain a negative pressure in the fuel building for inward leakage.
Exhaust from the fuel building is through -
the common iodine filter bank of two filter assemblies, each con-sisting of roughing, absolute and charcoal filters.
This nega-
' e tive pressure and filter arrangement limits the potential release of radioactive iodine and other radioactive materials.
The de-sign of the fuel building ventilation and filtration system is based on the assumption that the cladding of all the 'fuel rods in one fuel bundle might be breached.
The inventory of radio-active materials available for leakage used for our analysis was developed prior to the adoption of Regulatory Guide 1.25.
The assumptions used to derive the radioactive materials inven-tory for our analysis were more conservative than required by Regulatory Guide 1.25.
- 5.
As discussed in our response to Information Request Items _2 and 3, there are no operational activities which require the movement of heavy loads over the stored spent fuel.
Surry Technical Speci-*
fications prohibit the movement of heavy loads over spent fuel.
As shown in the drawings provided, the spent fuel cask!handling crane is prevented by design from positioning a heavy load direct-ly over spent fuel.
As explained in our response to Information Request Item 6, based on preliminary analyses; :the_ Surry spent fuel pool can withstand, without leakage that could uncover the fuel, the impact of the heaviest load to be carried by the crane from the maximum height to which it can be lifted.
The arrangement of the fuel building is such that, while the spent fuel cask cannot drop directly on the stored fuel, the cask could drop to the pool floor and then tip over to come in contact with the fuel.
This type of incident was analyzed in the NES analysis. *The preliminary analysis indicates that an accident of this type will cause some permanent damage to the fuel storage cell, however, the fuel storage rack will maintain its structural integrity.
- 6.
All.piping systems connected to the fuel storage pool are located such that a piping system leak can reduce the water level in the pool to only 4 ft. below normal since at that elevation,the water level is below the pipe penetrations in the pool wall.
This mini-mum water level ensures at least 20 ft. of water over stored fuel.
- 7.
One level monitoring instrument is installed which audibly alarms in the main control room if the water level drops to approximately 6 inches below normal level.
There is no local alarm.. This in-strument is not cal"ibrated on a regular schedule.
A fuel building radiation monitor is installed which alarms in the main control room in the event of high radiation levels.
Additionally, since the fuel building exhaust is through the vent-ilation vent system, a high activity in the fuel building would also activate an alarm on the Ventilation Vent Radiation Monitor.
Neither of these radiation alarms activates any secondary func-tion.
However, since both monitors alann in the main control room, the unit operator would take whatever corrective action is required, including, if necessary, adjustments in the ventila-tion and filtration flow paths.
The radiation monitors are e
checked daily, functionally tested monthly and calibrated on *.a refueling interval.
- 8.
The normal make-up to the spent fuel pool is from the primary grade water/boric acid blender on either unit.
A separate 2" supply line is available directly from the primary grade water supply pumps discharge.
In addition, the station fire system can also be used to supply the:~pent fuel pool.
All of these supplies are of seismic Category 1 design.
The estimated makeup rates for the three available supplies are as follows:
Normal Makeup Direct for PG System Fire System
~ ' 100-150 gpm 100-150 gpm 1500-2000 gpm As explained above~* the*preliiniriary task drop analyses for the'.worst case acc:iden t:, indicates** that some' Teakage :. would occur requiring a moderate" makeup c1:1pability~* *. The three available water supplies should:*be more than sufficient' to*maintain an adequate water level in 'the *event of such leakage.
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SCM.t: 1**1'*0° C,[NERAI. t.lOTca.t / un~(W(;.t ~~-
FUEL BUILDING A RRANGEMENT,SHEET 2 SURRY POWER STATION
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lRRAuIATION.SAHPLE HAHDLl NG TOOL.
42 FT L'.lt1G rnrnnLE PLUG JIJ\\NOLING TOOL 29 fT LOtlG
,, l BURNABLE POISON ROD nEHOVAL TOOL
- FLlEL HANDt..lNG-TOOLS SPEITT. FUEL ASSEHnLY IIANDL I HG TOOL 32 FT LONG e
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l?rJ:!i0ocl1*1r. ~-!'Jkr,,:il Sl11p;,i"*J C,viloi:i-:r studs FIGURE 3 *
'HTIALS DATE e
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CORRECTIVE MAINTENANCE PROCEDURE FOR REMOVAL AND REINSTALLATION OF UPPER INTERNALS MMP-C-RC-039 12-15-76 Rev*. 2 MR/fo --------
- _ 1.0.*
Purpose 2.0 3.0 1.1
- The purpose of this procedure is to provide instructions for the removal and reinstallation of the*upper. internals.*
References 2.1 W Drwg. 685J724 Internals Lifting Rig - Ring Support
- 2.2 W*Drwg.. 685J725 Internals Lifting Rig Spreader.
2.3 W Drwg. 685J726 - Internals Lifting Rig Sling *.
t:. *~!...
685J727'-
2.4 W Drwg.
Internal's Lifting Rig.: - General*Assy.
- i.:.
Initial Conditions 3.1:
Reactor shall be in cold shutdown ctindition~
-.~-~.
i **
- 3. 2
- RCC element drive shafts unla.tched~
3.3 *, Initiate., a;' &intenance Rep~rt.
3.4 3.5 3.6 3.7 Initiate a Radiation Work Permit *.
The lifting rig has been clea;ed :a:O:d-inspected.
- Polar*crane certification is valid.
Load cell'certification is valid.
3~8 Notify QA Department.
3.9 l1eet *the requirements of Attachment l> Part I.
Precautions NOTE: -- -A-charged fire extinguisher must_ J:>e at :the scene of any welding, burning, or open flame heating operations. -The
- Supervisor of the task sho~ld use his.discretion and assign an additional attendant. termed " a* firewatch" if the above ____ __
ignition sources are to be employed in or in close proximity to areas*vital to plant and public safety.
INITIALS 1-.*..*.
DATE 4.0 Prec~ions (continued) e 4.1 Comply with VEPCO Accident Prevention Manual.
4.2 Tools & equipment used must be kept clean.
MHP-C-RC-039 1<e*;;. 4 AUG 2 :5 137cl 4.3 Radiation levels at surface of water in refueling cavity must be continuously monitored.
4.4 The support ring pin brackets must be bolted in the lower set of holes.
4.5 Care must be exercised not to damage the load cell.
5.0 Instructions (QA) 5.1 Removal of upper internals.
5.1~1. Install Measuring Device on manipulator crane bridge railing,.;
5.1.2 Marchmark mounting device on manipulator crane bridge railing *.
5.1.3 Move manipulator crane over reactor vessel and mark exact bridge location on selsyn hammer
.and pointer
.or mark as appropriate on crane track.
5.1.4 Lower measuring tape until plumb bob rests on upper internals package~
5~1.5
- Q.A... Hold -
Record tape measure reading __ __.Ft. __ _.In.
5.1.6 Return tape measure to full up position.
5.1.7 Move manipulator crane away from reactor vessel.
5.1~8 Remove measurir.g device from manipulator crane br~dge railing.
5.1. 9 Connect the upper portion of the sling assembly, which includes the load cell, to the main crane hook of the polar.crane by inserting the top pin through the sling assembly side plates and the hole provided in the hook.
~HTIALS
- DATE 5.0 POS. 1 ----
20S. 2 ----
POS. 3 ----
POS. 1* ----
POS. 2 ----
POS. 3 ---'--
e 12-15-76 Rev. 2 5.1.10 Lower the upper portion of the sling over the rig, placing the lower load cell adaptor between the two lugs on the rig.
Insert the connecting pin by use of the pull rod assembly which is attached to one of the top lugs.
When the pin is properly positioned>
tighten the lock nut.
5.1.lL. Raise the rig carefully until it clears the upper internals storage stand, then proceed to the reactor vessel.
Ensure that the path from the storage stand to the reactor vessel is clear.
5-.1.12 Lower the rig over the reactor vessel guide studs until each of the lower tube assemblies are resting flush with*
the upper internals support plate and support ring pin brackets are properly p~_sitioned over the reactor vessel
- - alignment pins.
- 5. L.13.: Disconnect the upper portion ~f the sl.ing
- assemb.ly from
.. the rig by removing the connecting pin with the aid of the pull rod assembly.
- NOTE:
The.thread engagement of the torque tube assembly should be"' 3".
Both of the following threading operations should ~e done with care as the protective ring rods and torque tube assemblies are spring loaded.
5.1.14. Lower the mechanism handling tool over the protective*
ring connection rod, then discqnn~~t t~e ring by rotating
. the tool in 'the counterc.1.oskwise direction until the rod..
is disengaged from the ring.
5.1.15 Raise the tool until it clears the protective ring rod>
then lower. the tool over the torque tube assembly.
With a cloc~-wise rotation of the tool, thread the torque tube assembly into the internals until a firm fit is obtained.
NITL\\LS DATE 5.0
- Continued MMP-C-RC-039 12-15-76
").\\ev.2.
- 5.1.16 When the preceding steps have been completed for each of three locations, install the upper portion of the sling assembly by placing the lower load cell adaptor between the top lugs on the rig and inserting the con-necting pins. Tighten the lock nut* on the pull rod assembly when the connecting pin has been pr~perly positioned.
5.Ll7 NOTE:
The indicated load should not exceed the combined weight of the support structure a,nd lifting device
- by more than.10% or a total of 104,000 lbs. During the removal and transporting of the internals, moni-tor the load cell at all times for a sudden load increase which would indicate an interference. If this occurs, cease operations, determine the cause then remedy before proceeding *.
Slowly raise the internals from the reactor vessel until the guide stud brackets on the rig support ring are approximately twelve inches above the guide studs.
- Record total load indicated on.load cell --------'--
5.1.18 Proceed with the internals to the upper internals storage stand~
When the proper orientation of the rig with the
- stand guide studs is* obtained, lower the internals onto the stand ensuring that they seat properly. -
. 5.1.19
- Disconnect the upper portion of the sling assembly by::
- removing the connection pin with the pull rod Job Completed By --------------
Date --'--------------
I~~.
tNITIALS
- DATE
>OS. 1 ----
'OS *. 2 ----
OS. 3 -,----
- e 5~2 Installation of Upper Internals
}JMP-C-039 12-15-76 Rev. 2 5.2.1 Conne~t the upper portion of the sling assembly, which includes the load cell, to the main crane hook by inserting the top in through the sling assembly side plates and the hole provided in the hook.
- 5. 2. 2 Position the upper portion of the lifting sl.ing over
- the upper internals lifting rig. *. Attach to the lifting rig by inserting the connecting pin, using the pull rod assembly and tightening the lock nut.
5.2.3 Slowly raise the internals from the upper internals.
storage stand.
Proceed with the internals to the reactor vessel.
- Ensure th~t the path from the storage stand to the reactor vessel is clear.
NOTE:
During the transporting and installation of the internals, monitor the load cell at all times for a sudden load increase.which would indicate an interference.
Tf this occurs, cease operations, determine the cause then remedy before proceeding.
The indicated load should not exceed the*combined weight of the support structure and lifting device by more thanl0% or a total of 104,000 lbs *
. 5.2.4. Slowly lower the upper internals with lifting rig assembly over the guide studs and into the reactor.vessel until the internals are seated.
5.2.5 Disconnect the upper portion of the sling assembly from*
the rig by removing the,-connecting pin with the aid of the pull rod assembly.
5.2.6 Lower the mechanism handling tool over the torque tube assembly:.: *. With a countercloskwise rotation of the tool, unthread the torque tube assembly from the** tapped hole in the upper internals.
- .--1ITL<\\LS
'OS. 1 "OS. 2 -
OS. 3 -
- DATE 5. 2.ontinued e
.MMP-C-RC-039 12-15-76
.Rey. 2 5.2.7 Lower the mechanism handling tool over the protective ring connection rod> then connect the ring by rotating the tool in the clockwise direction until the rod is connected to the ring.
5.2.8 Attach the upper portion of the lifting sling to the lift~ng rig by inserting the connecting pin and tight-eining the lock nut.
5.2.-9 Slowly raise the lifting rig from the reactor vessel.
NOTE:
Observe the protective ring is being lifted.
Observe the upper internals.:remain.T.in position indicating complete disconnection_.
Verify with the load cell.
5.2~10 Raise the lift;ing rig clear of the guide studs and transport the lifting rig to the upper internals storage stand.
- 5. 2.11 Disconnect the upper portion of t!ie lifting sling by..
loosening the lock nut and connecting pin.
- 5. 2 ** 12 Transport the upper portion of the sling and the load cell. to.storage area. :
(Q.A.)
5.2.13 Install measuring device within matcbmarks on manipulator crane bridge railing.*
5~2Z14 Move manipulator crane to selsyn readings as noted in Step 5.1.3.
5~2.15 Lower measuring.tape until plumb bob _rests *on upper internals.package.
- ~ ;*
In.
5.2.16 Q.A. HOLD - Record tape measure reading Ft.
This reading should be within+/-~ in. of the reading recorded in Step 5.1.5~
DH'FIALS /UAT E e
5.. 0 Instructions (continued) flMP-C-RC-039 Rev. /;4 HR{f ------
AUG 2 3 1973 I
- 5.2.17 5.2.18 Return tape to full position.
___./ __ _
___./ __ _
___ / __ _
___ /_. __ _
Remove measuring device from manipulator crane bridge railing.
6.0 Post Maintenance Checkout 6.1 6.2 Clear }Iaintenance Report.
Clear Radiation Work Permit.
V Meet the requirements of Attachment 1, Part II.
Job Completed By: ---------
- Date: --------
APPROVED Jiy,*~
- . c~ StonNuckaisafety and Operatin omm*ttee,,-
,;JI~-*
.. !:~
RECOMlfilID APPROVAL:
.If/,
~
"~~~---------------
REVIEWED BY:
DATE:
LIST OF EFFECTIVE REVISIONS SECTION 1.0 2.0 3.0 4.0 5.0 6.0 ATTACHlIENT 1 DATE 12-15-76 12-15..:76 12-15-76 12-15-76 AUG i ~ 1978 12---15-76 05-19-77
.r
.. -r.**
IHITI.ALS ZOHE. I PART I 05-19-77 React (when Reactor Vessel i en or head is bein~ removed).
Before starting and during the course of the job.
A.
Suitable trash containers, such as poly bags or metal containers are at the job site.
B.
Combustible materials have _been removed from the area if burning or welding*
operatious are to be performed.*
C.
Clean and di-rty areas for storage of materials have been set_ up.
D.
Accountability records (logs)for personnel and materials have been set*upo E.
The surrounding equipment is adequat_ely protected.
F.
Installati-on of plugs,. caps or tethering of tools shall be used to prevent.
foreign material from entering the system.
G~
Large items that will not be reused shall be removed o:c-0.temporary storage provided..
- The housekeeping requirements *shall-be periodically checked by either *.**
First Line Supervision or Q.A **
.. ';** -~.
I *.
Provisions have been made for the draining or collection of Radioactive
- Fluids.
PART.II After the completion*of the job.
- --~-.
- _IAI..
5
_ !I:: Insure ;.,,,,,val\\/~~ mat~rial,-from the system prior to Closing out the
... ~.-*-::**
- ~ ;~_;,
- )_*.
- ::'.,(/t:*- system.-:.* :'. *
. :~
. All unused materials have been ~emoved~-:
- __.. -~.- /~-~-... -~.
.:. ' *i-_~-:-
- " ~. *-....
~
- C.
Equ/pment<and tools h~ve.be~n-removed.
Use log to ins~re* accountability
. _'")~
D..*.*. :e ~~::o::l:::t::::::::~ne:: have ~:~n removed.
. g)v~1~1j The Radioactive Fl~fd. collection containers or draining ~quipm~~~ have '.:}:{?Ari;
- nf:::v;:~ site clean up and/or decon has been performed.
'J~~
E *.
F.
DATE
.. ~- :*.
M.HP-C-RC-040
- 12~15-76 Rev. 2 MR# ------
1.0 VIRGL~L~ ELECTRIC AND POWER CO}fP/ili'Y SURRY POWER STATION.
CORRECTIVE MAINTENANCE PROCEDURE FOR.
INSTALLATION AND REMOVAL OF HEAD LIFTING RIG Purpose 1.1 lhe purpose of this procedure is to.provide in~tructions for the installation and removal of the head. li£ting rig sling.
2.0 References 2.1 - W Drwg 685-J-548 Head Liftin~ _Rig - Sling. -
2.2*
W Dn.g 685-J-545 -
Head Lifting.Rig - General Assy.
3.0 Initial Conditions 3.J/
Reactor *i.s at cold shutdown condition.
.. ~-...
3.2:
Lifting, rig has been clean~d-and inspected.
3.3 Initiate-a Maintenance Report.
3.4 - *_ Initiat:e:a Radiation Work Permit.**
3.5 Notify Q.A. Department.
-3_.6 Ueet the-requ:irements of"'Attacbment 1~ Part I.
4.0 Precautions-NOTE:_ - A char_ge.d fire;-extinguisher must be at the-.scene of any welding~ burning or open flame heating operations.
The Supervisor of the task should use his discretion and assign
.an additional attendant termed "a firewatch" if the above ignition-sources are to be employed in or in close proximity "to areas vital to plant or publi~ safety *.
4.. 1
-Comply *with.VEPCO Accident _Prevention Manual.
INirLU.S, DATE H'
5.0 e MMP-C-RC-040 12-15-76 gev. 2 5.1 Installation of head lifting sling.
5.1.1 Verify that l~" jaw and jaw turnbuckles are attached to the legs of the tripod.
5.L 2 Attach the main hook of the polar crane to the tripod utilizing the load cell attachments.
5.1.3 Lift the tripod assembly and position it over the reactor vessel centerline using the polar crane.
5.1.4 Remove the cotter keys, jam nuts and pins from the tripod legs.
5.1.5 By raising/lowering with the. p9lar crane, align the tripod legs with* the head lifting_ lugs_..
5ol.6. Insert pins, jam.nuts,..a)ld cotter key&-.
5.1. 7 Release turnbuckles ~rom tripod legs..:.
Job Completed BY: --------------
Date: --------------
5.2 Removal of the nead lifting_rig sling" 5~2.l Attach l~" jaw and j_?'w turn'l:iuckles. to the, leg_s. of.
5.2.2 5o2.3
- the* tripod with lockwell pins.
Remove cotter keys and* Jam.nuts from-the pins at the
- bottom of the.tripod,,
Jog the polar crane uoward*
to take the slack out of the trip,od and drive the pins out G At. this point it may be.,
- necessary to ad}ust.the turnbuckles to put outward pressure on the tripod legs in order to take the 1oad off the pins and/or raise or lower *the plant crane by jogging.
5.2.4 When the pins are removed operate the turnbuckles in conjunction with raising the trip_od with the polar crane in order to clear the clevises from *the support *1ug. ___ _
5.0
~nstr.ions (continued)
Move tripod to storage position.
t-JNP-C-RC-040 11-16-77 MR.if ----'----
5.2.5 5.2.6 Reinstall pins, jawnuts,and cotter keys on the tripod legs.
6.0 Post Maintenance Checkout 6.1 Clear Maintenance Report.
6.2 Clear Radiation Work Permit *.
6.3 Meet the requirements of Attachment 1, Part II.
Job Completed By: ---------
Date: ----~----
. APPROVED BY:
FL- --/ ~
RECOMMEND APPROVAL:._....:.d,__:_'-=-~--==~~-~---** __ _
DATE:
//§t;;/?J 7
Chairman, Station Nuclear Safety and Operating Co!Ilfilittee DATE: //4/72 I
REVIEWED BY: __
z;-_"">_2f!-
~-*--~..;..*-=---------
. QUALITY. ASSURANCE ENGINEER DATE : __
J_l-+f-(_0__,__/_7_7 LIST OF EFFECTIVE REVISIONS SECTION..
1.0 2.0 3.0 4.0 5.0 6.0 ATTACHMENT 1 DATE 12-15 12-15-76 12-15-76 12-15-76 12-15-76 11-16-77 05-19-77
I>
- P--G,,
",J INITL<\\LS INITIALS ATTACHMENT -1 NMP-C-RC-40
,a A
"05-19-77 ZONE III*-
Fue:9..iilding, Containment, *safety -ated Work Areas.
Before starting and during the course of the job.
A.
Suitable t:;ash containers,. such as poly bags or metal containers are at-*** -
the job site.
B.
Combustible materials have been removed from the area if burning or welding operations are to be* performed.
C.
Clean and dirty areas for storage of materials have been set up especially when working on Safety Relat;ed Systems*.*
D.
Clear exterior surface of components {ree of forei~ ~ebris:,- especially Boric Acid Residue.
E.
Establish accountability log for control of tools and equipment entering the clean area if a possibility exists that this material might inadvertantly enter any system.
F.
The surrounding equipment is adequately-protected.
G.
Installation-of plugs~. caps> or tethering of tools shall be* used to prevent*;*:"
foreign material from entering systems.
n.-
The housekeeping requirements shall be pei*iodical;Ly checked by eiither First Line Supervision or Q.AQ P..ART II After the completion of. the job.
B.
- c.
D.
. :i_;:*i);~::<tti.,\\:***._.
Insure removal.of all material from the* system~ '(tank,
. to closing.*out:.* the-s,s_tem. *.
"All unused matei~*:1!~1e~~ ~::n removed.
Equipment arid t~*~Jti1:;~~ been remov~d.,-...
In~ure a~~oU1"1t~b*~r£~1:t~:'._al{\\o*ols. a~d equip~ent upon their ra:;:~l by use of a log designated* for that purpose.
-:- :.. -. :~:~{:-:*,.
E.
The trash collection* containers* have been removed __.
F.
The final job. site. cl~n up and/or decon has. been performed.
. *~-.
--:=.-** _
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- '\\
r r.L VIRGINIA ELECTRIC AND POWER COMPANY SURRY POHER STATION UN IT NOS. 1 & 2 MOVEMENT OF TRANSFER CANAL DOOR*
1.0 Purpose To provide the necessary instructions for the movement of the
.Transfer Canal door in the Spent Fuel Pit.
2.0 Initial Conditions 2.1 Updated Spent Fuel Pit Map available.
3.0 Precautions and Limitations 3.1 T.S. - 3. 10.A. 10 OP-4.18 7-20-78 A **** *.heavy loads exceeding 110 percent of the weight of a fuel assembly_(not including fuel handling tool) shall not be moved over spent fuel, ****
INITIALS.,-
2 - -
4.0 Instructions 4.1 Initial Conditions satisfied.
4.2 Precautions and limitations noted and satisfied.
4.3 Obtain an updated map of the Spent Fuel Pit.
4.4 Lay out a route for the movement of fhe Transfer Canal door.
NOTE: Move spent fuel within the SFP as necessary.
4.5 Using properly sized rigging equipment, raise & lower door a few inches to test hoist brakes.
OP-4.18 7-20-78 4.6 Carefully ~~ve the Transfer Canal door along the predetermined path.
,Completed By: ----------------
oa.te: ----------------
7-20-78 APPROVED BY:~
Chairman, Station Nuclear Safety and DATE:pe~~
RECOMMEND APP RO VAL : __ lL'*"-"w~.=c...~j)=-_S__:....~--""------
DATE: [1 -I f -7 p-LIST OF EFFECTIVE SECTION 1.0 2.0 3.0
4.0 REFERENCES
TECH SPECS REVISIONS DATE*.*.
7-20-78 7-20-78 7-20-78 7-20-78
... ~.