ML19347C479
| ML19347C479 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/25/1975 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-75-111, NUDOCS 8011190582 | |
| Download: ML19347C479 (11) | |
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Pg osed Chang No. 131 Telephons 617 366-90ll TwX 7s0 390-0739 YANKEE ATOMIC ELECTRIC COMPANY
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September 25, 1975 i,o
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Attention: Office of Nuclear Reactor %egulatIBn A/
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Reference:
(a) License No. DPR-3 (Dock'ht $oi.25.0.-29)
(b) P: : posed Change No.112 submitted January 3,1974.
Dear Sir:
Pursuant to Section 50-59 of the Commission's Regulations, Yankee Atomic Electric Company hereby requests to make the following changes:
PR0p0 SED CHANGE: Reference is made to Section 218:3 of the Final Hazards Su= mary Report. We propose the following:
" Replace the existing 40 and 26 element spent fuel storage racks with anodized aluminum fixed-poison (Boral) curtain racks which have a reduced center-to-center spacing and a maximum capacity of 285 assemblies. This increased capacity is made possible by the presence of fixed neutrca absorbing material which compensates for the effects of the reduced spacing.
The 110 element rack, which has a maximum capacity of 106 spent fuel assemblies due to physical limitation in the four corners, will be maintained in the pool and used for storage of fuel having a minimum burnup of 20,000 MWDh!TU. This change brings the total storage capacity to 391 spent fuel assemblies.
REASON FOR CHANGE:
A study has been made to assess the ability of the existing spent fuel storage capacity to accommodate the present refueling schedules through 1982. This study became necessary due to the projected non-availability of adequate spent fuel reprocessing facilities through that year. The results of the study show that a significant increase in storage capacity is required to enable the Yankee Nuclear Power Station to continue normal operation through 1982 and maintain an adequate storage margin for unforeseen refueling requirements.
DESCRIPTION OF CHANGE: The present spent fuel racks will be replaced by an anodized aluminum support structure, to which are attached, by welding,
,o 8011190 E M l -
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United States Nuclear Regulatory Commission September 25, 1975 l
Attn: Office of Nuclear Reactor Regulation Page Two l
sheets of poison curtain material consisting of a minimum of 35 percent by I
weight of natural B G in a type 1100 aluminum alloy matrix (hereaf ter g
referred to as Boral). The Boral core is.084 inch thick and is clad on both sides with a.050 inch nominal thickness,(.040 inch minimum) of type 1100 aluminum alloy. The Boral parts are scaled, by welding, in the aluminum weldments which form the storage cavities to effectively seal the Boral matrix and prevent direct contact with the fuel pit water. The materials and fabrication processes are essentially the same as those i
used in the Boral spent fuel rack presently in use at the Yankee Nuclear i
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Power Station, which has performed well for a period in excess of 10 years for storage of spent fuel.
Figure 1 shows a typical 45-assembly spent fuel module which is identical to the 30 and 35 assembly modules (also part of the proposed installation) except for the number of assemblics. Rack construction consists of five fabricated aluminum cavities welded together via lead-in structure above and fuel support structure below. These sub assemblies are then co=pletely anodized for maximum corrosion resistance and finally bolted to one another to form the desired number of storage assemblies per module.
The cavity structures used in this design consist of square, concentric 5052-H32 aluminum tubes which extend above and below the stored fuel element. The void between the two tubes contains the Boral poison curtain parts on all four sides. The ends of the poison curtain void 'between the two tubes are closed and sealed by velding. Thus spent fuel pool water does not come in contact with the boron carbide core of the Boral rinimizing corrosion in this area. The strips of Boral in the' four sides of the cavity structure, form a neutron absorbing envelope completely surrounding the fuel.
This poison curtain evelope extends beyond (above and below) the active fuel and is permanently welded into the rack structure.
Thus, the poison curtains are an integral part of the basic rack design and are not subject to dislocation or removal, deliberate or inadvertent. All welding used in rack fabrication is done in accordance with the guidelines and applicable requirements of ASME Boiler and Pressure Vessel Code Section IX.
An additonal design basis which will be met is the requirement that the spent fuel racks as installed be able to maintain proper spacing and structural int igrity af ter being impacted by a spent. fuel assembly dropped onto any location from a height of 6 inches above the top of the racks.
In order to provide adequate assurance of uniform minimum B C 4
density, a quality control program is in effect which includes random sampling of the Boral plates during production and destructive examination of these sample sections for proper material density.
The performance of aluminum in borated, slightly acidic water (pH 5.5-6.0) such as that of its intended environment is excellent.
Industrial experience has r,hown that aluminum has excellent compatibility with boric acid and is used extensively in boric acid processing plants.
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United States Nuclear Regulatory Commission September 25, 1975 Attn: Office of Nuclear Reactor Regulation Page Three In order to provide additional conservatism in this regard, the aluminum structure will be anodized to more effectively passivate the material.
Criticality calculations have been performed to verify the sub-criticality of the new racks. A number of conservative assumptions were used in this study, including the following:
235
- 1) Fresh 4.5 w/o U Fuel.
ii) Minimum center-to-center spacing and boron content and thickness in the Boral Sheets.
iii) No soluble poison in the pool water nor fixed poison in the fuel
- assembly, iv) No axial or radial leakage from the rack.
v) Calculations were done at the most reactive pool temperature anticipated (68 F).
vi) A calculation uncertainty of 3%Ap was added to all results based on Monte Carlo calculations and the analysis of critical experiments.
The calculations were performed using a 4 energy group, X-Y representation of the racks in the PDQ-07 program. The accuracy of this representation was verified by comparison with KENO-II, Monte Carlo calculations.
The resulting K effective of the fully loaded new racks, including calculaticnal uncertainty, is 0.796, well below the proposed limit of.90.
To acco==odate any fabrication variations, calculations have been done leaving out one of four Boral sheets in one direction between each row of fuel assemblies.
Including calculational uncertainties, this case yielded a K effective of.834 The existing 110 assembly Boral rack was reanalyzed using the more conservative assumptions and calculational techniques currently employed.-
As a result of this reanalysis, we are proposing the 20,000 MWD /MTU minimum burnup limit on fuel stored in this rack. With this limit, the K, for the existing 110 assembly rack is.809 for the nominal case w2bhcalculationaluncertainties. The design case which is equivalent to leaving out one sheet of Boral curtain in the rack, produces a K,ff of 0.865, again well below the proposed limit of 0.90.
Depletion of the Boral sheet through capture of neutrons in boron was found to be much less than 1% over the estimated life of the racks and was therefore considered negligible.
The Spent Fuel Pool Cooling System heat rejection capability was determined from the original design analysis. The heat load resulting from the presence of additional spent fuel assemblies is within the capacity of
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(
l United States Nuclear Regulatory Commission September 25, 1975 j
Attn: Office of Nuclear Reactor Regulation Page Four i
the existing cooling system. These additional spent fuel assemblies include
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one full core beyond the anticipated refueling schedule.
The critical spent fuel pool heat load or. curs after normal refueling sequences absorb spent fuel storage space so that the unusual discharge o( a full core of fuel completely fills the storage capacity of the pool. This condition produces i
a heat load 2% less than that used in the original design of the cooling The thermal analysis to determine this value used minimum components.
realistic but adequately conservative time histories for irradiation and thermal decay of the stored fuel. Thus, the maximum bulk pool water temperature is less than 130 F for the expanded storage capacity.
Since poison curtain fuel storage racks completely enclose the stored fuel preventing horizontal cooling flow to the hot, center bundles in the pool; a thermal hydraulic analysis was conducted to verify that all assemblies would receive adequate cooling water via natural circulation to preclude boiling. This thermal hydraulic analysis utilized the RELAP-4*
computer code program to model a selected row of fuel assemblies stored in the new racks. Included $n the model were the assembly, downcomer region, pool, and fluid friction losses. For additional conservatism, all bundles were considered to be generating the maximum possible decay heat rate which is considerably greater than the actual peak heat i
generation rate resulting from the refueling cycle.
Inspection Program for Maintenance of Structural Integrity In order to provide continued assurance of structural integrity, special control samples of the Boral sheet and a section of structural-aluminum will be placed in the Spent Fuel Pool in a readily accessible location to permit easy receval. Periodically over the next five years, these samples will be removed from the pool and examined visually.
Their condition will be evaluated and appropriate corrective measures instituted, if required.
Final Hazards Summary Report (FHSR)
The existing description of the spent fuel storage facility is modified as indicated. Replacement FHSR pages are provided:
Section 218:3, paragraph 1 change to read:
"The fuel transfer pit contains nine fuel storage racks.
These consist of one 110 element capacity rack, three 30 element capacity racks, three 35 element racks and two 45 element capacity racks.
The 30, 35 and 45 element racks are fabricated of 6061-T6, 6063-T5 and 5052-H32 aluminum alloy.
The center-to-center spacing of the fuel stored in these racks is 11.00 inches.
The active portion of each assembly has Boral sheets fixed on each side for reactivity control. The Keff has been calculated to be.796, with unirradiated, 4.5% enriched uranium fuel stored in the racks. The Boral used in these racks h:s an.084 inch thick core which consists of-35% by weight of B C in an aluminum matrix. This Boral is sealed in cavities integral to g
the aluminum rack structure."
United States Nuclear Regulatory Commission September 25, 1975 Attn:
Office of Nuclear Reactor Regulation Page Five Section 218:3 paragraph 2 change to read:
"The 110 ele =ent rack is also fabricated of 6061-T6 aluminum and provides for storage of fuel in an oblong array with a center to center spacing of 8.78" x 9.5".
The active portion of each assembly is enclosed in a boral sheath for reactivity control. The boral is made up of 35 weight percent B C in an alu inum matrix, clad with aluminum on all sides.
g This rack is li=ited to the storage of fuel with a minimum burnup of 20,000 WD/MTU. The K with the restriction."* " has been calculated to be 0.806 for this rack Section 218:3 paragraph 3 change to read:
"A phased installation or relocation of the equip =ent described in the two preceding paragraphs is planned. During the installation period, a combination of these poison curtain racks and the original 40, 26 and 110 element racks will be used to store spent fuel."
Replacement page 218:3 and Drawing No. 9699-FM-21A, Rev. 13 for the FHSR, and page 9.1-1 of Reference b, Section 9.12, for the FSAR are attached.
SAFETY CONSIDERATIONS: The spent fuel storage facility has no effect on plant operation or protection. The facility serves as a storage facility for spent fuel prior to shipment for reprocessing. The proposed installa-tion replaces the existing racks with those of equivalent design as previously discussed. The area to be used for locating a spent fuel cask is unchanged by this storage modification. The cask is lowered through the roof hatch into its designated location without passing over existing fuel or racks. Thus, no change to the safe operation of moving a spent fuel cask is incurred by this change.
In the event of the loss of primary spent fuel pool forced cooling circulation the shut down cooling system can be cross connected to the spent fuel pool to provide the necessary cooling flow. The large volume of spent fuel pool cooling water allows a time of more than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> from design temperature to saturation te=perature in which to make the necessary change.
An estimated two hours is required to accocplish this change in the plant.
The reduced spacing of the new racks affects K effective calculations and cooling system heat load. The selection of material requires evaluation of corrosion aspects within the pool environment. All of these aspects have-been addressed in this submittal.
Based on the consideration herein, it is concluded that there is reasonable assurance that operation of the Yankee Nuclear Power Station with these Spent Fuel Storage Facility modifications will not endanger the health and safety of the public. This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
~ __.
United States Nuclear Regulatory Commission September 25, 1975 Attn: Of fice of Nuclear Reactor Regulation Page Six 1
SCHEDULE OF CHANGE:
The new spent fuel racks will be installed on a j
phased basis. Once the initial phase is complete, an increasing capacity is provided which is consistent with the normal refueling cycle and has the capability of storing an additional full core.(76 assemblies) at l
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any time through 1982.
Prior to the October, 1975 refueling outage, one of the new design rack modules will be installed, which will result in an increase in storage capacity of 45 spent fuel assemblies.
In the event the installa-tion of the first 45 cavity racks.is delayed, it will become necessary to temporarily add five extra cavities to this assembly. Additional phased increases are planned periodically during subsequent refuelings until the full change is effected which enables storage of a maximum of 391 spent fuel assemblics. The replacement of existing racks on a phased basis will be accomplished utilizing written procedures.
We trust the information provided is adequate.
If additional data is required, please feel free to contact us.
i Very truly yours.
YANKEE ATOMIC ELECTRIC COMPANY D. E. Vandenburgh Vice President C05:0NWEALTH OF MASSACHUSEITS)
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COUNTY OF WORCESTER
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Then personally appeared before ne, D. E. Vandenburgh, who being duly sworn, did state that he is 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 Company and that the statements therein are true to the best of his knowledge and belief, hob
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Armand R. Soucy Notary Public My Commission Expires September 9, 1977 t
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218:3 6/1/64 (Revised 8/75)
The fuel transfer pit contains nine fuel storage racks.
These consist of one 110 element capacity rack, three 30 element ' capacity racks, three 35 element racks and two 45 element capacity racks.
The 30, 35 and 45 element racks are fabricated of 6061-T6, 6063-T5 and 5052-H32 aluminum alloy. The center-to-center spacing of the fuel stored in these racks is 11.00 inches. The active portion of each assembly has Boral sheets fixed on each side for reactivity control.
The K.gf has been calculated to be.796, with unirradiated, 4.5% enriched uranium fuel stored in the racks.
The Boral used in these racks has an.084 inch thich core which consists of 35% by weight of B C in an aluminum matrix.
This Boral is 4
sealed in cavities integral to the aluminum rack structures.
The 110 element rack is also fabricated of 6061-T6 aluminum and provides for storage of fuel in an oblong array with a center to center spacing of 8.78" x 9.5".
The active portion of each assembly is enclosed in a Boral sheath for reactivity control.
The Boral is made'up of 35 weight percent B C in an aluminum matrix, clad with aluminum on all sides.
4 This rack is limited to the storage of fuel uith a minimum burnup of 20,0001%D/MTU.
The K has been calculated to be 0.806 for this ff rack with the restrict, ion.
I A phased installation or relocation of the equipment described in the two preceding paragraphs is planned. During the installation period, a combination of these poison curtain racks and the original 40, 26 and 110 element racks will be used to store spent fuel.
The design of the racks allows insertion of fuel assemblies ~only in the prescribed storage channels in the rackt.
The fuel transfer pit is provided with a cooling and purification system.
This removes.the decay heat given off by the spent fuel assemblies in storage and prevents the buildup of radioactivity and boric acid in the fuel pit water. The 500 gpm fuel transfer pit cooling pump circulates the water between the pit and a heat exchanger maintaining the water temperature under 130 F.
The uater is also circulated by the same pump through a 20 cu. ft. ion exchanger. The fuel transfer pit cooling pump may also be used to unwater the fuel transfer pit.
Fuel Transfer Pit Manipulator Crane The crane is composed of a trolley mounted on a bridge which in turn rides along rails set in concrete at the top of the fuel transfer pit. A rotating turret is mounted on the trolley.
The turret supports a rigid tool boom which cannot rotate relative to the turret. The stainless steel tool boom is provided with a grappling tool which will engage the top cnd of a fuel assccbly, control rod or control rod follower.
The boom is raised and lowered by means of a rack attached to the boom, meshing with the pinion gear output of a motor driven gear mechanism.
In order that the crane operator can accurately positior. the tool boom over the laydown mechanism in its vertical position, positive stops
.I are placed on each of the main crane rails.
The crane'is visually indexed by scales and pointers to enable the operator to position the boom accurately over the storage racks.
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218:3a 6/1/64 (Revised 8/75)
A height indicator is used to indicate the height of the tool boom.
The indicator consists of a ecchanically driven revolution counter, arranged so that indicating dials are visual to the operator. The crane bridge and trolley notors cre alternating current wound rotor type, operated with drum controllers (440 v, 3 phase, 60 cycles).
The tool, boom ho st motor is a d
direct current cotor supplied by a motor generator' set driven by a 440 v a-c totor and is operated by drum controllers.
The capacity of canipulator crane is 6000 lb.
The maximum vertical boon travel is 16 ft - 10 in.
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{j s.s uWW CllApTER 9 AUXILIARY Sig1.:*.MS 9.1 Fuel Storare and Handling 9.1.1 New Tuel Storage Ne-' fuel assenblies are removed from the shipping containers and stored in the r.eu fuel storage vault shown in Figure 9.1-1.
This concrete block building is located outside of the vapor container adjacent to the fuel transfer pit.
General access to the new fuel storage vault is gained through a 14 ft by 5 ft wide steel plate door located in the north wall of the building.
The storage vault is designed to receive and store 96 new fuel assemblies.
l The racks in which the assc=blics are stored are arranged in 4 parallel The center to center distance between assemblies is 14 in, which rows.
gives a surface to surface spacing of 6.3 in. between assemblics.
The spaci.7g of the racks is so arranged to avoid any chance of criticality.
Tne K of this arrangement would be approximately 0.8 even uith the u
vault *cc pletely flooded. New control rods and shim rods are stored in their shipping containers within the new fuel vault.
9.1.2 Spent ruel Storage The fuel transfer pit, outside of the vapor container, is designed to store fuel asse:blies, control rods, control rod followers, and shim rods under rater after removal from the reactor. In addition, the fuel transfer pit contains the equipment necessary to complete the functions of the fuel handling system outside the vapor container.
The fuel transfer pit contains nine fuel storage racks.
These consist of one 110 elctent capacity rack, three 30 element capacity racks, three 35 elerant racks and two 45 element capacity racks.
The 30, 35 and 45 ele:ent racks are fabricated of 6061-T6, 6063-T5 and 5052-H32 aluminum alloy.
The center-to-center spacing of the fuel stored in these racks is 11.00 inches.
The active porticn of each assembly has Boral sheets fixed on cach side for reactivity control. The E has been calculated to be.796, with gg unirradiated, 4.5% enriched uranium fuel stored in the racks.
The Boral used in these racks has an.084 inch thick core which consists of 35% by weight cf L,C in an aluminum catrix.
This Boral is sealed in cavities integrz.1 te'the aluminum rack structure.
The 110 ele:ent rack is also fabricated of 6061-T6 aluminum and provides for storage cf fuel in an oblong array with a center to center spacing of 8.78" x 9.5".
The active portion of each assemlby is enclosed in a Boral sheath for reactivity control.
The Boral is made up of 35 weight percent E,C, is an aluminu= entrix, clad with aluminum on all sides. The rack is lleited to the storage of fuel with a minimum burnup of 20,000 15.'D/NTU. The K h s been calculated to be 0.806 for this rack with the restricticn.ff e
9.1-1 (Revised 8/75)
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c NRC DISTRIBUTION, FOR PART 50 DOCKET MATE'HIAL (TEMPORARY FORM)
CONTROL NO-
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FILE:
FROM: Yankee Ato ic Electric Co DATE OF DOC D ATE R EC'D LTR TWX RPT OTHER Westborough, l' ass.
D.E. Vandenburch 9-25-75 9-29-75 XXX TO:
ORIG CC OTHER SENT NRC PDR XXX SENT LOCAL PDR XXX tec 3 Simed 7'
CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-29 DESCRIPTION:
ENCLOSURES:
Ltr notarized 9-25-75.....trans the following.
Amdt to O/L Change to Tech Spec # 131(Propos6 Consisting of revisions to Tech. Specs with regards to spent fuel storage racks.....
(43 Copies Enclosure Received)
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