Text

High Density Reracking of Spent Fuel Storage Pool
	ML20237H120
Person / Time
Site:	LaSalle
Issue date:	08/31/1987
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20237H112	List: ML20237H109; ML20237H120;
References
	NUDOCS 8708240366
	Download: ML20237H120 (284)
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O United States Nuclear Regulatory Commission Docket No. 50-374 High Density Reracking of Spent Fuel Storage Pool La Salle County Station Unit 2 1

Report Submitted by Commonwealth Edison Company 1

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Attachment A Amended Pages to Spent Fuel Storage Capacity Modification Safety Analysis Report i

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La Salle County Station Unit 2 Commonwealth Edison Comoany August 1987

LSCS-2 AMENDMENT 1 AUGUST 1987

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_ Instructions for Updating Instructions for amending the La Salle Unit 2 Spent Fuel Storege' Capacity Modification Safety Analysis Report, Revision 8, August 1987 are as follows. Changes to the Safety Analysis Report are identified on the page by a vertical'line in the right margin and the amendment number i and date in the upper right corner. To update your report, remove the following indicated pages and insert the indicated pages.

Remove Insert Page 5-9 Page 5-9 Page 5-12 Page 5-12 Page 5-14 Page 5-14 i

Page 5-16 Page 5-16

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AMENDMENT 1 AUGUST 1987 TABLE 5.3.4-1

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STRESS

SUMMARY

ALLOW-STRESS SERVICE STRESS ABLE SAFETY COMPONENT TYPE LEVEL (ksi) (ksi) FACTOR SECTION 4.1 RACK WELDS 240 B-B SHEAR B 13.60 27.9 2.05 INTERNAL RACK WELD SHEAR D 19.15 29.06 1.52 (Fusion) BENDING B 2.30 19.1 8.3 BENDING D 3.05 28.8 9.4 240 C-C SHEAR B 20.10 27.9 1.38 INTERNAL RACK WELD SHEAR D 25.38 29.06 1.14 (Fusion BENDING B 3.4 19.1 5.6 BENDING D 6.4 28.8 4.5 180 C-C SHEAR D 17.86 29.06 1.63 INTERNAL RACK WELD BENDING D 4.52 28.8 6.37 (Fusion)

SECTION 4.2 PEDESTALS RACK BOTTOM PLATE TO BOX SHEAR B 22.50 27.9 1.24 O WALL (0.09" x 0.125" Weld) SHEAR D 27.50 29.06 1.05 PEDESTAL TOP PLATE TO RACK SHEAR B 19.62 27.9 1.42 BOTTOM PLATE ( " Weld) SHEAR D 25.11 29.06 1.15 PEDESTAL NUT COMPRESSION B 14.1 23.9 1.68 COMPRESSION D 16.3 36.0 2.20 UPPER PEDESTAL GUSSET COMPRESSION B 23.55 23.9 1.01 COMPRESSION P. 27.8 28.8 1.29 GUSSET WELD SHEAR 8 23.9 27.9 1.16 SHEAR D 28.3 29.06 1.025 1" THICK PEDESTAL PLATE BENDING B 12.04 23.9 1.98 BENDING D 13.87 28.8 2.07 THREAD (EXTERNAL) SHEAR B 8.84 9.87 1.11 SHEAR D 10.21 10.73 1.05 THREAD (INTERNAL) SHEAR 8 7.22 9.87 1.36 SHEAR D 8.34 10.73 1.28 O

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AMENDMENT 1 AUGUST 1987

d. T'a -- Temperature effects at the highest temperature L \ associated with the postulated abnormal design conditions. In the case of a spent-fuel storage {

pool, this would consist of a full core discharge j with the heat exchanger inoperable. The thermal- i hydraulic analysis concludes that the La Salle County Station - Unit 2 pool .will be heated to the boi'nq point in approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Therc.sre, the maximum temperature of the racks will be assumed to be 2400 F, the saturation temperature under 23 feet of water.

e. E -- Operating basis earthquake (OBE), replaced by UCBV per 305.12a of Reference 1 where UCBV is the loads generated by the service level B artificial acceleration time histo"y..

f. E' -- Safe shutdown earthquake (SSE), replaced by FCBV per 305.12b of Reference 1 where FCBV is the loads generated by service level C artificial acceleration time history.

9 Pf -- Upward force on rack caused by postulated ;

structural fuel assembly. Reference Page 3.8 of !

the Specification, " External Loadings" gives 1200 lb uplif t force due to fuel handling equipment O jamming or maloperation.

h. Fd -- Loads due to accidental drop of heaviest load f rom maximum possible height.

From NF-1200 (Reference 9), the racks and pedestals would be l considered as linear-type supports. NF-3143 states that linear-type supports shall be analyzed based on the maximum stress theory when elastic analysis is performed in accordance with the rules of NF-3300. This section states that when linear elastic analysis is performed, the allowable stresses are determined in NF-3320, which provides stress limits for design, and Level A service limits in Section NF-3322. For Level B and Level D, stress limits are to be increased by factors shown in Table NF-3523.2-1. Bearing type stress limits are excluded from the rules for Level D service.

The Level A service stress limits are summarized in Table 5.3.4.2-2. The f actors that need to be applied to the Level A limits to obtain the Level B and Level D service limits are given in Table 5.3.4.2-3.

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Table 5.3.4.2-3 AMENDMENT 1 AUGUST 1987

'O~ ELASTIC ANALYSIS STRESS CATEGORIES AND STRESS LIMIT FACTORS FOR CLASS 1,2, 3, AND MC LINEAR TYPE SUPPORTS DESIGNED BY ANALYSIS COMPONENT SUPPORTS Stress Limit Factors for Loading Categories (Note (1)]

Service Level Service Level Service Level Service Level Test Stress Category Design A B [ Note (2)) C (Note (3)] D [ Note (3)] Loadings Primary Stresses (Note (5)) K, = 1.0 K, = 1.0 K, = 1.33 K, = 1.5 K, = 2:0 K, = 1.33 -

K, = 1.0 K, = 1.0 K, = 1.33 [ Note (4)l K, = 1.5 (Note (4)1 K, = 2.0 [ Note (4)] K, = 1.33 (Note (4)l K, = 1.0 K,. = 1.0 K, = 1.33 K,. = 1.5 K,. = 2.0 K., = 1.33 but stress s but stress s but stress s but stress s 8/3 of critical a/3 of critical 8/3 of critical 8/ of critical buckling stress buckling stress buckling stress buckling stress Primary Plus Secondary Evaluation is required for critical buckling for all loading categories. The requirement of this Subarticle shall be met Stresses (Note (6)I for this evaluation.

Peak Stresses Evaluation not required.

NOMENCLATURE:

K, = stress hmit factor applicable to the Design allowable tensile and bending stresses K, = stress limit f actor applicable to the Design allowable shear stresses K., = stress limit f actor applicable to the Design allowable compressive axial and bending stresses to determine buckling limit j, NOTES:

(1) Control of deformation is not insured by these stress limit factors. When required by Design Specification, deformation control must be considered separately.

' (2) K , K,, and K., = 1.0 for deugn of snubbers.

<3) St.ess shall not exceed 0.75,,.

(al K, shall not exceed 0.425, .

% (5) For Service Levels A, B, C, and D, stresses induced by restr'unt of free end displacement and anchor motions of piping shall be considered as prumary stresses.

Lb) Thermal stre$ses Mthin the suc' port as dehned bv NF-312111 need not be evaluated. For Serv <e Levels A and B, primary plus secondary stre%es shall t>e hhted to a range of 25, or 5, at temper /thre, whiChever is less, a

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AMENDMENT 1 t

-AUGUST 1987 TABLE 5.3.4.5-1 ALLOWABLE STRESSES IN KSI i 1000 psi

.2400F TYPE OF STRESS LEVEL A- LEVEL B LEVEL D

a. Tension - membrane 14.4- 19.1 28.8

b. Tension - net section at holes 10.8 14.3 21.6

c. Shear - gross section- 9.6 12.7 19.2

'd. . Shear - weld base material 21.0 27.9 29.06

e. Shear - fillet weld throat 21.0 27.9 29.06

f. ' Shear - fusion weld 21.0 27.9 29.06

9. ~ Bending - tension / compression on 18.0 23.9 36.0 solid sections

. h; Bending - tension compression 14.4 19.1 '28.8 on rolled or built-up sections

i. ' Compression - bearing 21.6 28.7 N/A

j. Compression - bolt bearin9 N/A

k. Shear (Threads)

8.58 9.87 10.73

LEVEL A = 1.0 1 B= 1.15 h - For Bolts See Table 3225.2-1, Subsection NF D= 1.25J 5-16

i AMENDMENT 1 AUGUST 1987 i

(] 5.4 References i /

1. Specification for Spent Fuel and Special Storage Racks, La Salle County Station - Unit 2, Commonwealth Edison Specification No. T-3758 with Addendum 1 and Amendment 1, dated 8-01-86.

2. Seismic Analysis of the La Salle County Station - Unit 2, Phase I, Spent Fuel Storage Racks (86-01-00-0082 fpril 1986).

3. Criticality Analysis for la Salle County Station - Phase I, Spent Fuel Storage Racks (86-01-00-0007 April 1986).

4. Spent Fuel Storage Racks Fuel Box Crush tests Maximum Density Rack Design Typical PWR Fuel. Report and Calculation 90 7F 17.

5. Thermal and Hydraulic Analysis Report, Spent Fuel Storage Pool, La Salle County Station - Unit 2 (8601-00-0083 April 1986).

6. Blodgett, " Design of Welded Structures," The James F. Lincoln Arc Welding Foundation, 1966.

7. Rabinowicz, E., " Friction Coefficients of Water-Lubricated Stainless Steels for a Spent Fuel Rack Facility," Study performed for Boston Edison Co., November 1976.

g 8. Roarke & Young, " Formulas for Stress and Strain," fifth Edition, McGraw-Hill Book Co., 1975.

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9. ASME Boiler and Pressure Vessel Code,Section III, Subsection NF, Edition and Addenda in effect at date of contract; use 1989 Edition through Summer 1982 Addenda for Structural acceptance criteria.

10. ANSI /ANS 57.2, " Design Requirements for LWR Spent Fuel Storage Facilities at Nuclear Power Plants," 1980.

11. NRC NUREG 0800, Standard Review Plan, Section 3.8.4, "Other Seismic Category I Structures," Rev 1, July 1981.

12. NRC Regulatory Guide 1.124, " Service Limits and Loading Combinations for Class I Linear-Type Component Supports," Rev. 1. January 1978.

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Attachment B Responses to NRC 21 Questions in a letter from E. G. Adensam to D. L. Farrar dated November 2 8 ',' 1 9 8 6 w'ith l l

Enclosure A - Determination of No Significant Hazards Consideration and Enclosure B - Radiological Consequences La Salle County Station Unit 2 Commonwealth Edison Company I

O August 1987

LSCS-2

., i 1. Describe, in some detail, the procedure that will be used for (1)

\ removal of fuel assemblies from the present racks, (2) removal and disposal of the racks, (3) installation of the new high density racks and (4) loading the new racks with the presently stored spent fuel assemblies. The description should include, step by step, the. number '

of people. involved in each step of the procedure (including divers if they are found to be necessary), the estimated dose rates they will be exposed to, the times spent in the radiation fields and the estimated man-rem associated with each step or the operation.

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RESPONSE

The existing spent fuel elements in the Unit 2 spent fuel storage pool will be transferred underwater through the spent fuel cask pit and transfer canals to the Unit 1 spent fuel storage pool. Additionally, sources and radioactive equipment in the Unit 2 pool will also be transferred out.

There are two options for reracking operations, dry pool cr wet pool:

1. Dry Pool U After transferring spent fuel elements and stored radioactive items to the Unit 1 pool, the gate to the transfer canal will be closed and the Unit 2 pool l I

will be drained. The pool and racks will be monitored and decontaminated as required. The racks will be disassembled into their components: eggcrate assemblies, box beams, cross beams, shim plates, and end support brackets.

The components will be cut to convenient lengths before or after being lifted out of the pool by the reactor building bridge crane. The rack pieces will not be lifted over fuel elements. The rack pieces will be enclosed in plastic and prepared for shipment offsite in accordance with NRC requirements and CECO procedures. The pieces will be moved to the Unit 1 equipment hatch and down to the ground floor by the reactor building bridge crane.

2. Wet Pool l

After transferring spent fuel elements and stored radioactive items to the Unit 1 pool, the Unit 2 pool and racks will be monitored and decontaminated as p required. The racks will be disassembled into their components: eggcrate !

assemblies, box beams, cross beams, shim plates, and end support brackets I

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LSCS-2 using divers. The components will be cut to convenient lengths before or after being lifted out of the pool- by the reactor building bridge crane. The pieces will be monitored and decontaminated as required. The pieces will then be wrapped in plastic and prepared for offsite shipment in accordance with NRC requirements and CECO procedures.

The high-density spent fuel storage rack modules will arrive onsite on the carrier's trucks. Any necessary reinstallation examination by station personnel will be made before the rack modules are transported up the Unit 1 equipment hatch of the reactor building. The requirements for reactor building secondary containment will be maintained as the racks enter the reactor building.

The reactor building overhead bridge crane will raise the new rack modules to the refuel floor for interim storage, preferably along the east wall (see attached response to question 10C and Figure 10-2). The reactor building overhead bridge crane will move the new rack modules at an approximate height of 2 feet over the floor, except for obstacles where a height of approximately 6 feet above the floor is permitted, to the Unit 2 spent fuel storage pool and then lower them into the pool. When the high-density storage racks are in the pool and leveled, then the final checks and tests, if any, will be completed. If dry, the pool will be filled with clean demineralized water.

The Unit 2 spent fuel elements temporarily stored in the Unit 1 pool will then be transferred underwater through the spent fuel cask storage pit and transfer canals into the high-density spent fuel storage racks in the Unit 2 pool.

No divers are expected to be needed in the dry pool reracking operations. It is estimated that up to approximately twenty people at any one time will be working on dry pool reracking operations.

The estimated integrated exposure to the workers in removing the old rack components and installing the new rack modules in a dry pool is estimated at 5 man-rem whole body. The exposure to the extremities due to handling the old racks is estimated at an additional 4 man-rem. These values are a small fraction of the reported annual occupational radiation exposures at nuclear power plants.

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Divers are needed for wet pool reracking operations. The estimated whole body O exposure to workers is 10.0 man-rem, with 11.2 man-rem to the extremities.

These estimated exposures are based on Quad Cities reracking experience.

However, the Quad Cities reracking was performed with spent fuel, accumulated over many cycles, stored in the spent fuel pool. Consequently, the exposure for the La Salle Unit 2 reracking is expected to be considerably less than the exposure for the Quad Cities reracking. The advantages of wet reracking are reduced liquid radwaste operations needed to clean the pool and to clean and store spent fuel pool water and improved control of airborne radioactivity.

CECO is currently evaluating both options, i.e., dry pool and wet pool reracking. Factors in this evaluation include, but are not limited to, estimated radiological exposure to workers, estimated money cost, manpower, schedular constraints, potential interferences with other scheduled work, and plant requirements.

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LSCS-2 n 2. Identify the radiation monitoring systems that will be used, and indicate their locations in the spent fuel pool area. The monitoring V systems in question are those which are to provide a warning to the i personnel whenever the area radiation levels increase inadvertently to preset alarm trigger levels.

RESPONSE

The radiation monitoring systems that will be used are the four area radiation monitors (ARM) located on the refueling floor near column line 15. Instrument numbers and locations of these monitors are shown in UFSAR, Volume X, Drawing ;

M-25, Sheet 2. These monitors are equipped with local indicators and audible alarms. Two fixed continuous airborne monitors (CAM) and a portable CAM on the refueling floor will also be used.

In addition, for particular tasks which would have a potential for increased radiation levels, a representative from the Rad / Chem Department would be present to monitor dose rates. Rad / Chem monitoring is required and controlled by existing station radiological procedures.

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LSCS-2

3. It may be possible that the space between the spent fuel and inside concrete shield wall is reduced due to the proposed modification. If i this is the case, provide an estimate of the potential increase in the dose rate in occupied areas outside the spent fuel pool concrete

. shield wall.

RESPONSE

As stated in Subsection 5.3.4.6 of the spent fuel pool reracking safety analysis report, a 5.3-inch gap is present between the racks and the West wall of the pool and a 3.0-inch gap is present between the racks and the South wall of the pool after reracking. The spaces before reracking was at least 4 feet.

The spent fuel pool at La Salle County Station - Unit 2 has 6-foot-thick concrete shielding on the sides and bottom. After_reracking, the calculated dose rate at the sides will be 2.5 mrem /hr with 5-day-old spent fuel and 1 mrem /hr with 22-day-old spent fuel in the pool. For the first 2 weeks of a refueling outage, the dose rates in a few areas around the pool may be in the range of.1 to 2.5 mrem /hr. The areas affected are: the storage room south of I - the pool, access corridors west of the pool at floor elevations 807 feet 0 inch and 820 feet 6 inches, and the standby liquid control system area east of the pool at floor elevation 820 feet 6 inches. The effect on personnel exposure is expected to be negligible.

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/" 4.- Provide a summary estimate of the projected changes in environmental doses resulting from the spent fuel pool modification. The estimates should include annual, as well as total plant life doses. Also include an estimate of the potential amount of K-85 and H-3 released

'due to additional fuel being stored in the spent fuel pool. ,

RESPONSE

The potential increase in the releases'of Kr-85 and H-3 are expected to be small, because the additional spent fuel stored in the new racks will be old fuel. The calculated environmental doses from station releases are reported in FSAR Appendix I and are seen to be very small fractions of the 10 CFR 50, Appendix I dose limits. A small increase in releases due to additional stored spent. fuel will have no significant impact on the environmental doses.

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LSCS-2

5. Indicate the depth of the spent fuel pool water which normally will d,es cover the stored-in-place fuel elements, and provide the resulting pool surface dose rates for this condition.

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RESPONSE

The La Salle County Station UFSAR Subsection 9.1.2.3 and Technical Specifications Subsection 3.9.9 require a minimum of 23 feet of water to be maintained above the active fuel in the stored assemblies. The pool water surface is approximately 22 feet above the top of the spent fuel pool storage racks, as described in LSCS UFSAR Subsection 9.1.3.1.1.b. After reracking, the resulting pool surface dose rates are calculated at less than 1 x 10-5 mrem /hr due to direct radiation from the spent fuel elements under 23 feet of water.

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LSCS-2 fN. 6.- Provide the spent fuel pool heat exchanger tube surface area,(square g l' feet).

. RESPONSE:-

.The total effective heat exchanger tube surface area is'3,8402ft . This is adequate for limiting the pool. temperature after a-full' core discharge to l approximately 1200 F .

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LSCS-2

7. Verify that the reactor building bridge crane, the lifting and

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v. handling rigs, and all special handling tools are single failure proof.

RESPONSE

The reactor building overhead bridge crane is not single failure proof.

However, this crane has been designed to withstand seismic and tornado conditions. The NRC review and acceptance of the LSCS Heavy Load Analysis, Phase I, is documented in NUREG 0519, Supplement 5, Sections 9.1.2 and 9.1.3, dated April, 1983. The NRC indicated acceptance of the analysis provided for La Salle County Station - Unit 2 Operating License Condition 2.C(14) " Control I

of Heavy Loads" in a letter from A. Schwencer (NRC) to D. L. Farrar (CECO),

dated March 12, 1985.

The lifting and handling equipment for the new rack modules is designed and analyzed in accordance with the requirements of NUREG-0612. The removal of the existing rack components will also be governed by the same requirements.

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LSCS-2

8. Verify that the method of attaching the-lifting device to the new'and-

!0 existing racks are single failure proof.

RESPONSE

The method of' attaching the lifting device to the new rack modules is in accordance with the single failure requirements of.NUREG-0612. The nethod of removing the existing rack. components will be governed by the same requirements.

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LSCS-2

9. For every item which has not been identified as single failure proof,

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fm provide the following information.

Detailed drawings of the component and the method and location a) of attachment (s);

b) The design and actual stress factors to be applied during reracking operations; c) A discussion as to the purpose (s) and use(s) of the component; d) A discussion of the results and effects of the failure of the component at the most adverse time and the protective actions which will be taken to prevent fuel damage or damage to safety-related structures, systems and components; and (f) Provide a discussion of the proposed methods to verify that the failure of this component does not lead to the damage of the pool liner, the fuel storage racks, or other safety-related structures, systems, or components.

RESPONSE

See the response to Number 7. All other items, fuel handling equipment, and

,r 3 O handling processes are single failure proof.

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10. Provide drawings which.show:

a) The arrangement of the spent fuel in the pool when each existing I rack is being removed and each new rack is being installed; b). .The sequence.of each rack removal and installation.of each new rack; l c) The path which each rack will follow within the pool, within the-reactor building, and within any other area until the rack is outside of all safety-related structuras; d) The maximum height that each rack will be lifted above any surface'below; and e) The physical relationship of each load path to 1) other safety-related systems and components, and 2) embedded structural beams within each surface over which the rack will pass.

RESPONSE: (10a)

The. existing spent fuel elements and any radioactive components in the Unit 2 pool will be transferred under water through the transfer canals and cask

-. storage cell to the Unit 1 pool prior to reracking. Thus, there will be no spent fuel elements in the Unit 2 spent fuel storage pool during reracking operations.

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10.b: The sequence of each rack removal and installation of each new rack;

RESPONSE

The rack components (box beams, cross beams, shim plates, end support brackets, and eggerate assemblies) will be lifted out of the pool, decontaminated as required, cut to convenient lengths, wrapped in plastic, moved to the Unit 1 equipment hatch, and lowered to the reactor building ground floor, using the reactor building overhead crane. The old racks will then be prepared for offsite disposal in accord with NRC requirements and CECO procedures.

The new rack modules will be installed (see responses to Numbers 10c and 10d) in the Unit 2 pool after'all the old rack components have been removed.

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10.c: 4 Provide drawings which show the path which each rack will follow

( within the pool, within the reactor building, and within any.other area until the rack is outside of all safety-related components.

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, RESPONSE: (10c) i lhe high density spent fuel rack modules will come onsite through the gates'at the main access facility. They will be taken directly to the reactor building equipment access tunnel. La Salle plans to bring the racks into the Reactor i Building on the carrier's truck. The station will adhere to secondary 1

containment requirements while entering the tunnel through the outer missile door and while entering the reactor building through the inner missile door.

l The rack modules will be lifted to the refuel floor through the Unit 1 equipment hatch using the reactor building overhead crane. Once above the refuel floor, mcVement of the racks will be controlled administrative 1y to prohibit movement'of the modules over any spent fuel. The racks will be taken directly to a convenient storage area. La Salle currently plans to store the modules along the east wall of the refuel floor as space permits. Two travel paths are being considered from the equipment hatch as shown in Figure 10-2:

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1) south along the east wall and, if necessary, west over the Unit 1 dryer-separator pit, then north along the. west wall to the area of the Unit 2 reactor building elevator.

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2) north along the east wall and, if necessary, west over the Unit 2 dryer-separator pit, then south along the west wall to the area of the Unit 2 reactor building elevator.

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LSCS -

10.d: Provide drawings which show the maximum height that each rack will be lifted'above any surface below.

RESPONSE: (10d)

The attached Figure 10-1 shows the path a rack module will follow as it is lifted from the ground floor elevation 710 feet 0 inch to the refuel floor elevation 843 feet 6 inches. The rack module may have to be raised an l-additional 4 feet to clear the safety railing surrounding the Unit'I hatch.

This would put the rack a maximum of approximately 138 feet above the ground floor. While a module is traveling above the refuel floor, the normal height above the floor would be 1 to 2 feet when possible. However, there could be some obstacles which might require a module to be lifted higher above the floor for a short period of time. The station will limit administrative 1y this height to approximately 6 feet above the floor. If it is necessary to carry a module over the dryer-separttor pit, the module would be a maximum of approximately 30 feet above the floor of the pit. When a module is carried over the spent fuel pool it will be a maximum of approximately 42 feet above

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V the floor of the spent fuel pool.

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I LSCS-2 10.e: The physical relationship of each load path to 1) Safety-related (q)-

systems and components 2) embedded structural beams within each surface over which the rack will pass.

RESPONSE: (10e) 1)' Figure 10-1.shows the load path for rack movement between the grade floor l' and the refuel floor in the Unit 1 equipment hatch. Figure 10-2 shows l

the two proposed load paths and interim storage area for the new rack modules on the refuel floor. The refuel floor over which the racks will pass has a live load capability of 1,000 psf, and the entire floor area is considered a safe load laydown area. The relationship of safety-related systems and components under the load paths are addressed in LSCS Heavy Load Report and LSCS PSAR Special Report 2.

2) The refuel floor over which the rack will pass has 18-inch-thick reinforced concrete slabs supported by concrete beams. There are no embedded structural steel beams supporting the concrete slabs.

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-(( 11. Provide the results of an analysis of dropping the rack into the spent fuel pool, and any other body of water over which the racks may pass, assuming the rack is at its maximum carrying height. The results should address the effects of splashing water out of the pool (both in terms of a potential personnel hazard and in terms of the loss of water and potential loss of NPSH for the spent fuel pool cooling system pumps), and pool impact effects 1) on the pool liner at its weakest point (at the leakage detection traces), 2) on other j fuel storage racks, and 3) on other safety-related structures, j systems, and components.

RESPONSE

The existing spent fuel elements in the Unit 2 spent fuel storage pool will be transferred under water to the Unit 1 pool prior to reracking operations. The old' rack components will be removed prior to installing the new high-density spent fuel storage rack modules. Movement of the racks will be controlled '

administrative 1y to prohibit rack movement over any spent fuel element. It may be necessary to move new rack modules over a dryer-separator storage pit, with no anticipated adverse consequences.

The potential for a postulated accident is small but has no safety significance because.the rerack operation will be performed without spent fuel assemblies in the pool. Normal Rad / Chem procedures will apply to minimize any l personnel hazards.

i l

l O

11-1 l

4 LSCS-2 (N 12. Verify that no fuel would be impacted if the rack were to fall on its

. t, side, or provide a discussion of your procedures which will prevent ,

the rack from falling on its side given that the rack is dropped by failing one yoke at a time.

RESPONSE

The Unit 2 spent fuel storage' pool will be empty of spent fuel elements during r reracking operations. The old rack components and new rack modules will not move over fuel elements. Consequently, no fuel elements will be impacted if a i rack.were to fall on its side.

O O

12-1 l.

LSCS-2 i 1

i

13. Verify that all operator training, load handling procedures, and eye testing of operators will be in conformance with NUREG-0612. " Control of Heavy Loads at Nuclear Power Plants."-

RESPONSE: )

i y.t La Salle County Station documented its compliance with NUREG-0612 and in i particular with ANSI B30.2-1976 with' respect to crane operator training,

]

qualification,_and conduct in a letter to A. Schwencer (NRC) from C. W.

Schroeder (CECO) dated April 5, 1983. Station compliance with ANSI B30.2-1976 was documented in Action Item Record 01-83-173.

l

.~

o J

O 13-1

LSCS-2

14. In Section 4 of the spent fuel storage capacity modification safety L ..

. analysis reportt -the seismic analysis of the modification is referenced to various~ portions of the Sargent & Lundy specification T-3758. Indicate where this specification can be found. ne piovide a copy.

RESPONSE

Attached is Sargent & Lundy Specification T-3758 " Spent Fuel and Special Storage Racks" with Addendum 1 and Amendment 1.

O i

1 0

14-1

O SPECIFICATION T-3758 SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY PROJECT NO. 7043-73 0

e O

EARGENT G LUNDY ENGlNECQD C"'CAGo August 1, 1986 AMENDMENT l

-(

TO SPECIFICATION T-3758 (DATED 07-17-85).

l FOR l

SPENT FUEL AND SPECIAL STORACE gACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY

1. The following pages have been revised and are issued herewith. These revised pages are to be inserted in the appropriate place in the Speci-fication and superseded pages of prior issue voided. The information set forth in this Paragraph is f ar convenience only and shall not affect the revised pages included herewith:

Page Changes Pertain to Approval Page AP-1 Amendment 1 signatures.

i Issue Summary Page (Post) IS-1 Amendment 1 page changes listed.

Certification of Specification l

Page CP-1 Amendment 1 certified.

l l

l-1 Article 105.1 revised.

1-2 Article 106.3 added.

1-7 Article 112.6 added. Deleted " final Page of Division 1."

1-8 New page. Carry over from page 1-7.

Added " Final Page of Division 1."

2-1 Article 201.2 revised. Subarticles 201.4a and 4b revised. Article 201.6 added.

2-la New page to take overflow.

2-lb New pa6e to take overflow.

2-le New page to take overflow.

A AMDI-l

.__ _ ______-____________________ w

SARGENT & LUNDY ENGINEERS cwicano - Amsndment 1, Cont.

Specification T-3758 Spent. Fuel and Special Storage Racks t

l O La Salle County Station -

Units 1 and'2 l

l:

.Page Changes Pertain to 2-1d New'page to take overflow.

2-le New page to take overflow. Article 201.7 added.

l 2-1f New page to take overflow.

2-3 Subarticle 202.2a revised.

2-4 Subarticle 202.2a revised.

2-4a New page to take overflow.

2-4b New page to take overflow.

2-4c New page to take overflow. Subarticle L 202.2b revired.

2-4d New page to take overflow.

i

( 2-5 Subarticle 202.2b revised.

2-Sa New page to take overflow.

2-8 Article 204.4 revised.

3-5 Article 302.8 revised.

3-7 Article 303.1 revised.

3-9 Article 303.15 revised.

3-12 Articles 305.4 and 305.9 revised.

3-13 Article 305.11 revised.

3-14 Articles 305.17 through 305.22 added.

Article 306.2 revised. Articles 306.3 through 306.5 deleted. Deleted " Final ,

Page of Division 3." ]

3-15 New page. Carry over from page 3-14 Added " Final Page of Division 3."

(')

s.

AMDI-2

CARGENT& LUNDY ENGlNEERS cmcaco - Amandment l', Cont.

Specification T-3758

.. Spent Fuel and Special' Storage Racks

~

i rs. . La Salle County Station -

Units 1 and 2 Page Changes Pertain to

2. The following design documents are issued herewith and form a part hereof

a. Response Spectra Curves:

Title Spectra No. Date Service Level B LC-1-NS 02-12-86 LC-1-ES 02-12-86 LC-1-VS 02-12-86 Load Comb Level C C-NS 02-13-86 C-ES 02-13-86 C-VS '02-13-86 04-26-73

~

Operating Basis Earthquake (OBE) 106-0B-NS Response Spectra 106-0B-EW 04-26-73 106-0B-VW 07-20-73 107-0B-VW 07-20-73

_ fI 108-08-VW 106-0B-VS 07-20-73 07-20-73 107-0B-VS 37-20-73 108-0B-VS 07-20-73 107-0B-NS 04-26-73 116-0B-NS 04-26-73 124-0B-NS 04-26-73 107-0B-EW 04-26-73 116-0B-EW 04-26-73 124-08-EW 04-26-73 108-0B-NS 04-27-73 108-0B-EW 04-27-73 Design Basis Earthquake (DBE) 106-DB-NS 04-26-73 Response Spectra 106-DB-EW 04-26-73 :

106-DB-VW 07-24-73 l 107-DB-VW 07-24-73 108-DB-VW 07-24-73 106-DB-VS 07-25-73 107-DB-VS 07-25-73 108-DB-VS 07-25-73 107-DB-NS 04-26-73 116-DB-NS 04-26-73 124-DB-NS 04-26-73 107-DB-EW 04-25-73

'16-DB-EW

_ 04-26-73 O

'24-DB-EW 04-26-73 AMDI-3

J

'cARGENT a LUNDY E Qi$EERS

,o Am3ndm2nt'1, Cont.

Specification T-3758 Spent Fuel'and-

.f Special Storage Racks

(~- .

La Salle County Station', -

L]

Units'1 and'2 Title Spectra No. Revision Safety / Relief Valve SS-113-VS 0 ]

'(SRV-ALL & ADS) Response SS-113-HS 0 Spectra Reactor Bldg. SS-114-VW. O SS-114-HW 0 SS-115-VS 0 i SS-115-HS 0 SS-116-VW 0 SS-116-HW 0 SS-119-VS 0 SS-119-HS 0 SS-120-VW - 0.

SS-120-HW 0 Safety / Relief Valve SA-113-HS 0 (SRV-Asymmetric) Response SA-113-VS 0 i Spectra Reactor Bldg. SA-114-HW 0 SA-114-VW 0 SA-115-HS 0 SA-115-vs 0 SA-116-HW -0 O- .

SA-116-VW SA-119-HS 0

0 SA-119-VS 0 SA-120-HW 0

SA4120-VW 0 Safety / Relief Valve (SRV-Single) S0-113-HS 0 Response Spectra Reactor Bldg. S0-113-VS 0 50-114-HW 0 S0-114-VW 0 S0-115-HS 0 50-115-VS 0 S0-116-HW 0 50-116-VW 0 S0-119-HS 0 S0-119-VS 0 j S0-120-VW 0 l 50-120-HW 0 LOCA (Asymmetric Chugging) AC-311-HS 0 Response Spectra Reactor Bldg. AC-311-VS 0 AC-312-HW 0 AC-312-VW 0 AC-313-HS 0 .

1 O

AMDI-4 l

J

SARGENT O'LUNDY

' ENGINEERS -. -

CHICAGO Amendment 1, Cont..

Specification T-3758-p Spent fuel and Special Storage Racks

' f/')-

[ La Salle County Station -

Units 1 and 2- 1 Title Spectra No. Revision-LOCA (Asymmetric Chugging) AC-311-HS 0 Response Spectra Reactor Bldg. AC-311-VS 0 AC-312-HW- 0 AC-312-VW- 0-AC-313-HS 0 AC-313-VS 0 AC-314-HW 0 AC-314-VW 0 AC-315-HS 0 AC-315-VS 0.

AC-316-HW 0 AC-316-VW 0 AC-317-HS 0 AC-317-VS 0 AC-318-HW 0 AC-318-VW 0 LOCA (Condensation, Oscillation CC-311-HS 2 !

Load Combination-1) Response Cd-311-VS 2 l Spectra Reactor Bldg.. CO-312-HW 2 l

\- : Ce-312-VW 2 C6-313-HS 2-CO-313-VS 2 CC-314-HW 2 CO-314-VW 2 CO-315-HS 2 CO-315-VS 2 CC-317-HS 2 Co-317-VS 2 CO-318-HW 2 CO-318-VW 2 LOCA (Condensation Oscillation Co-311-HS 2 Load Combination-2) Ce-311-VS 2 CO-312-HW 2 C6-312-VW 2 CO-313-HS 2 CO-313-VS 2 CO-314-HW 2 CO-314-VW 2 CO-315-HS 2 CC-315-VS 2 CO-317-HS 2 Co-317-VS 2 CO-318-HW 2

.O CO-318-VW 2 AMD1-3 1

__-_-_-_________-_-_________U

SARGENT~G LUNDY ENGINEERS cd'c^oo Amandment 1, Cont.

Specification T-3758 Spent Fuel and

,Q Special Storage Racks La Salle County Station -

() 2 Units 1 and 2

b. Seismic Displacements:

Horizontal Seismic Model (Calc. No. 163, page 103, Rev. 1)

Probable Maximum Displacements - OBE, Horizontal Excitation (Table 18, Calc. No. 163, pages 55 & 56, Rev. 1)-

Probable Maximum Displacements - DBE, Horizontal Excitation (Table 18A, Calc. No. 163, page's 57 & 58, Rev. 1)

3. The'following reference drawings have been previously issued and form a part hereof: ,

3.1 Structural Drawings:

Drawing No. Revision S-214 U S-215 AD S-222 AF S-223 AC Os S-224 S-225 AK P

S-227 E S-228 L S-229 AD S-230 M S-231 R j S-232 AA l S-233 L l S-234 5 S-235 N S-236 S S-237 W l S-238 U i S-239 C S-240 C S-241 H S-242 H

{ S-243 H S-244 D S-245 AD S-246 D S-247 F S-243 B S-249 H S-250 AK l

AMDI-6

SARGENT O LUNDY E N GIN E E RS _

g emeaoo Amsndment1,.- Cont.

Specification.T-3758 Spent Fuel and.

.j

'% .Special Storage Racks

, La Salle' County Station -

Units 1 and 2 S-251 AF -'

S-252 K f.

' .S-253 T S-254 U S-255 S.

S-256- .AB S-259 M S-260 T S-261 P S-262 AJ S-263 W S-264 Y S-265 E-S-266 B=

S-267 E S-268 F S-269 D S-270 J S-271 D S-272 AC S-273 -AB O S-274 S-275 S-276 C

D S

S-277 F S-278 F S-279 W S-280 Y S-714 Z S-715 AA S-759 C

4. The following page of the Supplement listed below has been revised and

. issued herewith.

Attachment A - Commonwealth Edison Standard Quality Arti Page 15 of 22 cles - Revision 9, dated January 6, 1983 - As modified for Specification T-3758 (22 pages).

5. Except as expressly amended by this Amendment 1, all provision 3 of Specification T-3758, remain unchanged.

AMDl-7 Final

SARGENT & LUNDY EN September 9, 1985 r

j,NEERS-c

/N ADDENDUM 1 c*

~ '

TO 1-SPECIFICATION T-3758 (DATED JULY 17, 1985)

FOR

' ~'

SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY i

1. TheLfollowing pages have been revised and are issued herewith. These revised pages'are to be inserted in the appropriate place in the Specifi-cation and s'uperseded pages of prior issue voided. The information set forth in this Paragraph is for convenience only and shall not affect the revised pages included herewith:

g Changes Pertain to AP-1 Addendum 1 approved.

IS-1 Addendum 1 listed.

CP-1 Addendum 1 certified.

1-2 Article 106.3 deleted.

1-3 Article 107.3 revised.

1-4 Article 109.2 revised.

3-3 Articles 301.8k and 1 revised.

3-3a Carryover from 3-3.

3-12 Article 305.9 revised. !

l 3-13 Article 305.14 revised.

PFII-2 Item 4.2 deleted. Items renumbered. J

2. Bidder shall state in his proposal that the provisions of this Addendum I have been covered.

l

/

Gl Al-1 Final I

GARGENTfxLUNDY EN j,NEER2 Spec. No. T-3758 NUCLEAR SAFETY-RELATED o9 Projsett 7043-73 Issue: Amd. 1,08-01-86 s.

SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY APPROVAL PACE NUCLEAR SAFETY RELATED ITEMS ARE PART OF THIS SPECIFICATION

! Issue l l

Purpose Date Prepared by etsviewed by C . Approved by, Comments 04-22-85 M M pear I

Bids 07-17-85 I

,g g ' : i s'!

/ a <y // " '- ~ '

Addendum 1 09-09-85 g g b spe/ [ h" b

' Amendment 1 08-01-86 p'/ua. .((s , <. / gM(

t I t l

l !

i :

I 1

i l

l l

l I

i O .

l AP-1 Fina1

CARGENT O LUNDY ENGlNEERO NUCLEAR SAFETY-RELATED cmcaoo Project 7043-73 Spec. No. T-3758 Issue: Amd. 1, 08-01-86 (x,

\ l

%d SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY ISSUE SUKMARY PACE Purpose of Issue Date Pages Affected Com - Specification 04-22-85 All T-3758 issued for client comments.

Bid - Specification 07-17-85 All T-3758 issued for Bids.

rT Add. 1 - Addendum 1 09-09-85 , AP-1, IS-1, CP-1, 1-2,

(,,) to spec. T-3758 1-3, 1-4, 3-3, 3-3a, issued. 3-12, 3-13, and PFII-2.

I Amd. 1 - Amendment 1 08-01-86 , AP-1,IS-1,CP-1,1-1,1-2,l to Spec. T-3758 -

1-7,1-8,2-1,2-la,2-lb,I' issued. 2-Ic, 2-Id, 2-le, 2-1f, 2-3, 2-4, 2-4a, 2-4b, l l

2-4c, 2-4d, 2-5, 2-Sa, 2-8,'.

i 3-5, 3-7, 3-9, 3-12, 3-13,'

3-14 and 3-15.

1 i

i 4

/

x_)\

S-1

nal

CARGENT & LUNDY' ENGINEERS

' NUCLEAR SAFETY RELATED cHicAco Project: 7043-73 T-3758

.A

'( ,j- '

LA 3ALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY INSTRUCTIONS TO BIDDERS RE: Specification T-3758 Spent Fuel and Special Storage Racks Issues Bid, 07-I7-85

1. PROPOSAL Proposal will not be considered unless it includes Proposal Form - Part I and Proposal Form - Part II, consisting of the accompanying forms properly filled out, and all required submittals. Extra copies of these forms are enclosed for Bidder's use. Bidder shall use the same format and page numbering in submitting his bid.

2. PRICE INFORMATION The base price shall 6ppear only where called for in the Proposal Form -

Part I, and shall not appear elsewhere in the Proposal. Other price information, such as options and alternates, shall be given as a price addition to or deduction from the base price and shall be specified in the Proposal Form - Part II, or attached thereto. Unit Prices (if any) shall be as specified in Proposal form - Part II. Price information shall not be included in proposal transmittal letter or in the Bidder's j )

technical or other nonpriced data.

3. COMPLETENESS OF PROPOSAL 3.1 Bidder is hereby notified that it is Purchaser's intention that Bidder's proposal shall be complete in order to avoid extras to the Contract price.

3.2 Bidder shall, therefore, include in his bid all work which is indicated in the Bid Documents and which is normally considered part of the type of work covered by the Bid Documents, whether or not such work is fully detailed in the Bid Documents. {

4. BID DOCUMENTS 4.1 The following are attached hereto and form the Bid Documents:

i

a. These Instruction to Bidders.

1

b. Specification T-3758.

c. Purchaser's General Conditions, Exhibit "A", dated February, 1979,

d. Proposal Form - Part I. ]

l

e. Proposal form - Part II. )

ITB-1 ITB-J-26 (11/83)

i GARGENT & LUNDY E N GIN E E n$ '

cmeaoo T-3758 Bid, 07-17-85

.)

4.2 Any contract or purchase order resulting from these Bid Documents will incorporate the terms and provisions of said documents. It is intended-that these Bid Documents shall prevail over conflicting provisions of 1

Bidder's proposal.- All exceptions to these Bid Documents must be listed together and specifically identified'as Exceptions in Proposal Form -

Part II, Item 14.6. Bidder's printed terms and conditions are not considered specific exceptions.

5. BIDDER'S RESPONSIBILITY 5.1 It is the Bidder's responsibility to gather and dispense all information to his subbidders regarding the provisions of the Bid Documents and any other information a subbidder may require to prepare his bid (s). l i

5.2 contact between subbidders and the Consulting Engineers shall be only through the Bidder, and Bidder shall so inform his subbidders.

6. PROPOSAL DISTRIBUTION 6.1 Engineering details should be discussed with the Consulting Engineers, Sargent & Lundy. 55 East Monroe Street, Chicago, Illinois 606031 but all other matters pertaining to submitting of proposal should be discussed with Mr. R. C. Van Derway, General Purchasing Agent, Commonwealth Edison ,

Company, One First National Plaza, Chicago, Illinois. '

/~' 6.2 Only one copy of Proposal Form - Part I, the original, shall be :

submitted. The remaining Proposal copies to be submitted to Purchaser shall include Proposal Form - Part II. The number.of Proposal copies required by Purchaser is stated in Purchaser's Invitation to Bid letter.

6.3 All copies of Bidder's Proposal shall be enclosed in the envelope furnished with this inquiry, sealed and delivered by the appointed time to:

l l

IF MAILED: Commonwealth Edison Company Sealed Bid Auditor P. O. Box 767 Chicago, Illinois 60690 ,

IF DELIVERED IN PERSON: Commonwealth Edison Company Sealed Bid Auditor i

34th Floor East j One First National Plaza Chicago, Illinois l 6.4 Any price or technical data submitted subsequent to the original proposal l ,

shall state the reason for the revision, be submitted in the same number of copies as the original bid and be mailed or delivered to Consonwealth Edison Company, Sealed Bid Auditor as indicated in Paragraph 6.3 above, in Bidder's envelope, sealed and clearly marked with the appropriate

( inquiry reference number.

ITB-2 ITB-J-26 (11/83)

SARGENTO LUNDY ENGtNEERD

' CHICAGO T-3758 Bid, 07-17-85

'A 6.5 If Bidder's engineering data proposal cannot be conveniently included with the price proposal it shall be submitted separately to:

Commonwealth Edison Company Mr. R. E. Van Derway, General Purchasing Agent 34th Floor West One First National Plaza Chicago, Illinois

7. NONDISCLOSURE OF PROPOSAL FORM - PART I BID INFSRMATI C The price information given in completed Propesal form - Part I, and ,

supplemental price information submitted subsequent to the original i Proposal, shall not be disclosed to Purchaser's employecs, agents or consultants, except where specifically approved.by Purchaser's General Purchasing Agent or his Alternate.

8. RIGHT TO REJECT The right is reserved by Purchaser to reject any or all proposals or any portion thereof. Neither receipt of proposal nor failure to reject proposal shall impoge any legal obligation on Commonwealth Edison Company.

9. SPECIAL PROPOSAL REQUIREMENTS

.A 9.1 In addition to the completed Proposal Forms Part I and Part II, Bidder shall furnish the following with each copy of his bid.

(J

a. A detailed list of all items of the equipment and their accessories and complete specifications covering construction and materials used in each item of equipment.

b. Drawings showing the general arrangement and principal dimensions of the equipment, including sectional views.

c. A final change date after award of contract prior to which a Purchaser may request design changes at no charge.

d. Contractor shall visit the site during the Bid Period to familiarize himself with the fuel pool and the existing system of structural members which support the existing racks. Any as-built dimensions which are important to Contractor's design must be verified by the Contractor on the site.

O ITB-J-26 (11/83) ITB-3 Final

_____________A

SARGENT & LUNDY

.. E N GIN E E RS NUCLEAR SAFETY-RELATED cmcaco. j Spec. No. T-3758 1 Project: 7043-73 Issue: Amd. 1, 08-01-86

)

b CERTIFICATION OF SPECIFICATION l

FOR SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY l

i

.I certify that this Specific.ation was prepared by me or under my supervision and that I am a registered professional engineer under the laws of the State of Illinois.

O O t.

i Certified by: Mw,. fp (p' . /j h Date: July 17. 1985 f#......,.. ,

.! \D...g:..%,

/Q3+'62 l Pimio \

3 91/'$

q StfibfiSti):.4l: <.

k *\**d.Gt!.iid CF 4f

/ * ......**** /

Revisioni Add. 1 Certified by' p-w:e

, h Date: 09-09-85 A;nd . 1 (744 ce d- yd 08-01-86 O

CP-1 Final i l

SARGENT & LUNDY ENGINEEOS NUCLEAR SAFETY-RELATED cmcaco Project: 7043-73 Spec. No. T-3758 Issue: Bid, 07-17-85

/<~s t I

\

'~) SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 COMMONWEALTH EDISON COMPANY TABLE OF CONTENTS ARTICLE PACE DIVISION 1 - CENERAL REQUIREMENTS 101. Purchaser.................................................... 1-1 102. Name of Project.............................................. 1-1 103. Location of Project.......................................... 1-1 104. Transportation Facilities.................................... 1-1 105. Scope of Work................................................ 1-1 106. Work by Others............................................... 1-2 107. Schedule..................................................... 1-2 108. Definitions and Abbreviations................................ 1-3

[~'}

G 109. Codes and Standards.......................................... 1-3 110. Specified Products and Substitutions......................... 1-5 111. Quality Assurance............................................ 1-5 112. Packaging, Shipping, Storage, Etc. .......................... 1-6 I

113. Conformance with 10CFR Part 21............................... 1-7 DIVISION 2 - SUPPLEMENTS, STANDARDS AND DRAWINGS l 201. Supplements.................................................. 2-1 202. Drawings..................................................... 2-1 203. Manufacturer's Drawings...................................... 2-4 204. Drawings and Data (Contractor's)............................. 2-5 6

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SARGENT O'LUNDY ENcourens T-3758 CHICAGO '

Bid, 07-17-85 TABLE OF CONTENTS, Cont.

ARTICLE- PACE

. DIVISION 3 - TECHNICAL REQUIREMENTS 301.. Genera 1...................................................... 3-1

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302. Design and Fabrication....................................... 3-4' 303.. Dimensional Requirements..................................... 3 .304. Design Data.................................................. 3-9 305..

Structural. Requirements...................................... 3-11 .

'306. Inspection and Testing....................................... 3-14 307. Painting..................................................... 3-14 308. Too1s........................................................ 3-14 L

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1 GARGENT & LUNDY ENGINEEng NUCLEAR SAFETY-RELATED cmcaco -

Project: 7043-73 Spec. No. T-3758 Issue: Amd. 1, 08-01-86

+ 1 V.

SPECIFICATION FOR SPENT FUEL AND SPECIAL STORACE RACKS DIVISION 1 - CENERAL REQUIREMENTS j 101.. PURCEASER: COMMONWEALTH EDISON COMPANY.

102. NAME OF PROJECT: LA SALLE COUNTY STATION - UNITS 1 AND 2.

103. LOCATION OF PROJECT La Salle County Station is located in La Salle County, Illinois, six '

miles southeast of Marseilles, Illinois, three miles west of State Highway 170, and one-half mile north of the Grand Ridge-Mazon Road (La Salle County Highway 6).

104 TRAN3PORTATION FACILITIES

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A stur track from the Atchison, Topeka and Santa Fe Railroad near Ransom, Illinois, runs north seven and one-half (7-1/2) miles to the Station site. A barge dock is in place on the Illinois River. The project site is accessible from County Highway 6.

105. SCOPE OF WORK

[h 105.1 Contractor shall design, engineer, fabricate, furnish and deliver t\_ / f.o.b. carrier La Salle County Station consigned to Purchaser, c/o Mr.'C. J. Diederich, equipment consisting of spent fuel storage racks complete with all necessary appurtenances for the storage of maximum number of spent fuel assemblies; and special storage racks i designed for 43 miscellaneous storage locations, capable of (md . I accommodating 3 control rod guide tubes, 5 defective fuel assemblies I in its storage container, and 35 control rods. The spent fuel and special storage racks shall be of the freestanding, high density, neutron absorbing type. Contractor shall provide the maximum storage by optimizing the spent fuel storage pool's structural loading capability and the geometric layout of the pool.

105.2 contractor shall also provide the~following professional services as part of the scope of work.

a. Advance notification of design impact of racks on the fuel pool cooling and residual heat removal system equipment and appur-tenances.

b. Preparation of licensing reports and the certified design report.

Contractor shall support and aid purchaser in all licensing phases of the spent fuel and special storage rack design.

c. Preparation of fabrica:icn specifications and design detail e drawings.

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i CARGENTe LUNDY' {

ENGINEERS 1 CH# caco. T-3758 .

'l Amd. 1, 08-01-B6 j

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g d.. Preparation of erection specifications and field erection drawings.

Erection specifications shall provide instructions and technical direction for the cleaning / decontamination of the spent fuel and special storage racks. .. Erection specifications and drawings shall include a comprehensive outline as to the extent of field fabri- .

cation required, and information pertaining to all disassembling, I reassembling, welding, bolting, cleaning, checking inspection, testing, etc. required to be done by the erection. contractor.

e. Contractor shall supply all special tools, instruments and fixtu'res indicated in the erection instructions / specification which are not normally furnished by erection contractors or plant's erection contractor.

f. Providing field technical direction in the installation / erection maintenance and servicing of the racks.

g. Contractor shall survey and evaluate existing pool configuration.

Contractor shall provide instructions and technical direction for the removal of existing fuel racks and associated structural support components.

.106. WORK BY OTHERS The following Work will be by others:

f- 106.1 Unioading, erection, and field testing of equipment.

106.2 All disassembly associated with the removal of structural support components and existing spent fuel racks specif~ied in Article 105.2g.

106.3 Purchaser shall verify onsite, af ter leveling of racks, that ea:h Amd. I cell can accept a 3 plate mandrel without exceeding a maximum drag force of 50 lb. The exterior dimension of each plate shall be 5.975 inches on side.

107.. SCHEDULE 107.1 Contractor shall submit a schedule covering engineering, manufac-turing, etc., for timely completion of the Scope of Work as hereinafter specified within 2 weeks following contract award.

107.2 The schedule shall encompass all major milestones involved in completion of the Work, for example (but not. limited to): pre-liminary and final drawing submittals, quality assurance procedures submittal, submittal of major contractor calculations, return of comments by the Consulting Engineers; material orders, material receipts, fabrication releases, fabrication sequence, testing and shipment. The final Schedule and its contents shall be agreed upon by Contractor and the Consulting Engineers immediately after award cf centract, to facilitate submittal of the Schedule by Contractor as specified aoove.

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SARGENT & LUNDY ENG' NEE"5 T-3758-Add. 1, 09-09-85

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107.3 .The spent fuel and special storage racks for Unit.2 shall be Add.1 delivered f.o.b. carrier La Salle County Station by the following date:

Add.1 Unit 2................................ August 1, 1986 (or sooner) 108. DEFINITIONS AND ABBREVIATIONS 108.1 . Definitions:

a. Wherever the word " Vendor" appears in the Bid Documents, it shall be construed to mean " Contractor."

b. Wherever the word " Purchaser" appears in the Bid Documents, it shall mean " Owner," Commonwealth Edison Company.

Wherever in the Contract Documents the term " Consulting Engineers"

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c.

is used, it refers to Purchaser's Consulting Engineers, Sargent & ,

Lundy.

d. The term " certified" shall be construed to mean certified by the Contractor unless specifically noted otherwise.

e. The term " Manufacturer" shall be construed to mean " Contractor."

f. The word " product" as used herein shall mean materials, equipment, or processes.

g. Wherever " Supplier" or " Subcontractor" is used in this Speci-fication, or any referenced specifications, it shall be construed to mean " Contractor."

h. Wherever the term " furnish" is used in this Specification, or indicated on the drawings, it shall be construed to mean furnished by the " Contractor."

i. The term " indicated" shall mean "as shown, noted, called for, or specified" unless otherwise specifically stated.

j. Wherever the term " installed by others" is used in this Specification, or any referenced specification, it shall be construed to mean installed by the Purchaser or Purchaser / Contractor groups.

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SARGENT & LUNDY

.ENGINLERS T-3758 Add. 1, 09-09-85 108.2- Abbreviations ANSI - -American National Standards Institute ASME -

~ American Society-of. Mechanical Engineers ASTM -

American Scoeity for Testing and Materials 109. CODES AND STANDARDS General: The following codes and' standards are applicable to the design, manufacture, inspection, testing, and' cleaning of the' equipa nt included in this Specification and shall form a part of this Specification to the extent'specified herein. All referenced documents shall be'the latest issue'of each in effect as of the date of-this contract unless otherwise noted. These documents are not attached'to this Specification.

'109.1 ANSI Standards ANSI-N45.2.2 -

Packaging,-shipping, receiving, storage and handling of items for nuclear power plants ANSI-N45.2.9 -

Requirements for collection, storage and main-tenance of quality assurance records for nuclear power plants ANSI-N45.2.10 -

Quality assurance terms and definitions ANSI-N45.2.11 -

Quality assurance requirements for the design of nuclear power plants

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ANSI-N45.2.13 -

Quality assurance requirements for contro1 of procurement of items and services, for nuclear I power plants.

ANSI-N45.2.1 -

Cleaning of fluid systems and associated ,

components during construction phase of nuclear power plants.

ANSI /ANS-57.2 -

Design requirements for LWR spent fuel storage facilities at nuclear power plants ANSI /ANS-8.1 - Nuclear criticality safety,in operations with fissionable materials outside reactors.

'ASME Codes - (Edition and Addenda in effect at ;date of j 109.2 p

contract; use 1980 Edition throt.gh Summer 1982 Add.1 Addenda for Structural acceptance criteria) l ASME Section III - Nuclear Power Plant Comrocents 1

ASME Section IX - Welding and Brazing Quari(ications O

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SARGENT & LUNDY E N GIN E E R 5 cmcaso T-3758 Bid, 07-17-85 Nuclear Regulatory Commission Documents:

()1109.3 a.. Nuclear Regulatory Guides:

1.13 - l Spent Fuel Storage Facility Design Basis .

1.123, 07/77 -

Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 2

1.128, 02/79 -

' Quality Assurance Program Requirements 1 29 -

Seismic Design Classification 1.60 -

Design Response Spectra for Seismic Design of Nuclear Power Plants 1.61 -

Damping Values for Seismic Design of Nuclear Power Plants 1.64,.06/76 -

Quality Assurance Requirements for the Design of Nuclear Power Plants 1.92 -

Combining Modal Responses and Spatial Components in Seismic Response Analysis 1.124 -

Service Limits and Loading Combinations for Class 1 Linear Type Component Supports.

b. NRC Standard Review Plans SRP 3.7 -

Seismic Design SRP 3.8.4 -

Other Category I Structures SRP 9.1.2 -

Spent Fuel Storage Branch Technical - Residual Decay Energy for LWR for Long Term Position APCSB9.2 Cooling SRP 9.1.3 -

Spent Fuel Pool Cooling and Cleanup System.

c. NRC Cuidance " Review and Acceptance of Spent Fuel Storage and Handling Applications" dated April 14, 1978 and modifications to same, dated January 18, 1979.

110. SPECIFIED PRODUCTS AND SUBSTITUTION 9 Mention of materials or components'by name as products of certain manufacturers in this Specification is made to insure that the proper quality and/or type is provided. Products of other manu- j facturers will be acceptable if Contractor furnishes proof to the

.O Consulting Engineers that the proposed substitute products are equal 1-5

SARGENT & LUNDY ENGINEERS T-37$8

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Bid, 07-17-85 7g to or better than the specified products in quality, performance, t ) design, environmental qualification and suitability for the intended use. Any purchase of proposed suestitute products by Contractor prior to acceptance by the Consulting Engineers and Purchaser will be at the contractor's own risk.

111. QUALITY ASSURANCE The Quality Assurance Requirements are Commonwealth Edison Company Standard Quality Articles as amended and listed in Article 201 of this Specification.

112. PACKACINC, SHIPPING, STORACE, ETC.

The equipment by this Specification is classified as Level C in accordance with ANSI N45.2.2 and shall be packaged, shipped and prepared for storage in accordance with ANSI N45.2.2, and the following: .

112.1 contractor shall adequately prepare all the equipment for shipment and all equipment and items shall be packaged for six (6) months outdoor storage. The Contractor shall furnish and install necessary covers to protect the equipment from rain, hail, w' ,, dust, etc.

All exposed machined surfaces shall be protected with a suitable antirust compound before shipment. Contractor shall support and brace the racks with bracing of adequate strength and spacing to ensure that no damage to racks occurs as a result of handling, shipping or long term horizontal storage.

-- 112.2 All equipment and separately shipped items shall be clearly identi-fied with a securely fastened, weatherproof tag, labeled with Pur-chaser's Order No., Station Name and Unit Number, " Specification No.

T-3758," " Equip. No. ," and, service. All shipping con-tainers, packing lists, bills of material, correspondence, etc.,

shall be identified with the same above information.

Example: P. O.

La Salle County Station, Unit 1 Specification No. T-3758 Equip. No.:

Service: Spent Fuel and Special Storage Racks 112.3 contractor shall be responsible for his subcontractor (s) adhering to the above shipping preparations on all equipment and items shipped to the Purchaser by the subcontractor, 112.4 In order to provide the Purchaser with equipment in a corrosion-free state, the manufacturer shall furnish the Purchaser with instruc-tions for storage and maintenance of his equipment for the period prior to installation as well as for the period between completion of installation and the time that the equipment is placed in service.

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SARGENT & LUNDY E N GlN E E R $

cme ^oo T-3758-Amd. 1, 08-01-86 (f112.5 Shipping' Instructions:

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'The Manufacturer shall ship the devices to the Purchaser's project a.

site.

b. . Truck, parcel post. .or railway express shipment shall be consigned to Commonwealth Edison Company, Attention: Mr. C. J. Diederich, La Salle' County Station, Rural Route, Marseilles, Illinois 61341.

c. Mail to the _ station'shall be addressed in the.name of Commonwealth Edison Company, Attention: Mr. C. J. Diederich, La Salle County-Station, Rural Route #1, Marseilles, Illinois 61341.

d. Routing information will be furnishes upon request to Traffic and

. Expediting' Agent for Commonwealth Edison Company following receipt of detail information showing points of shipment for all proposed i carloads or truck shipments.

Note: Complete shipping instructions will be-furnished to Contractor by Purchaser at a later date.

112.6 Contractor shall use the following numbers to tag the equipment: Amd. 1 UST & D Rack No.

(per CECO. CECO O~ Drawing 8601-1)

Equip.

No.

UST & D Rack No.

(per Drawing 8601-1)

Equip.

No.

1 2FC06C 17 2FC22C 2 2FC07C 18 2FC23G 1 3 2FC08C 19 2FC24C 4 2FC09C 20 2FC25C 5 2FC10C 6 2FC11C 18 Cell - Control Rod Storage Rack 2FC26C 7 2FC12C 17 Cell - Control Rod Storage Rack 2FC27G 8 2FC13C 9 2FC14C 3 Cell - Control Rod Guide Tube and 10 2FC15C 5 Cell - Defective Fuel Storage Rack 2FC28C 11 2FC16C 12 2FC17C 13 2FC18C 14 2FC19C 15 2FC20C 16 2FC21C l

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.OARGENT Q LUNDY ENGlNEERS cmcaoo T-3758 Amd. 1, 08-01-86 1

5 113. CONFORMANCE WITH 10 CFR PART 21 The work indicated in this Specification and/or on the drawings as Nuclear Safety-Related requires the application of the provisions of Title 10, Chapter 1, code of Federal Regulations, Part 21, reporting of defects and. noncompliance (10 CFR Part'21). It is the responsi-bility of Contractor to implement the provisions.of 10 CFR, Part 21, insofar as they are applicable to Contractor's' Work under this Specification.

10 O

.-3 Final ? age n: Di.:sier .

E GARGENT & LUNDY ENGINEERS T-3758

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Amd. 1, 08-01-86

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( SPENT FUEL AND SPECIAL STORACE RACKS LA SALLE COUNTY STATION - UNITS 1 AND 2 DIVISION 2 - SUPPLEMENTS, STANDARDS AND DRAWINCS 201. SUPPLEMENTS The following are attached hereto and form a part hereof:

.201.1 Exhibit "A" - Purchaser's Ceneral Conditions dated February, 1979.

201.2 Attachment "A" - Commonwealth Edison Company Standard Quality Amd. 1 Articles - Revision 9 dated January 6, 1983 - As modified for Specification T-3758 (22 pages).

201.3 Form 30-B -

Standard Specification for Contractor's Drawing and Data Transmittal.

201.4 Envelope Spectra:

a. Service Level B - Spectra No. LC-1-NS, LC-1-ES and LC-1-VS, dated Amd. 1 12 Feb. 86.

(E1. 807'-0", Reactor Bldg. Slab, 2% Damping)

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b. Load Comb.

Level C 4% Damping -

Spectra No. Level C-NS; Level C-ES and Level C-VS, dated 13 Feb. 86.

(El. 807'-0", Reactor Bldg. Slab)

(The envelope spectra are drawn from the load combinations for' pool dynamic and seismic response spectra for service levels B and C) 201.5 Design Assessment Report, Section 4.4.3-NSSS, and BOP Equipment (Page 4.4-2).

201.6 Individual Response Spectra: Amd. 1

4. Operating Basis Earthquake (OBE) Response Spectra - Reactor Bldg.

al. North-South Component: Spectra No. 106-0B-NS, dated 4/26/73 a2. East-West Component: Spectra No. 106-0B-EW, dated 4/26/73 a3. Vertical Wall Response: Spectra No. 106-0B-VW, dated 7/20/73 107-0B-VW 108-OB-VW a4. Vertical Slab Response: Spectra No. 106-0B-VS, dated 7/20/73 107-0B-VS

() 108-OB-VS 2-1 i

GARGENTO LUNDY ENGINEER $

cwicaco T-3758 Amd. 1, 08-01-86

' N-hI a5. North-South Component: ' Spectra No. 107-0B-NS, dated 4/26/73 116-0B-NS 124-0B-NS a6. East-West Component: Spectra No. 107-0B-EW, dated 4/26/73 116-0B-EW 124-0B-EW a7. North-South Component: Spectra No. 108-0B-NS, dated 4/27/73 a8. East-West Component: Spectra No. 108-0B-EW, dated 4/27/73

b. Design Basis Earthquake (DBE) Response Spectra - Reactor Bldg.

bl. North-South Component: Spectra No. 106-DB-NS, dated 4/26/73 b2. East-West Component: Spectra No. 106-DB-EW, dated 4/26/73 b3. Vertical Wall Response: Spectra No. 106-DB-VW. dated 7/24/73 l 107-DB-VW >

108-DB-VW b4 Vertical Slab Response: Spectra No. 106-DB-VS, dated 7/25/73 ,

107-DB-VS-108-DB-VS b5. North-South Component: Spectra No. 116-DB-NS, dated 4/26/73 107-DB-NS 124-DB-NS b6. East-West Component: Spectra No. 107-DB-EW, dated 4/26/73 116-DB-EW 124-DB-EW

c. Safety / Relief Valve (SRN-AN & ADS) Response Spectra - Reactor Bldg.

cl. Vertical Slab Response, El. 807'-0": Spectra No. SS-113-VS, Rev. O c2. Horizontal Slab Response, El. 807'-0": Spectra No. SS-113-HS, Rev. O c3. Vertical Wall Response, El. 807'-0": Spectra No. SS-114-VW, Rev. O c4. Horizontal Wall Response, El. 807'-0": Spectra No. SS-114-HW, Rev. O c5. Vertical Response, Fuel Pool Slab: Spectra No. S5-115-VS, Rev. O e6. Horizontal Response. Fuel Pool Slab: Spectra No. SS-115-HS, Rev. O c7. Vertical Response, fuel Pool Wall: Spectra No. SS-116-VW, Rev. 0 2-la

SARGENT & LUNDY E N GIN E E R$

cmcaso T-3758 Amd. 1, 08-01-86 I'

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c8. Horizontal Response, Fuel Pool Wall: Spectra No. SS-116-HW, Rev. O c9. Vertical Slab' Response, El. 843'-6": Spectra No. SS-119-VS, Rev. O c10. Horizontal Slab Response, El. 843'-6": Spectra No. SS-119-HS, Rev. O cil. ' Vertical Wall Response, El. 843'-6": Spectra No. SS-120-VW, Rev. O c12. Horizontal' Wall Response, El. 843'-6": Spectra No. SS-120-HW, Rev. O

d. ' Safety / Relief Valve (SRV-Asymmetric) Response Spectra - Reactor Bldg.

dl. Horizontal Slab Response, El. 807'-0": Spectra No. SA-113-HS, Rev. O d2. Vertical Slab Response, E1. 807'-0": Spectra No. SA-113-VS, Rev. O d3. Horizontal Wall Response, El. 807'-0": Spectra No. SA-114-HW, Rev. 0 d4. Vertical Wall Response, El. 807'-0": Spectra No..SA-114-VW, Rev. 0 d5. Horizontal Response, Fuel Pool Slab: Spectra No. SA-115-HS, Rev. O d6. Vertical Response, Fuel Pool Slab: Spectra No. SA-115-VS, Rev. O d7. Horizontal Response, Fuel Pool Wall: Spectra No. SA-116-HW, Rev. O d8. Vertical Response, Fuel Pool Wall: Spectra No. SA-116-VW, Rev. O d9. Horizontal Slab Response, El. 843'-6": Spectra No. SA-119-HS.

Rev. O d10. Vertical Slab Response, El. 343'-6": Spectra No. SA-119-VS, Rev. O dil. . Horizontal Wall Response. El. 843'-6": Spectra No. SA-120-HW, Rev. O d12. Vertical Wall Response. El. 343*-6": Spectra No. SA-120-VW, Rev. O

e. Safety / Relief Valve (SRV-Single) Response Spectra - Reactor Bldg.

el. Horizontal Slab Response, El. 807'-0": Spectra No. S0-113-HS, Rev. O e2. Horizontal Slab Respcnse. Fuel ? 01: Spectra So. 50-115-HS, Rev. 0 2-;o '

i

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CARGENT O LUNDY ENGINEERS I c w ees.co T-3758 Amd. 1, 08-01-86 V e3. Horizontal Slab Response, El. 843'-6": Spectra No. 50-119-HS, ,

Rev. 0 l

e4. Horizontal Wall Response, El. 807'-0": Spectra No. S0-114-HW, Rev. O e5. Horizontal Wall Response, Fuel Pool: Spectra No. S6-116-HW, Rev. O e6. Horizontal Wall Response, El. 843'-6": Spectra No. S0-120-HW, Rev. O j e7. Vertical Slab Response, El. 807'-0" Spectra No. 56-113-VS, Rev. O e8. Vertical Slab Response, Fuel Pool: Spectra No. S0-115-VS, Rev. 0 [

l e9. Vertical Slab Response, El. 843'-6": Spectra No. S0-It9-VS, Rev. 0 e10. Vertical Wall Response, El. 807'-0": Spectra No. S0-114-VW, Rev. O ell. Vertical Wall Response, Fuel Pool: Spectra No. S0-116-VW. Rev. O e12. Vertical Wall Response, El. 843'-6": Spectra No. 50-120-VW, Rev. O

f. LOCA (Asymmetric Chugging) Response Spectra - Reactor Bldg.

A fl. Horizontal Slab Response, El. 807'-0": Spectra No. AC-311-HS,

(] Rev. O f2. Horizontal Slab Response, El. 815'-3": Spectra No. AC-313-MS, Rev. 0 ,

f3. Horizontal Slab Response, El. 820'-6": Spectra No. AC-315-HS, Rev. O f4 Horizontal Slab Response, El. 843'-6": Spectra No. AC-317-HS, Rev. O f5. Vertical Slab Response, El. 807'-0": Spectra No. AC-311-VS, Rev. O f6. Vertical Slab Response, El. 815'-3": Spectra No. AC-313-VS, Rev. O f7. Vertical Slab Response, El. 820'-6": Spectra No. AC-315-VS, Rev. O f8. Vertical Slab Response, El. 843'-6": Spectra No. AC-317-VS, Rev. 0 ,

I f9. Horizontal Wall Response, El. 807'-0": Spectra No. AC-312-HW, I Rev. O fl0. Horizontal Wall Response, El. 315'-3": Spectra No. AC-314-HW, Rev. 0 O

s1=

SARGENT & LUNDY ENGINEERS cmcaco T-3758 Amd. 1, 08-01-86 fil. Horizontal Wall. Response, El. 820'-6": Spectra No.-AC-316-HW, Rev. O f12. Horizontal Wall Response, El. 843'-6": Spectra No. AC-318-HW, Rev. O f13. Vertical Wall Response, El. 807'-0": Spectra No. AC-312-VW, Rev. O f14. Vertical Wall Response, E1. 815'-3": Spectra-No. AC-314-VW, Rev. O f15. Vertical Wall Response, El. 820'-6": Spectra No. AC-316-VW, Rev. 0 ,

i f16. Vertical Wall Response, El. 843'-6": Spectra No. AC-318-VW, Rev. O

g. LOCA (Condensation Oscillation Load Combination-1) Response Spectra - Reactor Bldg.

g l'. Horizontal Slab Response, El. 807'-0": Spectra No. CO-311-HS, Rev. 2 g2. Horizontal Slab Response, El. 815'-3": Cpectra No. CO-313-HS, Rev. 2 g3. Horizontal Slab Response, El. 820'-6": Spectra No. CO-315-HS, Rev. 2 j -

g4. Horizontal Slab Response, El. 843'-6": Spectra No. CO-317-HS, Rev. 2 g5. Horizontal Wall Response, El. 807'-0": Spectra No. CO-312-HW, Rev. 2 g6. Horizontal Wall Response, El. 815'-3": Spectra No. CO-314-HW, Rev. 2 l g7. Horizontal Wall Response, E1. 843'-6": Spectra No. CO-318-HW, Rev. 2 ,

I Vertical Slab Response. El. 807'-0": Spectra No. CO-311-VS, Rev. 2 g8.

g9. Vertical Slab Response. El. 315'-3": Spectra No. CO-313-VS, Rev. 2 g10. Vertical Slab Response. El. 320'-6": Spectra No. CO-315-VS, Rev. 2 g11. Vertical Slab Response, El. 843'-6": Spectra No. CO-317-VS, Rev. 2 l

g12. Vertical Wall Response, El. 807'-0": Spectra No. CC-312-VW, Rev. 2 !

i g13. Vertical Wall Response. El. 315'-3": Spectra No. CO-314-VW, Rev. 2 gl4. Vertical Wall Response. El. 543'-6": Spectra No. CO-313-VW, Rev. 2 f

2-;d

CARGENT G LUNDY ENGlNEERG cmcaso T-3758 Amd. 1, 08-01-86 gs

( ) h. LOCA (Condensation Oscillation Lead Combination-2) Response Spectra - Reactor Bldg.

hl. Horizontal Slab Response, El. 807'-0": Spectra No. CO-311-HS, Rev. 2 h2. Horizontal Slab Response, El. 815'-3": Spectra No. CO-313-HS, Rev. 2 h3. Horizontal Slab Response, El. 820'-6": Spectra No. Ce-315-HS, Rev. 2 h4. Horizontal Slab Response, El. 843'-6": Spectra No. Ce-317-HS, key. 2 h5. Horizontal Wall Response, El. 807'-0": Spectra No. CO-312-HW, Rev. 2 h6. Horizontal Wall Response, El. 815'-3": Spectra No. CO-314-HW, Rev. 2 i

l h7. Horizontal Wall Response, El. 843'-6": Spectra No. CO-318-HW, Rev. 2 h8. Vertical Slab Response, El. 807'-0": Spectra No. CO-311-VS, Rev. 2 A)

m. h9. Vertical Slab Response, El. 815'-3": Spectra No. CO-313-VS, Rev. 2 h10. Vertical Slab Response, El. 820'-6": Spectra No. CO-315-VS, Rev. 2 hil. Vertical Slab Response, El. 843'-6": Spectra No. CO-317-VS, Rev. 2 h12. Vertical Wall Response, El. 807'-0": Spectra No. CO-312-VW, Rev. 2 h13. Vertical Wall Rer. ? 'e , El. 915'-3": Spectra No. CO-314-VW, Rev. 2 h14. Vertical Wall Response, El. 843'-6": Spectra No. CO-318-VW, Rev. 2 201.7 Seismic Displacements:

a. Horizontal Seismic Model (Calc. No. 163, page 103, Rev. 1)

6. Probable Maximum Displacements - OBE. Horisontal Excitation. ,

(Table 18, Calc. No. 163, page 55 6 56, Rev. 1) l

c. Probable Maximum Displacements - DBE, Horizontal Excitation. !

(Table 18A, Calc. No. 163, page 57 6 58, Rev. 1) i

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CARGENT &.LUNDY ENGINEERS cmcaco -- T-3758-Amd.-l', 08-01-86

)

.y. 4 k 202. DRAWINCS The following Reference Drawings form a part hereof:

b 202.1- Mechanical Drawings:

M-Index Sheet 1- General Arrangement Index, Rev. D M-5 -

General Arrangement Reactor Building Floor Plan, Rev. D M-6 -

General Arrangement Reactor Building Floor Plan, Rev. L M-13 -

General Arrangement Section "A-A", Rev. F M-14 - General Arrangement Section "B-B", Rev. C l

M-15 -

General Arrangement Section "C-C", Rev. D i

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SARGENT & LUNDY E N G1N E E R S T-3758 L Bid, 07-17-85 g M-16 -

General Arrangement Section "D-D", Rev. E

(

M-17 - General Arrangement Section.; "E-E" and "F-F",

Rev. C M-96, SH.1 -

P&ID RHR System (Unit 1), Rev. AA M-96, SH.2 -

P&ID RHR System (Unit 1), Rev. AB M-98, SH.1 -

P&ID FC Syetem (Unit 1), Rev. Y M-98, SH.2 -

P&ID FC System (Unit 1), Rev. L M-144, SH.1 -

P&ID FC System (Unit 2), Rev. AA M-144, SH.2 - P&ID FC System (Unit 2), Rev. N M-841, SH.1 - FC System Piping (single liner) Unit 1, Rev. J M-841, SH.2 -

FC System Piping (single liner) Unit 1, Rev. U M-841, SH.3 -

FC System Piping (single liner) Unit 1, Rev. U M-841, SH.4 -

FC System Piping (single liner) Unit 1, Rev. R M-841, SH.5 - FC System Piping (single liner) Unit 1, Rev. M M-841, SH.6 - FC System Piping'(single liner) Unit 1, Rev. V M-841, SH.7 -

FC System Piping (single liner) Unit 1, Rev. K M-841, SH.8 -

FC System Piping (single liner) Unit 1, Rev. K M-841, SH.9 -

FC System Piping (single liner) Unit 1, Rev.-F M-841, SH.10 -

FC System Piping (single liner) Unit 1, Rev. E M-841, SH.11 -

FC System Piping (single liner) Unit 1, Rev. N M-841, SH.12 - FC System Piping (single liner) Unit 1, Rev. E f

M-841, SH.13 - FC System Piping (single liner) Unit 1, Rev. H M-941, SH.1 -

FC System Piping (single liner) Unit 2, Rev. E )

M-941, SH.2 -

FC System Piping (single liner) Unit 2, Rev. T M-941, SH.3 - FC System Piping (single liner) Unit 2, Rev. L M-941, SH.4 -

FC System Piping (single liner) Unit 2, Rev. K M-941, SH.S -

FC System Piping (single liner) Unit 2, Rev. H 2-2 j l

DARGENT & 'LUNDY l II E N GIN E erg i cmcaco T-3758 i Amd. 1, 08-01-86 k M-941, SH.6 ~- FC System Piping (single liner) Unit 2, Rev. U M-941, SH.7 -

FC System Piping (single liner) Unit 2, Rev. K M-941,'SH.8 -

FC System Piping (single liner) Unit 2, Rev. F M-941, SH.9 - FC System Piping (single liner) Unit 2, Rev. F i l

M-941, SH.10 -

FC System Piping (single liner) Unit 2, Rev. C 202.2 St'ructural Drawings:

a. Unit 1 S-214 - Reactor Building Floor Framing Plan El. 761'-0" Amd. 1 East Area. Rev. U S-215 - Reactor Building Floor Framing Plan El. 786'-6

West Area, Rev. AD S-216 - Reactor Building Floor Framing Plan El. 807'-0" East Area, Rev. H Reactor Building Floor Framing Plan El. 807'-0"

( S-217 -

West Area, Rev. AD S.218 - Reactor Building Floor Framing Plan El. 820'-6" East Area, Rev. AB S-219 - Reactor Building Floor Framing Plan El. 820'-6" West Area, Rev. AD S-220 -- Reactor Building Operating Floor Framing Plan El.

843'-6" East Area, Rev. AA S-221 - Reactor Building Operating Floor Framing Plan El.

843'-6" West Area, Rev. AP S-222 - Reactor Building Miscellaneous Floor Framing Plans, Amd. 1 Rev. AF S-223 - Reactor Building Framing Section 1-1 Lower Area, .

Rev. AC S-224 - Reactor Building Framing Section 1-1 Upper Area, Rev. AX S-225 - Reacter Buildiez Framing Se: tion 2-2 Lower Area, Rev. P 2-3

_ .-_ ._-_ ____ _-____-__-________ _ ___ O

CARGENT.O LUNDY E N GIN E E RS cmcaso T-3758 Amd. 1,.08-01-86

' \~') S-226 - Reactor Building Framing Section 2-2 Upper Area, Rev. T S-227- -

Reactor Building framing Section 3-3 Lower Area, Rev. E Amd. l' S-228 - Reactor Building Framing Section 3-3 Upper Area, Rev. L S-229 - Reactor Building Framing Section 4-4 Lower Area, Rev. AD S-230 -

Reactor Building Framing Section 4-4 Upper Area, l Rev. M l S-231 -

Reactor Building Framing Section 5-5 Lower Area, ,

Rev. R S-232- -

Reactor Building Framing Section 5-5 Upper. Area, '

Rev. AA-S-233 -

Reactor Building Framing Section 6-6 Lower Area, Rev. L

g. S-234 - Reactor Building Framing.Section 6-6 Upper Area,_

g ,) Rev. S S-235 -

Reactor Building Framing Section 7-7 Lower Area, ;

Rev. N , ;

S-236 - Reactor Building framing Section 7-7 Upper Area, i Rev. S S-237 -

Reactor Building framing Section B-3 Lower Area, Rev. W l

S-238 -

Reactor Building framing Section 8-8 Upper Area, Rev. U S-239 - Reactor Building Framing Concrete Column Schedule, Rev. C S-240 -

Reactor Building framing Concrete Column Sections and Details, Rev. C S-241 - Reactor Building Framing Concrete & Beam Schedule 1 Sheet 1, Rev. H S-242 - Reactor Bailding Framing Concrete Beam Schedule Sheet 2, Rei. H O

j

-L l

l

CARGENTQ LUNDY E N GIN E E RD ;

cwicao T-3758 Amd. 1, 08-01-86' .

f t .

S-243 -

' Reactor Building Framing Concrete Beam Schedule Amd. 1 )

Sheet 3, Rev. H' S-244 --

Reactor Building Framing Concrete Beam Schedule l Typical 1 Details, Rev. D

]

S-245 -

Reactor'Drywell Framing Sections & Details Sheet 9, Rev. AD S-246 - Reactor Building Framing One-way diab' Schedule -

Sheet 1, Rev. D S-247 -

Reactor Building Framing One-way Slab Schedule j Sheet 2, Rev. F i t.

S-248 - Reactor Building Framing One-way Slab Schedule Sheet'3, Rev. B S-249 -

Reactor Building Framing Two-way Slab Schedule Sheet 1, Rev. H 5-250 - Reactor Building Framing Sect. & Dets. Sheet 1, !

.j Rev. AK : j t .i S-251

~

~ Reactor Building Framing Sect.'& Dets. Sheet 2, {

Rev. AF 1

%J S-252 - Reactor Building Framing Sect. & Dets. Sheet 3,

( Rev. K

's-253 - . Reactor Building Framing Sect. & Dets. Sheet 4, Rev. T ;

S-254 - Reactor Building Framing Sect. & Dets. Sheet 5, {

Rev. U .

S-255 - Reactor Building Framing Sect. & Dets. Sheet 6, j Rev. S 1 S-256- - Reactor Building Framing Sect. & Dets. Sheet 7, Rev. AB S-257 - Reactor Building Framing Sections & Details Sht 8, Rev. W S-258 - Reactor Building Framing Sections & Details Sht 9, .

Rev. K S-259 - Reactor Building Framing Sect. & Dets. Sheet 10, Amd. 1 f- Rev. M s

2-4a l

l. _ _ _ _ _ _ _ _ _ - _ -

I 0 ARGENT & LUNDY EN GIN E E RO cmcAco T-3758 Amd. 1, 08-01-86 I r" s . Reactor Building Framing Sect. & Dets. Sheet'11,

{ J' S-260 -

Rev. T Amd 1 .

l S-261 - Reactor Building Framing Sect. & Dets. Sheet 12, Rev. P S-262 - Reactor Building Framing Sect. & Dets. Sheet 13, (

Rev. AJ l S-263 - Reactor Building Framing Sect. & Dets. Sheet 14, Rev. W S-264 - Reactor Building Framing Sect. & Dets. Sheet 15, Rev. Y S-265- - Reactor Building New Fuel Storage Vault, Rev. E i

S-266 - Reactor Bailding Foundation Sections & Details I Sheet 4, E tv. B ;

S-267 - Reactor Bui. ding Decontamination Pit, Rev. E S-268 - Reactor ShielJing Plugs Sections & Details Sheet 1, Rev. F S-269 - Reactor Shielding Plugs Sections & Details Sheet 2, O Rev. D S-270 - Reactor Building Framing Anchor Plate Schedule &

Details, Rev. J j S-271 - Reactor Building Embedded Plate Detail, Rev. D S-272 - Reactor Building Framing Section 9-9 Lower Area, j Rev. AC -

S-273 - Reactor Building Framing Section 9-9 Upper Area, ,

Rev. AB S-274 - Reactor Building Framing Section 10-10, Rev. G 1

Reactor Building Framing Sheet 16 Sections &

S-275 -

Details, Rev. D S-276 - Reactor Building Framing Section 5B-5B Upper Area, Rev. S S-277 - Reactor Building Trolley Beams Sections & Details,

. Rev. F S-278 - Reactor Building ~rolley Beams Sections & Details.

Rev. F

% I 1

2-Lo I

i

CARGENT O LUNDY ENGlNEEDS cmcaso T-3758 Amd. 1, 08-01-86 i

S-279 -

Reactor Building Framing Section SA-5A Upper Area, Amd. 1 Rev. W S-280 -

Reactor Building Framing Sections & Details Sheec 17, Rev. Y-S-281 -

Reactor Building Pool Liner Top Plan, Rev. J S-282. -

- Reactor Building Pool Liner Bottom Plan, Rev. H S-283 -

Reactor Building Pool Liner Sht 1 Sections &

Details, Rev. J S-284 -

Reactor Building Pool Liner Sht 2 Sections &

Details, Rev. K S-285 - Reactor Building Pool Liner Sht 3 Sections &

Details, Rev. K S-286 - Reactor Building Pool Liner Sht 4 Sections &

Details, Rev. J S-287 -

Reactor Building Pool Liner She 5 Sections &

Details, Rev. G S-288 - Reactor Building Pool Liner Sht 6 Sections &

Details, Rev. H S-289 -

Reactor' Building Pool Liner Sht 7 Sections &

Details, Rev. L S-290 - Reactor Building Pool Liner Sht 8 Sections &

Details, Rev. G S-291 - Reactor Building Pool Liner Sht 9 Sections &

Details, Rev. C S-292 - Reactor Building Pool Liner Sht 10 Sections &

Details, Rev. C S-293 -

Reactor Building Pool Liner Sht 11 Sections &

Details, Rev. F

b. Unit 2:

S-714 - Reactor Building Floor Framing Plan El. 786'-6" Amd. 1 East Area, Rev. Z S-715 - Reactor Building Floor Framing Plan El. 786'-6" West Area. Rev. AA l

2-tc i

l

1 SARGENT Gr LUNDY E N GlN E E RS emcaoo T-3758 Amd. 1, 08-01-86 Reactor Building Floor Framing Plan El. 307'-0"

} S-716 -

East Area, Rev. G.

S-717 - Reactor Building Floor Framing Plan E1. 807'-0" West' Area, Rev. AK

.S-718 - Reactor Building Floor Framing Plan El. 820'-6" East Area, Rev. Y S-719 - ' Reactor Buildin', Floor Framing Plan El. 820'-6" West Area, Rev. AH S-720 - Reactor Building Operating Floor Framing Plan El.

843'-6" East Area, Rev. AA S-721 - Reactor Building Operating Floor Framing Plan El.

843'-6" West Area, Rev. AC S-726 ~- Reactor Building Framing Section 202-202 Upper Area, Rev. M O

V 2-4d

'EARGENTO LUNDY ENGlNEERS CHIC A GO T-3758 Amd. 1, 08-01-86

() S-757 - Reactor Building Framing Sections & Details Sht 8, Rev. T S-758. -

Reactor Building Framing Sections & Details ]

Sht 9, Rev. C l S-759 -

Reactor Building Framing Sections & Details Amd. 1 Sht 10, Rev. C S-781 -

Reactor Building Pool Liner Top Plan, Rev. M S-762 -

Reactor Building Pool Liner Bottom Plan, Rev. H I

S-783 - Reactor Building Pool Liner Sht 1 Sections &

Details,.Rev. F S-784 - Reactor Building Pool Liner She 2 Sections &

Details, Rev. J S-785 - Reactor Building Pool Liner Sht 3 Sections &

Details. Rev. L S-786 - Reactor Building Pool Liner Sht 4 Sections &

Details, Rev. C S-787 - Reactor Building Pool Liner She 5 Sections &

.O Details, Rev. E S-788 - Reactor Building Pool Liner Sht 6 Sections &

Details. Rev. H S-789 - Reactor Building Pool Liner Sht 7 Sections &

Details Rev. C S-790 - Leactor Building Pool Liner Sht 8 Sections &

Details, Rev. C S-791 - Reactor Building Pool Liner Sht 9 Sections &

Details. Rev. E S-792 - Reactor Building Pool Liner Sht 10 Sections &

Details, Rev. D S-793 - Reactor Building Pool Liner Sht 11 Sections &

Details, Rev. D j

A-249 - Reactor Building Operating Floor Plan East Area j Unit 1, Rev. C A-250 - Reactor Building Operating Floor Plan West Area Unit ., Rev. M i

2-5 )

SARGENT & LUNDY ENGlNEEng l C"'C' T-3758 Amd. 1, 08-01-86 A-251 -

Reactor Building Operating Floor Plan East Area Unit 2, Rev. H

, i O

4 I

(

2-5a I

1 I

SARGENT & LUNDY .1 ENGlNEERS T-3758 Bid, 07-17-85 j I A-252' -

Reactor Building Operating Floor Plan West Area Unit

~b '2, Rev. M 203. MANUFACTURER'S DRAWINGS 203.1 The following manufacturer's reference drawings revised as indicated, form a part hereof:

a. General Electric:

al. 761E72O' -

' Defective Fuel Storage Container (Existing for ref.), Rev. 7 a2, 117C3280 Storage Rack for Control Rod & Defective Fuel (Existing for ref.), Rev. 1 a3. 117C3525 - Channel Storage Rack (Existing for ref.), orig.,

03-01-72

~

a4. 761E388'SH.1 -

Arrangement - Dual Plant Refueling Facilities, Rev. 9 761E388 SH.2 -

Arrangement - Dual Plant Refueling Facilities, Rev. 8 s 761E388 SH.3 - Arrangement - Dual Plant Refueling Facilities, Rev. 8 761E388 SH.4 - Arrangement - Dual Plant Refueling facilities, Rev. 8 761E388 SH.5 -

Arrangement - Dual Plant Refueling Facilities, Rev. 8 761E388 SH.6 - Arrangement - Dual Plant Refueling Facilities, Rev. 8 761E388 SH.7 -

Ar ingement - Dual Plant Refueling Facilities, Rev. 8 1 761E388 SH.8 -

Arrangement - Dual Plant Refueling Facilities, {

Rev. 8 l l

761E388 SH.9 - Arrangement - Dual Plant Refueling Facilities, I Rev. 8 761E388 SH.10 - Arrangement - Dual Plant Refueling Facilities, Rev. 8 761E388 SH.11 -

Arrangement - Dual Plant Refueling Facilities, Rev. 9 2-6

SARGENT & LUNDY ENGINEERS T-3758 Bid, 07-17-85 761E388 SH.12 -

Arrangement - Dual Plant Refueling Facilities,

'v Rev. 8 a5. 795E532 -

Equipment Storage Rack (Existing for ref.), Rev. O SHTS 1-4 a6. CE Documentation for Initial Core (The following Figures are used by permission of CE and are not considered proprietary information):

Figure 1 -

C-Lattice 100-mil Channel BWR 4/5 Figure 2 -

Distribution of Rod types and their Material Composition Figure 3 -

BWR 4/5 1.76 Bundle Figure 4 - BWR 4/5 2.19 Bundle Table 1 -

Cadolinia Rod Data Figure 5 - Initial Core Loading Hap Figure 6 -

Enrichment Distribution Map for 2.33 Average Enrichment a7. 117C4175 -

Control Rod Drive Outline, Rev. 4 a8. 814E935 -

Control Rod, Rev. 4 a9. 919D681 - Blade Guide, Rev. 2

( a10. 919D914 - Control Rod Guide Tube, Rev. 6 all. 922D217 - Spent Fuel Storage Racks (Existing for ref.), Orig.,

03-01-72 a12. 761E143 - Channel Outline, Rev. 2

b. Crane Deming:

19514 - Performance Curve for 1 & 2 FC01 PA & PB, Orig., 10-31-74 l t

203.2 The following data contains proprietary information for proposed fuel. This data will be furnished to the Bidder by the Purchaser upon request and acknowledgement of proprietary statement.

I Figure 7 - Proposed Enrichment Distribution for La Salle (18 month l cycle design) 204. DRAWINGS AND DATA (CONTRACTOR'S) 204.1 After notification of award, Contractor shall submit to the Consulting Engineers for review, certified drawings and data as follows:

l

a. As called for in Standard Specifications. i

b. Drawings showing general arrangement, principal dimensions and end

( ) connection details including removal clearances.

%)

2-7 1

SARGENT G LUNDY ENGINEERS !

cmcaco T-3758 Amd. 1, 08-01-86

~s

/ 1

\- / c. Dismantling drawings for existing pool condition,

d. Seismic reports and documentation.

e. Fabrication specifications.

f. Erection specifications and field erection drawings. ,

t

g. Licensing reports and certified design report.

a

h. Instructions and technical data for the removal of existing fuel j racks and associated structural support components.

i. Contractor's Design Report (to show compliance with the design requirements as given in the Specification). The report shall document adequacy of design and design verification in accordance with 10CFR50 Appendix B and ANSI 45.2.11.

j. Such other detail drawings of equipment, accessories and appur- I tenances as required by Purchaser.

k. Interface loads for Purchaser's evaluation of rack loads on spent fuel pool design.

,- ~s 1. The analysis, methodology, computer / analytical models, design data, assumptions, and detailed output results for all criticality

( ')

'- analyses.

m. Drawings / maps showing cell / racks designated for consolidated fuel rods which have a two to one consolidation ratio.

204.2 Contractor Drawing Submittal Requirements: Contractor shall send one sepia and three copies (suitable for microfilming) of the outline drawings to the Consulting Engineers for review within 4 weeks after notifications of award.

204.3 Contractor's drawings and documents shall list the parts to which the drawing or document applies. The Consulting Engineers will return for resubmission all drawings or documents which are not properly identified or which do not detail the correct equipment.

Additionally, all drawings and documents shall identify the Purchaser (Commonwealth Edison Company), the Station (La Salle County Station). Sargent & Lundy Specification (T-3758) and the Purchaser's purchase order number.

204.4 All engineering correspondence shall be addressed to Sargent &

Lundy, Attention: Mr. D. C. Haan, Project Manager. Reference may be made to the Sargent & Lundy engineer who asked the question. j Carbon copies af all letters snall be sent in separate envelopes to:

px H. L. Massin. Project Engineer. Commonwealth Edison Company Amd. 1 M. Vega, Mechanical Engineer. Sargent & Lundy 2-8

l 'GARGENT& LUNDY ENGlNEERS cmcaco T-3758

' Bid, 07-17-85 I

~

204.5 After. Award, one additional copy of all. letters (including transmittals) shall be sent to:

Traffic & Expediting Agent Commonwealth Edison Company P. O. Box 767 Chicago, Illinois' 60690-204.6 'If general " standardized" drawings are submitted for review which -

include devices which Contractor does not intend to supply for this Specification, then said drawings shall clearly show which devices are not to be supplied.. Drawing transmittals'not meeting this requirement )

will be returned to Contractor for. correction.

.204.7 Drawings and documents submitted to the Consulting Engineers are subject to review.. The review will be categorized in one of six categories, and the category will be notea by the Consulting Engineers by stamping the drawing when it is' returned to the Contractor. The six categories are:

Status 1 Review and no exception taken. Manufacturer can proceed with fabrication.

Status 2 Reviewed and Manufacturer can proceed based on making revisions noted and resubmit.

Status 3 Reviewed and Manufacturer is to revise and resubmit and hold fabrication.

Status 4 Drawing (s) has been received for identification only.

Status 5 Drawing (s) has been received for information only.

Status 6 Drawing (s) has been superseded by another draw-ing: .

204.8 Certain drawings, documents and manufacturer's instruction books may not require review by the Consulting Engineers. Such drawings and documents will be stamped Status 4, "For Identification Only"; or Status 5, " Received for Information Only."

204.9 When a drawing is transmitted to the Consulting Engineers for review i for the first time, contractor shall state that it is the initial transmittal on his transmittal letter or sheet. Subsequent trans-mittals, if required as a result of the Consulting Engineers' review, shall indicate the revision number or letter in the transmittal letter. l 204.10 After a drawing has been reviewed and resubmitted by Contractor as I required, Contractor shall note the revisions on the return drawing by the following methods:

l 4

2-9 3

______________-_._.___.______.______m____ ____ ________ __ _ _ _

SARGENT & LUNDY E N G l N E E "I D cwicaoo T-3758 Bid, 07-17-85

' (') a. Show the revised portion by encircling it, so that it is readily visible and the revision symbol is noted.

]1 J

b. In an appropriate space near the drawing title blocks, indicate the !

revision number or letter, and the signature of the authorized person who approved the revision, along with a brief description of the l- revisions.

c. If the number of revisions is more than three, Contractor's transmittal I letter must also include a description of the revisions, and the space near the title block on the drawings should refer to a document where a description of the revision may be found by the Purchaser.

204.11 Where alternatives are shown on drawings, the alternative being furnished shall be easily identifiable on that drawing.

204.12 At least four weeks prior to shipment, it shall be the Contractor's responsibility to obtain the Consulting Engineers' review categorized as either Status 1 or 2 on those drawings which cover items that are to be shipped. Contractor shall be liable for the costs of those field changes resulting from failure to adhere to this requirement.

204.13 Instruction Books: If applicable, Contractor shall furnish thirty (30) complete installation and operation manuals to the Consulting Engineers for all equipment furnished. These books shall be bound and complete

[, with an index or table of contents. Irrelevant material shall be

( carefully crossed out. Contractor shall also submit updated material as required to make the entire contents of the installation and operation sheets and/or manuals applicable to equipment as shipped.

Such submittals shall state what information is being replaced and/or what is additional information. " Pen and ink" changes will not be acceptable. Such submittals shall be made at no additional cost to the Purchaser.

204.14 Contractor shall provide Purchaser with the recommended maintenance procedure (s) required for equipment in order to maintain the equipment.

204.15 Latest revision of equipment drawings shall be used in the instruction I books.

204.16 Drawings shall be revised to reflect all change orders issued.

204.17 Weights of all parts greater than 50 lbs. shall be listed on the Drawings.

204.18 Drawings and instruction books shall be of sufficient detail to permit i easy repair and maintenance.

2-10

'O Final Page of Division 2

SARGENT & LUNDY ENGINEEMS T-3758 Bid, 07-17-85

.O SPENT FUEL AND SPECIAL STORACE RACKS

'Q LA SALLE COUNTY STATION - UNITS 1 AND 2 ;

i DIVISION 3 - TECHNICAL REQUIREMENTS 301. CENERAL 301.1 The work in general shall be as set.forth in the scope of work under Article 105'for the following equipments

a. Spent fuel storage racks.

b. Special storage racks (total of 40 storage cells / unit).

301.2 The storage rack design shall conform to the guidelines set forth in Article 109 for the storage of fresh uranium dioxide fuel at a level j of slight enrict 4ent in U-235.

l .. a. The initial fuel is uranium dioxide enriched to an average 3.20

l. weight % in U-235 with the remaining 96.8 weight % U-238. The dominant ved enrichment of the high and medium enrichment bundles is 3.2 and 2.2 weight % respectively. Cadolinia in the form of Cd,0 3 is selectively placed in fuel rods in the medium and high enriefiment bundles. The average axial distribution of gadolinia is provided in Table 1. Purchaser will supply Contractor proprietary data on Cadolinia distribution upon request and acknowledgment of proprietary statement. The low enrichment bundle, entirely natural O. uranium rods, with the medium and high enrichment bundle combine to produce a core average enrichment of 1.88%.

b. The fuel for reload cycles will have,the same basic zonal concept utilized in the initial core. Purchaser is considering other nuclear fuel fabricator proposals for reload fuel assemblies to support equilibrium 18 month cycles, and equilibrium 24 month cycles. The storage rack design shall be capable of accommodating a maximum rod bundle average enrichment of 4.25 weight % for the same fuel geometry as for CE 8x8 type "C".

301.3 The spent fuel storage racks shall be stored wet in the spent fuel storage pool as shown on Consulting Engineer's Drawings under l- Article 203.1. The spent fuel storage racks store the irradiated fuel removed from the reactor core in the vertical position until ready for shipment to a fuel storage center. The spent fuel storage racks shall be constructed from corrosion resistant materials which are compatible with the fuel assembly materials in a demineralized water environment normally at 120'F.

301.4 Defective fuel assemblies shall be stored wet in the spent fuel storage pool. Defective fuel assemblies shall be placed in sealed cans and stored in the special fuel storage racks.

O 3-1

. - __ _ . _ . _ _ ___ __-__ _ -___=

i SARGENTF2 LUNDY ENGlNEERS T-3758 I' Bid, 07-17-85

~'

301.5 The equipment shall be designed and fabricated for a service life of i (A 40 years.

301.6 Welding procedures, welders, and welding operators shall be qualified in accordance with Section IX of the ASME Boiler and Pressure Vessel Code. All rack erection will be by others.

L 301.7 The rack design shall be creative and shall optimize the use of the I spent fuel storage pool as shown on Consulting Engineer's drawings identified in Article 202. Contractor is to consider use of ,

asymmetric racks to fit the curvature of the spent fuel pool. The maximum storage of spent fuel assemblies is desired, subject to space / weight / seismic constraints and the necessary allowance for the storage of miscellaneous items.

301.8 Contractor shall perform the following analyses to support and license the rack designs

a. Seismic and pool hydrodynamic analysis for racks as discussed in Article 305.

b. The design basis criticality analyses shall be based on stored fresh fuel assemblies, w.th or without their channels, of maximum average bundle enrichment of 3.20 weight % U-235, moderated by pure non-borated water at a temperature within pool design limits yielding the largest reactivity. The analyses shall assess reactivity for g the uniform and distributed pin enrichment bundles shown in Fil.ures 1 through 5 of Article 203.la6.

c. Criticality analyses for fresh fuel assemblies, with or without their channels, of distributed pin enrichment with an average bundle enrichment of 4.25 weight % U-235 in an 8x8 Type C assembly geo-metry, stored in the design basis racks discussed in Article 301.8b, moderated by pure non-borated water at a temperature within pool design limits yielding the largest reactivity.

d. Criticality analyses for the same conditions discussed in Articles 301.8b and 301.8c except for consolidated fuel rods stored in the design basis racks discussed in Article 301.8b. Results of these criticality analyses shall not impose Purchaser to fuel bundle management requirements with the exception of zones where consoli-dated fuel rods shall not be stored, based on the results of the ,

fuel pool floor structural integrity evaluation.

e. Criticality analyses shall be performed for all the credible J abnormal occurences specified in paragraph 6.4.2.1.3 of ANSI /ANS 57.2. Criticality analyses shall be performed for any asymmetrically loaded cell or combination of cells storing consolidated fuel rods and for cells partially filled with consolidated fuel rods.

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,; N. Criticality and 301.Sepaleses ti:h alibe/discu, performed sed takiniiin Aiticlev credi{301.f.,b, fhd not taking QO1.8c, credit 301.8d(

for residual burnable r/oison. '

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g. Sensitivity vaalyses of 'the ,3f fech of d sigra pa'r/me its on Ke s

> "worstcase"criticalitranalysisforthedesignbu.srassIgor i ts- '

. cuss'ed in Article 301.8h. The effective neutron r,ul'tipih's. tion fac-t-# tor Kegg, shall be leas than or equal to 0.95, tir:cJudiai all 3

1

'unce,rtainties for all ' combinations c of desigfi pArarcters as discussed in Article 6.4 or MSI/Mi3,57.2. m

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/Contrdetoc 3shall verhy., i comparisukubhcritR41'dperimental I a < #d ata thad yhe benchmarpqd' cross iscri,nal' f values v.nd calculation y

_ ' method arg sirqar to (Fr,si for t!m duign basis racks discussed in f O

_ Article 391.bb.pcontra m.rL shall $r din a tabulation of the design

~V7 ' ' basis valu'es f or ithe variens uncertainties and biases used in the criticality calediations. i * '

f }

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, i. t ; Contractor shall perform a thermal-hydraulic analysis lO rdcordance V

' .with the requirements of SRr t9.1.3, Branch Teenical Pnfon A? CSS 9-2 and AN51/ANS 57.2 for the design basis sp4 ;consolidarh fuel rod aj -condition.6usingthedataprovidedinArticiep303,jnd30c.

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j.

Contractor's de' sign'shall allow adequat.t cooling,by Satural cir-culation and $y tfou provided by ts ffgent fuel pool hooling system f" -

,< en,maintai5/the, pisign limits spec fied in Article 303.9. Adequate f coc'ingimr1Nsithepthetemperatureofthefuelcladdingshallnot

[O'

' [, ij cauce/ lead tie strut,qdral f ailures and to saf ety c'oncerns.

's t & , ; ,

I j k. Cc M actor shrf.,no$ exceed during normal operations with the

~

coolingsystem(operational,amaximumpooltemperatureof120*F.

. Contractor shall not' exceed a maximum pool teinper'ature of 150'F Add.1

> q during' abnormal /emer~gency conditions wich the fuel pool cooling

![ system and Rny, heat exchanger backup ep'erational.

f, y 1. Contractor shall determine the time available to the Operating Staff Add.1

+ befci e pool water Will begin to boil, assuming abrupt lost of cool-ing systems. Centractor shall calculate the rate of water evapora-tion and the time to boil for the following two instants of times

11. When the bulk water temperature has reached its maximum value.

12. The inetant when the hest generation rate in the pool has reached i'ts peak value.

m. Contractor shall verify that direct gamma heating of the cell walls 3

y, and of the inter-cell water shall not cause boiling in the water channels between the fuel assemblies.

n. Contractor's thermal-hydraulic analysis shall include beyond the requirements of SRP 9.1.3 the fo asing two cases f or the design

basis and the consolidated fuel r.>d conditions. Contractor shall 1

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SARGENT & LUNDY ENGlNCERS T-3758 Add. 1, 09-09 535

-* use Branch Technical Position APCSB.9-2'to compute the:d'ecay energy-Purchaser's spent fuel discharge rate is four release rate.

assemblies per hour for'a reload of typically 240 assemblies.

~ Case I: 100 day refueling outage with a full core discharge 30 days after return to service.

Case II:- 100 day refueling outage with a full core discharge 90 days after return to service.

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SARGENT & LUNDY E N G i N E E A 'S T-3758

- '*** i Bid, 07-17-85 i

o. Contractor shall perform a flow area blockage analysis as part of the thermal-hydraulic evaluation to verify that the' rack design will not experience bulk boiling inside the cells. .j

p. Contractor shall evaluate the adequacy of existing fuel pool cooling systems for the design basis and consolidated fuel rod condition a heat loads. I 301.9 The Contractor shall guarantee to the Purchaser that the storage configurations proposed are licensable by the NRC, and the Contrac-tor shall aid the purchaser in making application and obtaining this license. If the rack design is not licensable under the rules, regulations, and interpretations in effect of notification of award of' contract, all modifications and adjustments shall be'to the Contractor's account.

302. DESICN AND FABRICATION 302.1 The spent fuel and special storage racks shall store irradiated fuel as specified in Article 301.2 in the vertical position. The racks will store BWR fuel assemblies, with or without the fuel channel, that can be lowered from above. The design shall be capable of storing consolidated fuel rods with a two to one storage capabil-ity. Contractor shall provide a drawing / map of the pool's floor indicating which cells in the rack arrangement can store consolida-ted fuel rods with a two to one consolidation ratio. !

302.2 The racks shall accommodate BWR fuel assemblies / bundles as outlined in manufacturer's drawings under Article 203.

302.3 Criticality in the fuel storage areas shall be prevented by physical systems or processes. Contractor shall use neutron absorbing alloy construction materials or other novel designs. Innovative designs will be considered only if the design has been reviewed and approved by the NRC.

302.4 The design shall include a margin for uncertainties in reactivity calculations, fabrication tolerances, fuel densification, accidents, and optimum moderation conditions. Contractor shall verify the design basis racks to a 95 percent probability at a 95 percent confidence level that the calculated Kegg plus uncertainties and biases is less than or equal to 0.95.

302.5 The storage cells shall be comprised of austenitic stainless steel and neutron absorbing material (poison) to achieve high corrosion resistance, structural integrity, attenuation of neutrons to prevent criticality, and protection of fuel from damage.

302.6 Contractor shall provide fabrication materials which will not gall the pool's liner plate or any sliding / turning components.

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SARGENT& LUNDY ENGINEEDS

. cMicroo T-3758 Amd. 1, 08-01-86 4

-( f 302.7 The racks shall be freestanding and self supporting. The rack supports shall permit remote adjustment from above through the i cells. The racks shall not be anchored or braced to the pool structure. l 302.8 Fabrication materials shall conform to the ASME Boiler and Pressure -

Vessel Code,Section III, Subsection NF, for Class 3 component supportr. or equivalent ASTM Specifications. Amd. 1 302.9 The materials of fabrication shall be procured in accordance with specifications,.which shall as a minimum, require material trace-ability chemical analysis and mechanical properties test. Weld filler material shall be procured in accordance with appropriate Contractor specification.

302.10 Contractor shall provide controls discussed in Section 5.8 of Purchaser's Standard Quality Articles, to the extent that identification and traceability of all fabrication materials can be produced for each individual cell in every rack. A drawing / map shall be provided for the purpose of identifying each cell in relation with a reference cell in each rack.

302.11 The nuclear and structural properties of the neutron absorbing material after exposure to radiation shall be verified by the results of a qualification program supported by test data and/or analytical ~ procedures.

302.12 The spent fuel and special storage racks shall be designed and fabricated to prevent inadvertent removal of the neutron absorbing material by mechanical or chemical means.

302.13 Provision shall be made in the design of the racks for coupon or other type inservice surveillance testing on a periodic basis throughout the life of the racks to verify the effectiveness of the neutron absorbing material.

302.14 The materials used in the construction shall be compatible with the storage environment of the racks and shall not contaminate the fuel assemblies with foreign particles or matter that would compromise the integrity or function of a fuel assembly during its lifetime, nor shall they contaminate the water in the storage pool. Materials that shall not contact fuel assemblies af ter final cleaning of racks are as follows:

a. Any material that contains halogens in amounts of 50 ppm, including chlorinated cleaning compounds,

b. Lead ,

c. Mercury i a d. Sulfur

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SARGENT& LUNDY ENGINEERS cwicaoo T-3758 l Bid, 07-17-85 i, i

e. Phosphorus

f. Zine

g. Copper and copper alloys

h. Cadmian

i. . Tin

j. Antimony

k. Bismuth

1. Mischmetal

m. Carbon steel, e.g., wire brushes

n. Magnesium oxide, e.g., insulation

o. Neoprene or other similar gasket materials made of halogen-containing elastomers.

p. Viton

q. Saran

r. Silastic Ls-53

s. Rubber-bonded asbestos

t. TFE (Teflon) containing more than 0.075% total chlorine (glass- ,

filled) and TFE films containing more than 0.05% total chlorine.

u. Nylon containing more than 0.07 total chlorine.

v. Polyethylene film (colored) with pigments over 50 ppm fluorine, measurable amounts of mercury or halogens, or more than 0.05% lead.

w. Grinding wheels that have been used on other than stainless steel or Inconel material.

x. Water containing more than 25 ppm halogens during any cleaning operation.

y. Any material that forms alloys or deposits on the fuel assembly.

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CARGENT & LUNDY ENG1NEEA5 cmcaso T-3758 Amd. 1, 08-01-86 303. DIMENSIONAL REQUIREMENTS-303.1 contractor shall provide sufficient clearance in each storage cell to preclude. misalignment and marring of the fuel bundle / assembly during insertion or removal. Contractor sitall maintain an interior functional gage of 6.00 inch plus or minus (1) 0.020 inch on side Amd. 1 throughout the length of the spent fuel storage cells.

303.2 The rack design shall provide adequate lateral clearance between the channel and the storage cell. The rack design shall provide sufficient lateral flow area and sufficient vertical flow area to preclude boiling.

303.3 The rack design shall provide means to effectively block spaces between storage cells to prevent insertion of fuel bundle / assembly.

303.4 The fuel assembly bottom bearing surface shall be in a plane perpendicular within 1/16 inch with respect to the plumb position (true vertical).

303.5 Length of storage cell shall permit ease of handling without compromising the integrity of the fuel assembly. Length of the storage cell shall not cover or obstruct entry paths to the bail handle.

303.6 All surfaces contacting fuel assemblies during loading and storage

-s shall be free of burrs, sharp corners, edges and weld beads or splatter which could mar or damage the fuel assembly surface.

Contractor shall assure against projection of fastners into the interior of the cell.

303.7 The finish of the rack surfaces contacting fuel assemblies shall be no rougher than 250 micro-inch RMS.

303.8 Contractor shall provide as a minimum, 1/8-in. radius or chamfer at all edges which potentially can contact the fuel assemblies. If edges are chamfered, blending shall be performed at all intersecting i edges. J 303.9 Spent fuel pool design parameters are as follows:

a. Spent fuel pool water temperature. *F................... < 120

b. Normal pool level is 22 feet above top of spent fuel racks. l

c. Fuel pool cooling pump flowrate... 3000 gpm

d. RHR Loop B pump flowrate (ased for emergency heat load).............. 7500 gpm 3-7

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SARGENT & LUNDY ENGlNEERS cmcaco T-3758 Bid, 07-17-85

e. Fuel pool heat exchanger capacity, 14.6x106 Btu /hr pool at 120*F based upon 1/3 of a core. irradiated for 3 years and stored in the pool for 1 year and 1/3 of a core irradiated for 3 years and stored in the pool-for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

[

f. RHR heat exchanger capacity, 42x106 Btu /hr pool'@ 120*F 16.8 x 10 7 Btu /hr pool at 212*F based upon 1/3 of a core irradiated for 3 years and stored in the pool for 100 days, and a whole core irradiated for 3 years and stored in the pool for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

3 Spent fuel water quality:

gl. Suspended solids, ppb............. 5 g2. Total dissolved solids as SiO2 , ppb................ ........ 25 g3. Total iron as Fe, ppb............. 5 g4. Total copper as Cu, ppb........... 3 g5. Sodium as Na, ppb................. 5 g6. Chloride as CL ppb................ 2

/ g7. Specific conductivity............. 3.0 mmho/cm at 25'F

\

g8. pH................................ 6.0 to 7.5 303.10 Rated crane capacities are as follows:

a. Main hoist........................ 125 tons

b. Auxiliary hoist.................... 10 tons

c. Hook travel distances for the main and auxiliary hoist............... 160 ft.

303.11 The grapple and hoist on the refueling bridge is provided with load sensing and limiting devices that are designed to the following load limits:

Fuel Aux.

Crapple Hoist (1bs) (1bs)

a. Load limiting switch.............. 1200 1000

b. Load sensing switch............... 486 485 1

, c. Stall torque of hoist system...... 3000 ft-lb 3000 ft-lb 3-8

CARGENT & LUNDY ENG1NEEA0

' cmcaso . T-3758 Amd.' 1, 08-01-86 h

( .303.12 Contractor shall' distribute the rack supports such that a six inch minimum clearance exists between the center lit.e of pool liner weld

'" seams and/or leak channels and the edge of the rack-supports.

Contractor shall maintain the minimum clearance under all design basis conditions.

303.13 contractor shall determine the minimum distance between the pool walls and boundary racks on the basis.of the structural and thermal-hydraulic' analysis results.

303.14 Contractor shall allocate' space in the spent fuel pool for the storage of refueling related equipment. Contractor shall use the Manufacturer's drawings in Article 203.la4 and the drawings in Article 202 to-determine the space required for storage of refueling related equipment, spent fuel racks and special storage racks.

Contractor's proposal shall explicitly state all assumptions made' for the space allocation on the pool floor.

303.15 Contractor shall size 43 special storage cells per unit capable of accommodating three control rod guide tubes, five defective fuel Amp. 1 assembly-in its storage container and 35 control rods. Contractor shall use the Manufacturer's Drawings (CE) Listed in paragraph 203.1(a) and a clearance allowance of 0.500 inch to design the '

cells.

304 DESIGN DATA 304.1 Peaksteagystateheat flux, cure 361787 Stu/hr ft ........................

(end of corelife condition axial peaking factor 1.4 at the bottom) 304.2 Individual channel flow rate at relative bundle power of unity for core plenum to plenum pressure drop of 24.8 psi are as follows:-

a. Central zone, 1b/hr............... 134.5 x 10 3

b. Peripheral zone, 1b/hr............ 69.0 x 10 3

c. Total bypass flow rate, M1b/hr.... 11.47 304.3 Ceneral reactor core description

a. Net Output, Mw,................... 1100

b. Thermal, Mw....................... 3323 c.. Capacity factors - cycle 1....... 0.791 cycle 2,3..... 0.700 cycle 4-7..... C.731

d. Inlet Subcooling, 3tullo.......... 527.o 3-9

SARGENT Sc LUNDY ENGINEERS cmc 4ao 4- 3758 Bid, 07-17-85 k 1035 e.. Pressure, psia....................

f. No. of assemblies / core............ 764

g. .No. of control rods / core.......... 185

h. Equivalent core diameter, inch.... 187.1

i. Overall core power density, kw/1 iter.......................... 50.0

j. Shape of control rod blade shade.. . Cruciform

k. Control rod pitch, inch........... 12.0

1. Blade thickness................... 0.260

m. Blade span, inch.................. 9.75

-n. Sheath thickness, inch............ 0.03

o. Material (blade).................. Stainless steel

~~ p. Tube diameter, inch............... 0.188

\ q. Tube wall thickness, inch......... 0.025

r. Poison length, inch............... 143.0

s. -Poison tubes, number.............. 76

t. Poison density.................... 70% TD ;

i 304.4 Fuel data (CE 8x8 type "C"):

a. Fuel material..................... UO 2

b. Fuel density...................... 95% TD

c. Burnable poison material.......... Cd23 0

d. Cladding material................. Zirc-2 9

e. Spacer cateria1................... Zirc-4/Inconel

f. End fittings and hardware materia 1.......................... Stainless steel

g. Channel material.................. Zirc-4 1

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!sARGENT G LUNDY ENGlNEERS cmcaco T-3758 Bi'd, 07-17-85

, [ h. Fuel bundle weight (less channel):

L, bl. Fuel, 1b.......................... 402.8 th2. Cladding (w/end plugs), 1b........ 123.3 h3. 7 spacers (TOTAL), 1b............. 5 h4. End fitting and hardware, Ib...... 21 h5. Total bundle weight, 16........... 600 (approx.)

1. Channel weight, 16................ 80

j. fuel rod.00, inch................. 0.483

k. Fuel pellet OD, inch.............. 0.410

1. . Cladd thickness, inch............. 0.032

m. Water rod OD, inch................ 0.591

n. Cladding thickness of water rod,'

inch.............................. 0.030

/~' o. Active fuel length, inch.......... 150 t

p. Number of rods per assembly.......' 64

q. Number of water rods per assembly.......................... 2

r. Weight.of UO2 per rod, 1b......... 7.4 (approx.)

i

s. Coretotg1 heat transfer area, ft ......................... 74871

t. Core inlet temperature, 'F........ 532.8

u. Maximum fuel temperature, 'F...... 3435 305. STRUCTURAL REQUIREMENTS 305.1 The design and analysis of the spent fuel and special storage racks shall be performed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NF. The racks shall be classified as ANS Safety Class 3, ASME Code Class 3 component supports, and Seismic Category I structures. The design shall comply with the following.

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SARGENTe LUNDY l ENG1NEERO cmcaso T-3758 Amd. 1, 08-01-86 in f \'

V 305.2 Contractor's structural analysis for the racks shall be in accordance with Article 305.1 for all anticipated loadings including . i seismic forces, pool hydrodynamic forces (SRV, CHUCCING, CONDENSA- f TION OSCILLATION), pool slosh forces, impact forces from accident I and abnormal occurrences, thermal forces, applied loads and deadioads. The accident and abnormal forces shall include cases (a), (b), (d), (f), (h) and (i) of paragraph 6.4.2.1.3 of ANSI /ANS 57.2.

305.3 Contractor's rack design shall be such that deformations are limited '

to preclude criticality for all plant conditions. The rack design shall also limit physical damage to the extent that permits normal insertion and removal of fuel during the plant conditions discussed in paragraph 6.4.2.4 of ANSI /ANS 57.2 305.4 Contractor shall design the racks for the effects of seismic and poci hydrodynamic loads (including LOCA). A non-linear analysis Amd. I shall be performed to predict the amount of rack sliding and tipping, in addition to the loads. Contractor's in-house computer program called RACK 0E shall be used in lieu of a three dimensional analysis. Contractor shall develop a two dimensional model and adequately incorporate the stiffness, mass and damping charac-teristics of the racks and pool. The dynamic analysis shall be in accordance with SRP 3.7 and Regulatory Guide 1.92.

(y 305.5 Contractor shall for the purpose of performing the detailed dynamic analysis generate an artificial acceleration time history from the combined response spectra provided under paragraph 201.4.

305.6 Contractor's detailed dynamic analyses shall use damping values of 2% and 4% of critical damping for the upset and emergency service levels respectively.

305.7 Contractor's rack design shall include the forces from sliding and overturning due to dynamic loads, and limit the maximum angle of tilt to not exceed one-half of the overturning angle. Fuel damage !

or reduction in required margin to criticality due to impact shall not be allowed. ]

l 305.8 Contractor shall use coefficient of friction values of 0.2 and 0.8 l to determine the maximum response generated by the sliding and ]

overturning analyses considering full, partially filled and empty )

racks. Contractor shall perform the sliding and overturning i analyses for the design basis and consolidated fuel rod conditions.

305.9 Contractor shall maintain limits specified in Article 305.14 for the Amd. 1 design basis and consolidated fuel rod conditions. Contractor shall provide Owner a drawing showing the total local fuel rack / pool floor interface loads at each rack support location.

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CARGENT & LUNDY ENGlNEEQO esicaoo T-3758 Amd. 1, 08-01-86

,m

(, ) 305.10 Contractor shall determine by analytical means and/or testing the maximum kinetic energy that cells / racks can absorb without damage or violation of criticality criterion from the fuel handling accident analysis.

305.11 Contractor shall perform a detailed stress analysis of the racks using the loads and load combinations specified in paragraph 305.12. Contractor shall compute and verify that the maximum Amd. 1 stresses at all critical locations maintaining the code stress limits and no change in cell and/or rack geometry of a magnitude which violates the criticality acceptance criterion.

305.12 The load combinations that shall be considered are specified below and are in accordance with the Design Assessment Report referenced in Article 201.5. Contractor shall specify the evaluation method for the load combinations examined. Contractor shall use the load combinations in Appendix D of Section 3.8.4 - II.3 of the SRP with the following changes:

a. Replace E with UCBV.

b. Replace E' with FCBV.

c. UCBV is defined as the loads generated by the service level B artificial acceleration time history and FCBV is defined as the

(' loads generated by service level C artificial acceleration time history.

305.13 The spent fuel and special storage racks shall be capable of withstanding a force equal to the maximum lifting capacity of the spent fuel pool bridge hoist, applied, at any point, without damaging the racks to the extent that the stored fuel configuration violates the criticality acceptance criteria. The maximum lifting capacity of the spent fuel pool bridge hoist is specified in Article 303.11.

305.14 The load capacity of the spent fuel pool is limited to 3500 lbs/ft 2 due to the dead weight of the racks and the fuel assemblies or 5920 lbs/ft2 due to the dead weight of the racks fuel assemblies and the water in the pool. The above limit includes the dynamic loads due to seismic response based on an evenly distributed rigid load.

305.15 Contractor shall provide any analyses necessary to certify the structural integrity of the racks.

305.16 Purchaser reserves the option to request a detailed structural analysis of the spent fuel pool including dynamic loads to determine the maximum loading capacity. Contractor shall include a price for this analysis in the Proposal.

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SARGENTErLUNDY ENGINEER 9 cmeaoo T-3758 Amd. 1, 08-01-86 l

,y f 305.17 The material specified for the Spent Fuel Pool Liner Plate is Amd. 1 i SA-240, Type 304, hot rolled, annealed and pickled and then I processed by cold rolling.

305.18 The concrete specified for the spent fuel pool walls is denoted on the S&L drawings as BA-40 and BA-45, corresponding respectively to compressive strengths of 4000 psi and 4500 psi. The concrete fill I specified for the La Salle project has a strength of 2000 psi.

u 305.19 The shipping cask storage area is designed for a dead lead of 100 tons. The new fuel storage vault floor slab is designed for a dead-load of 2000 pounds per square foot (psf) while the cover over the vault is designed for a live load of 480 psf.

305.20 The design basis live loads for the Reactor Building floors at elevations 843'-6", 820'-6" and 807'-0" are respectively, 1050 psf, 450 psf and 450 psf.

305.21 Reinforcing steel consists of full size deformed bars meeting the requirements of ASTM A615-72 (per FSAR Appendix page E.2-1). Grade classifications are as follows:

a. Sizes #3 to #11 are grade 60.

b. Sizes #14 to #18 are grade 50.

bl. Grade 50 bars are specially ordered reinforcement modified so obtain a guaranteed minimum yield strength of 50 ksi and a minimum ultimate strength of 75 ksi but maintaining a ductility of 12% elongation in an 8 inch gage length. ,

305.22 The normal, abnormal and accident condition temperature for the spent fuel pool walls are respectively, 120'F, 150'F and 212*F.

306. INSPECTION AND TESTING 306.1 Contractor shall specify the met' hod of inspection and the acceptance / failure criteria for all structural welds. The weld inspection shall comply with the requirements of Section III of the ASME B&PV Code and ANS 57.2 306.2 Contractor shall verify after fabrication by testing that each cell can accommodate a dummy fuel assembly and defective storage cannister. Contractor shall verify after fabrication, by mandrel Amd. I testing, that each cell has a minimum interior dimension of 5.980 inches on side. The test shall be performed using a three plate mandrel, each ptate having an exterior dimension of 5.975 inches on side.

307. PAINTING 307.1 The stainless steel rack surfaces snail not require painting.

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SARGENT O LUNDY l ENGINEERS i cmcaoo T-3758 Amd. 1, 08-01-86 I

308. TOOLS 308.1. Contractor shall furnish one complete' set of all special tools, instruments and fixtures not normally furnished by equipment erectors or the Plant Constructor but required to transport, erect, adjust, dismantle, service and/or maintain the equipment. l'urchaser will determine whether special tools, instruments, and fixtures will be purchased or leased.

308.2 Tools shall be compatible with the intended use and shall be new and of first class quality.

308.3 Tools shall be shipped to the project site in a suitable separate container, clearly marked with the name of the equipment for which the tools are intended. >

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Attcchn:nt A Spec. No. T-3758 Issue: 11d,.07-17-85

'! Revision 1, (cated 2/18/77) 1 k- Revision 2, (dated 3/7/77) (By QA) J Revision 3, (cated S/16/77' (By SNED) i Revision 4, (dated 1/20/76) (By SNED) !

Revision 5, (dated 11/1/73) (By QA)

Revision 6 (dated 12/3/79) (By SNED)

Revision 7,(dated 7/1/80) (By SNED) l Revision 8, (dated 12/1/81) (By SNED) '

Revision 9, (dated 1/6/83) (BySNED)

Commonwealth Edison Company Standard Quality Articles Section 1 - Ouelity Assurance 1.0 Quality Assurance Program:

1.1 Tne contractor shall be reovired to have an acceptable Quality Assurance Program which will be in effect for the duration of the (9 contract. The Quality Assurance Program shall include the Quality

%J assurance system, organization, policies, responsibilities, listing of I

procedures and/or requirements for processes necessary to control cuality throughout all phases of tne contract. Tnis program shall meet the requirements of 10CFR50, Appendix B and must address, as applicable, the reavirements delineated in Article 5.0, " Acceptance Criteria". Acceptable guices for meeting these requirements are ANSI N ;

45.2, " Quality Assurance Requirements for Nuclear Power Pl' ants", plus applicable associated ANSI N 45.2 daughter documents, and Article NCL )

4000 of ASME Boiler and Pressure Vessel Code,Section III. The prrgram j 1

must be accepted by tne purchaser prior to award of contract.

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O 2.0 Quality Assurance Program Approval:

2.1 Before any contractor can be considered acceptable for. an award of contract, he must have submitte: an acceptable Quality Assur.ance Program. In order to be considered as acceptable, the program muAt; address, as applicable, the requirements delineated in Art.i.cle ,1.0 above.

2.2 If the contractor's program does not cover all of the requiremen.ts .in detail, he must state when and how the requirements do not apply. This j statement of non-applicability must be substantiated.

2.3 Comitments accepted by the purchaser as a condition of award shall be, implemented by the contractor immediately upon award of contract. ,

fhese comitments shall require the contractor to make written changes O to the program in the form of revisions or supplements to the program, t

The supplement shall be controlled in the same manner as the manual, ,

and considered as an auditable part of the program. I 2.4 The control of the accepted Quality Assurance Program is the responsibility of the contractor. Contractor shall promptly notify the purchaser of all revisions to the Quality Assurance Program for the duration of the contract. g revisions to the accepted Quality Assurance Program shall be implemented on the purchaser's work by the contractor without the purchaser's written approval of the Program revision.

Page 2 of 22

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( )t 3.0 Quality Assurance Program Submittal with Proposal:

3.1 A contractor who has written acceptance by the purchaser and a l controlled copy of the accepted Quality Assurance Program assigned to the Manager of Quality Assurance, Commonwealth Edison Company, need only submit documented verification that the controlled copy is l applicable to the scope of work involved in the bid, and include infonnation with the proposal covering the current effective date of the program manual, including all current revisions and supplements in effect.

3.2 A contractor, who does not have an accepted and controlled copy of his Quality Assurance Program as described in Article 3.1 above, shall A submit to the purchaser with his bid two (2) controlled copies of his V Quality Assurance Program f or review and acceptance, one assigned to the Manager of Quality Assurance and the other assigned to the Station Nuclear Engineering Manager.

4.0 Quality Assurance Program Submittal Af ter Award:

4.1 Af ter awarc, if the contractor meets the requirements of 3.2 above, he must submit three (3) uncontrolled copies of the accepted Quality Assurance Program to the purchaser.

4.2 A'f ter award, if the contractor meets the requirements of 3.1 above, the contractor must submit four (4) copies of the accepted Quality Assurance Program. One (1) copy must be controlled and essigned to the Station Nuclear Engineering Manager and the three (3) remaining uncontrolled. I Page 3 of 22

After award, if contract is for more tnan one station, the contractor l

4.3 l must submit two (2) additional uncontrolled copies for eacn additional station.

4.4 After award, any revisions to the accepted quality assurance program which the purchaser approves, the co1 tractor must submit copies of the l accepted revisions for the uncontrolled ar.d controlled manuals in the purchas,er's possession for the duration of the contract. .

4.5 'Those contractors, whose awarded contract applies only to work performed off-site need not submit uncontrolled copies as indicated in 4.1, 4.2 and 4.3 above unless stipulated in the contract.

5.0 Quality Assurance Program Acceptance Criteria

5.1 Organization

A. The contractor's Quality Assurance Program shall include an organization chart identifying key positions and the reporting relationship between the Quality Assurance personnel and management (including field Q. A. organization, if applicable). All Quality related activities which are referenced in the manual must be assigned to specific personnel. The Quality Assurance personnel shall have:

1. Written responsibilities for cuality related job positions.

2. Authority and organizational freedom to:

identify and evaluate problems a.

b. recuire and implement approved corrective actions

c. control further processing, where appropriate action such as "stop work" may be reovired.

' 3. Independence from Procurement, Manufacturing, Fabrication, Scheduling and Construction groups.

Page 4 of 22

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- 5.2 Quality Assurance Program:

A. The contractor's Quality Assurance Program must be formally accepted by Company Management with a signed policy statement.

This Program shall be implemented through written procedures and/or instructions or they shall be established to ensure that the subject's work is accomplished in compliance with the appropriate code and procurement requirements. .

B. Provisions for training Quality Assurance personnel performing These activities affecting Quality shall be a part of the program.

provisions must include how this training is accom;ilished and who is responsible f or its implementation.

C. Provisions for a review of the status, adecuacy, implementation and effectiveness of the total Quality Assurance Program on a specific

\- time senedule shall bE a part of the Program.

D. Provisions shall be est&Dlished in the Program f or the controlled ,

issuance of the latest revision to ,the Quality assurance manual, procedures and instructions.

E. Included in the Program is a commitment that the program applies to safety-related work, and complies with 10 CFR 50 Appendix B and/or ANSI N 45.2.

F. The Program shall delegate responsible individual (s) to sign-off on Certificates of Confonaance and/or Compliance. .

5.3 Design Control: .

A. Kaasures to assure that the design basis for the systems and/or components are correctly translated into specifications, drawings, procedures, and instructions as appropriate, shall be described.

Tnese measures shall include provisions to insure that appropriate cuality standards are specified and included in design documents.

Page 5 of 22

O B. The design control measures for independent verification or check j

of the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational

~

methods, or bl/ the performance of a suitable testing program shall; be described.

C. Means by which the contractor will insure that design changes are subjected to design control measures commensurate with those applied to the original design shall be described.

'5.4 Procurement Document Control:

A. Measures to assure that purchase documents for procurement of material, eauipment, and services, whether purchased by the l

contractor or his subcontractor are reviewed for inclusion of O ouality requirements shall be described in the Program.

V Subcontractors shall be required to provide to the contractor a Quality Assurance Program consistant with the requirements of the contractor's Q. A. program f or review and acceptance by the i contractor. The contractor will be responsible for determining the Quality Assurance requirements to be applied to his subcontractors.

5.5 Instructions, Procedures and Drawings:

A. Activities affecting Quality shall be prescribed by documented work procedures or instructions, as appropriate, and accomplished in accordance with these documents. Procedures or instructions shall include appropriate acceptance criteria for work performance and quality compliance. The above measures shall be described in the Program.

1 Page 6 of 22

l e

5.6 Document Control:

A. Measures to control the issuance of the latest applicable documents such as instructions, procedures, drawings, purchase requirements H and confirmatory documents such as tast reports, including changes thereto, which prescribe activities affecting Qur.lity shall be described. These measures shall assure that documents including i

changes are reviewed for adequacy and approval for release by ,

authorized personnel and are distributed to and used at locations where the prescribed activity is performed. Also to assure that obsolete drawings, specifications and instructions have been destroyed or isolated from use.

5.7 Control of Purchased Material, Eauipment and Services:

A. Measures to assure that purchased material, eauipment and services, whetner purchased directly or through subcontractors, conform to the procurement documents shall be described. These measures shall.

l include provisions, as appropriate, for source evaluation and selection, objective evidence of avality furnished by contractor or subcontractor, inspection at the contractor or subcontractor source, and receiving inspection for compliance with ' procurement documents upon delivery. The effectiveness of Quality Control by contractor or subcontractors may be assessed by purchaser or his designee at intervals appropriate to the importance; complexity, and cuantity of the components being purchased or fabricated.

O Pac @ ] @7 88

l O )

Identification and Control of Materials, Parts and Components: f 5.8 !

A. Mensures for the identification and control of materials, parts, j and components, including partially fabricated assemblies, shall be' '

described. These measures assure that identification and traceability of the item is maintained by heat number, part number, serial number or other appropriate means as required throughout fabrication, erection and installation. These identification and

control methods shall be designed to prevent the use of incorrect or defective materials, parts and components.

5.9 Control of Special Process:

A. Measures to assure that special processes, including welding, heat treating, and nondestructive testing, are controlled and accomplished using oualified personnel and approved procedures, with certifications as reouired, and in accordance with applicable codes, standards, specification criteria and other requirements shall be described Documentation involving the work shall be maintained for cualified and/or certified personnel, process qualifications, and procedures. l 5.10 Inspections:

A. Tne inspection program for activities affecting Quality that is established and executed by or for the contractor and his subcontractors to verify conformance with documented instructions procedures, and drawings shall be described. Such inspection shall be performed by cualified personnel, with certification as reoutred, other than those who performed the activities being inspected. Tne Program shall identify the person responsible for the training, documentation of this training, and maintance of the training records.

B " O A NN _ _ _ _ _ _ _ _ - _ _ _ -

i I

fN d j E.- There shall be provisions in the Program for establishing After ,

aware of contract, customer inspection hold points. Where f i

mandatory inspection hold points are' required, the specific hold points will be indicated in the appropriate documents.

C. The Program shall have provisions for documenting and retaining all

- inspection results.

5.11 Test Control:

A. A test program shall be established to insure that any testing recuired to demonstrate that the systems and/or components perform satisf actorily in service is performed by cualified personnel, with certification as required, in accordance with written test procedures which incorporate the requirement and acceptance criteria and limits contained in specifications. Test procedures shall include provisiens f,or assuring that all prerequisites for the given test have been met, that adequate and calibrated test instrumentation is available and used, and that the test is performed under appropriate environmental conditions.

B. The Program shall have provisions for documenting, evaluating, and )

i retaining all test results.

5.12 Control of Measuring and Test Ecuipment: i 4

A. Measures shall be established in the Program to assure that tools, ,

gauges, instruments and other measuring and testing devices used in activities affecting auality are properly issued and controlled.

To assure accuracy the equipment shall be calibrated, adjusted and I

Page 9 of 22 i

i

~k maintained at prescribed intervals or prior to use against certified eouipment having known valid relationships to the National Bureau of Standards or other recognized applicable standards.

b, .4 cords shall be maintained and touipment suitably marked (such as tag, sticker, etching, etc.) to verify calibration status.

5.13 Handling, Storage and Shipping:

A. Measures established to control handling, storage, cleaning, packaging, and preservation of material and equipment to prevent damage or deterioration shall be described.

Measures established to provide adequate marking and labeling for B.

packaging, shipping and storage of items shall be described. '.

f3 V C. Measures shall be established in the Program to provide adequate procedures for issuing, controlling, and identification of materials. ;

5.14 Inspection. Test and Operating Status:

A. Measures establi:hed to indicate by the use of controlled markings such as stamps, labels, travelers, etc. to assure that parts, supplies and assemblies are identified as to their status of inspections and tests performed shall be described. These measures ]

shall include procedures for control of status indicators including the authority of application and removal of tags, marking,. labels l and stamps. ]

i O .

Page 10 of 22

^ 5.15 Nonconforming Materials, Parts or Components:

U-

~

A. Measures established to control materials, parts or components which do not conform to requirements in order to prevent their inadvertent use or installation shall be described. These measures shall include procedures for identification, documentation. {

segregation, disposition and notification to affected organizations. Nonconfonning items shall be reviewed and properly dispositioned as to acceptance, rejection, repair or rework in accordance with documented procedures.

5.16 Corrective Action:

A. Measures shall be established to assure that conditions adverse to Quality are promptly identified and corrected. The identification of the adverse condition, cause of condition and the corrective action taken to prevent continuing re-occurrence of like conditions shall be documented and reported to appropriate levels of management. .

5.17 Quality Assurance Records:

A. Records shall be mairlained to furnish evidence of activities affecting Quality and the measures that Will assure prompt and complete delivery to the purchaser of those documents reauired by the specification. The contractor shall meet the requirements of applicable codes and ANSI Standards concerning record retention I such as being identifiable and retrievable, duration of retention, ;

location and assigned responsibilities. The O !

l i

Pace 11 of 22 {

1

____ - _ - _ 0

1 1

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A j U minimum records maintained, where applicable, shall be receiving, )

in-process, assembly, test, final, packaging / shipping inspections, I

personnel, procedures, process qualification records for special ]

processes, training records for auditors, inspectors and testers, k and submittal of subcontractor cuality control records (i.e. CMTR's and certificates or conformance and/or compliance, etc.).

5.18 Audit:

A. Measures established to provide a comprehensive program of planned and scheduled audits to be carried out to verify compliance with all aspects of the Program and to determine the effectiveness of that Program shall be described. Tnis plan shall include both seneduled internal audits and, where appropriate, external (subvendor/ subcontractor) audits.

Vendors performing on-site work, a senedule of on-site audits will be ceveloped with the following considerations.

1) As early in the life of the activity as practical i

2) On intervals consistent with the schedule for accomplishing the activity.

3) Commensurate with the status and importance of the activity.

B. The Program shall provide for audits to be conducted in accordance with written procedures and/or checklists by trained and certified audit personnel not having direct responsibilities in areas being i 1 .

l audited. A description shall be provided in the Program of Auditor !

i training activities with Qualification and certification reautrements. Inis shall include a description of training activities, a delegation of. responsibilities for performance of 1

these activities, and documentation of these activities.

Page 12 of 22 o----_--------_

g O

V !

i C. Audit results shall be occumented with objective evidence, distributed, and an archival file shall be maintained. The audit 1

results shall be reviewed by management having resporisibilities for {

l the area being audited.

^

D. Follow-up action, including re-audit of the deficient area (s) to assure corrective action has been accomplished shall be described in Program.

Section II - Quality Control 1.0 Quality Control Document Submittal with Proposal 1.1 Certificate of Authorization ( ASME):

A. When applicable, the contractor shall submit with his Quality Assurance Program a copy of his current ASME Certificate of Authorization, if a Certificate of Authorization has not been issued, then a copy of his current interim letter of Authorization from the ASME is reauired.

1.2 Quality Control List:

A. ine contractor shall include with his proposal an index of Quality Control Procedures to be applied to the work. .

B. The contractor shall submit with his proposal for inclusion into the contract awarded, a detailed list of the documents and l documentation, which will be furnished prior to or concurrent with a

shipment. This proposed list of documents and documentation shall ;

include all Code recuired permanent records.

O V

Page 13 of 22 i l

1 l

l l

I

kl.0 Quality Control Document Submittal af ter Award:

2.1 Quality Control Procedures:

A. 'Within six weeks after an award of contract, the contractor should submit the detailed procedures to be used or~ a schedule for submitting these procedures. Procedures governing work that is to be perfonned off-site shall be submitted to the purchaser's consulting engineers' Quality Control Division for review and acceptance. Procedures governing on-site work shall be submitted to the Station Construction Site Project Superintendent for review and acceptance by the purchaser. Schedules for submitting procedures shall be submitted in a similar manner.

NOTE: A contractor shall not start any work covered by these i O procedures until the appropriate procedures have been accepted

%d in writing by the purchaser and/or the purchaser's consulting engineer as appropriate, t B. The Quality Control Procedures shall contain those administrative procedures necessary to implement each (Section 5.1 through 5.18) of the Quality Assurance Program described above. The procedures shall designate who is responsible for the implementation by each of the departments stated in the Quality Assurance Program and define the authorities and duties of all personnel associated with Quality control. The procedures shall detail how all elements affecting the product cuality will be processed and shall include the specification of the necessary documentation. Personnel perfonning design activities shall be cualified to perform these activities as established by the t'

( contractors internal system of qualification.

Page 14 of 22 i

.______________o

1 l

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C. Quality Control Procedures shall also contain these design, .

l manuf acturing, testing, inspection, cleaning, etc., procedures l l

necessary for the accomplishment of the work and to assure its proper l

Quality. Procedures shall be cualified as necessary to Code or I i

Standard Requirement. Tnese procedures shall detail what equipment is to be used, limiting conditions, acceptance criteria, techniques, etc.,

that will be used. These procedures shall include, as applicable, the following: (The specification writer is to list the procedures recuired or reference wnere the recuirec procedures are listed in the specifications):

a. Welding procedure and welding procedure qualifications Aedi:;r:phy

(. fuLOTb.2 rs

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g. Major weld repairs

h. Control of weld materials and weld rod oven calibration procedures

i. Subcontractor qualification and surveillance tw #A MAuv4t.

j. Nonconformance and deviation control su d?A feuod i

k. Bending and/or fonning {

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p/<rTn. f C ;: :: n:1 :::1"i:: tion: '

93t Page 15 of 22 l t

LO NOTE: Contractor may add to this list, but he may not delete any item without having the written approval of the consulting engineer's Quality Control Division and/or purchaser.

Contractor shall revise all or any portion of his Quality Control Procedures as required by the consulting engineer's Quality Control Division, and/or the Station Construction Site Project Superintendent, and shall re-submit the procedures as many times as required to receive written acceptance from the consulting engineer's Quality Control Division or Station Construction and Quality Assurance.

2.2 Inspection Point Program:

A. An inspection point program shall be established by the contractor and shall include pertinent manuf acturing and inspection operations which will be of concern to the purchaser relative to Quality Control. Contractor's recommended customer inspection point program, which will be applied to the eauipment, shall be submitted ~

in writing for review and acceptance within six weeks after award of contract. Inspection point progr: , for off-site work shall be sutimittee to consulting engineer's Quality Control Division, f f

i Inspection point programs for on-site work shall be submitted to the Station Construction Site Project Superintendent.

NOTE: ~1. The contractor shall not start any work which requires an inspection point program until the purchaser or the purchaser's consulting engineer has reviewed and accepted the program as appropriate.

Page 16 of 22

F.

f. . The agreed-upon list of inspection points do; not constitute

" hold points" unless specific points-are designated by the, purchaser.

B. Purchaser and/or his designated representative shall have full

-access to contractor's and subcontractor's shops for reviewing progress and determining acceptability of Quality Control activities. Station Construction Site Project Superintendent or his designee shall be notified.at least'two (2) working days excluding Saturdays and Sundays, prior to starting of th'e specified

. tests and inspection points, agreed upon durng the review of the inspection point program.

C. Purchaser and/or his designated representative shall have full access to contractor's and subcontractor's shops for' reviewing and auditing the implementation of its,cuality assurance program. Any findings resulting from a contractor's/ subcontractor's audit shall be addressed and promptly corrected to the purchaser satisf action.

The audited organization shall provide a scheduled date for completion of corrective action.

2.3 Subcontractor Requirements:

Contractor shall be responsible for the review, comment and

~

A.

acceptance of the Quality Assurance Program and Quality Control Procedures of the subcontractor. In addition, contractor shall be responsible for his subcontractor's work.

2.4 Seismic Report:

~

A. Seismic reports, where reauired, shall be submitted to the consulting engineers for review and acceptance.

Page 17 of 22

2.5 Nonconfomance Report: ,

1 O

V .

A. Any nonconformance with purchase documents, approved drawings, !

procedures, or approved material selection shall be promptly 3 1

submitted in writing for resolution. Off-site contractors shall j i

submit nonconformance reports to the Station Nuclear Engineering Department Manager. On-site contractors shall submit nonconformance reports to the Station Construction Department Site Project Superintendent. Contractor may proceed at his own risk ;

prior to acceptance of a nonconformance.

2.6 Design / Stress Report:

A. Where recuired by the design specification, manufacturer will prepare a design / stress report in accordance with The American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III, Division 1 Referen:e Paragraph NCA-3552.

O b Manufacturer will submit its certified design / stress report to the Consulting Engineers for review and acceptance.

2.7 Quality Control Records:

A. Two copies per station of all appropriate documentation as herein speciffed or as recuired by applicable Code, Standard, and Criteria, shall be submitted to the Consulting Engineer's Quality Control Division in separate packages, clearly identified for the applicable station. Also, packages shall be segregated for the applicable unit within the station. Documentation shall be submitted for review for acceptability prior to or concurrent with the shipment. This documentation shall include but not limited to i the following: ""

(T": :p :i'icati n write- i t: in: Ort 5 r:

of the recuired documentat g, for each item, the

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Page 18 of 22 j

C'\

V a. Certified Material Test Report, which shall include the actual results of all chemical analyses and mechanical tests required i

by the material specification.

1

b. Welding Material Test Report

c. Welder qualification papers

d. ";di:;r:;'i: r:;:-t: : d " '-

2w

e. Repair Weld Reports (Ol:gf

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/ e t 15 2.8 . Certificate of Compliance /Confomance:

A. Certificate of Compliance A Certificate of Compliance signed by a cualified party, attesting that the items or services are in accordance with this specification and accompanied by all documentation required by J

these articles to substantiate that statement, is required upon completion of this contract.

Page 19 of 22

B. Certificate of Conformance 1 It is recognized that in special cases, the specified documentation -

I 1 may not be available at the time the eauipment is ready for shipment. In these cases, shipment to the site will be allowed under the following conditions:

1.

With written approval of the purchaser, a Certificate of

' Confomance shall be transmitted with the shipment. Approval shall be obtained two weeks prior to shipment.

2.

The certification should be sufficient to specifically identify the purchased material or ecuipment, such as by the purchase order number, specification number, station name, unit number, i and eouipment tag numbers.

3.

A certification should identify the specific procurement requirements, met by the purchased material or ecuipment, such as Codes, Standards, and other Specifications. This may be accomplished by including a list of specific requirements or by providing, on-site, a copy of the purchase order and the procurement specifications, or drawings, together with suitable conformance statements. The procurement requirements identified should include any approved changes, waivers, or deviations, applicable to the subject material or ecuipment.

Equipment tags and numbers shall be included on all documents available at time of shipment.

4.

The certification should identify any procurement requirements that have not been met, together with an explanation and means for resolving the nonconformance.

Page 20 of 22

O 5. The certification system shall be described and the position responsible for attesting on the certification documents shall be oescribed in the cuality assurance program.

2.9 Radiographic Film:

A. All radiographic film shall be submitted within ten working days af ter completion of radiographs and evaluation by the contractor.

Radiographic films taken during off-site f abrication shall be submitted to the consulting engineers for review and coment.

Radiographic films taken during the course of on-site work shall be submitted to tne Station Construction Site Project Superintendent f or review and comment. Tne submittal shall include the following:

l. Two film negatives (double film techniaue) of each radiographic location including those of repaired areas made both before and l

v af ter repair work are reovired. (Paper separators shall be provided bet.een each radiograph).

2. The contractor's radiographic inspection report covering his interpretation for each film (reader sheet). Proper identification of the radiographs is most important.

3. The contractor's radiographic techniace report covering the essential variables.

4. The contractor's shooting sketch showing the identification and location of film and placement of radiation source.

5. After submittal of radiographic film and the required reports and prior to completion of such review, the contractor may l proceeo with any work at his own risk.

Page 21 of 22

l 1

- (3 2.10 Documentation Submittal:

O i A. Tne contractor shall submit, af ter drawing approval, a detailed listing of the reautred auality control documentation to be provided prior to or concurrent with the shipment for receipt inspection at the site and for review and acceptance by the Consulting Engineer.

, B. All documentation (including radiographs) shall be clear, legible and of suitable quality for microfilming, and/or storage for the "

life of the plant.

2.11 Invoice Submittal:

A. Invoices for ecuipment received on-site will not be honored until all documentation has been received, and complies with procurement documents.

2.12 Spare Parts:

A. All requirements regarding Quality Control and documentation that applied to the original parts of the specified ecuipment shall apply ecually to the spare parts of the specified equipment.

Contractor shall identify those requirements in detail on spare parts quote.

2.13 When a defective or non-complying item (10CFR Part 21) 15 identified by a vendor, it shall be imediately documented and reported by the vendor to the Station Nuclear Engineering Department Manager.

Page 22 of 22 0030Q*

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' en8aECr we. 4 se-to 243YNC onnetwo z. coo rnoE s-uf er s FREQUENCY lu trS 800 4 200.8 100.0 50.0 20.8 10 0 S.9 E.8 10 05 gg . . . inis s a i n i e a i i n i e a i nii nini ei e i i. . . niaisiin ii . . .

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1 1'

d I

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(- j 4266-10 8-18-0-6 LRS LSAD C8nBINRT. .

SRRGENT & LUNDY seeCTan er teRD CenciNatiSN .

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l

F 4

1

-r -

LSCS-MARK II DAR Rev. 9 0/81 o )

4.4.3 NSSS and BOP Equipment The following bounding load cases were used for the re-evaluation:

1 Load Combination Acceptance Criteria

1. Upset N + OBE + SRV*ALL-TQ 2.'

N + SSE + C9-2 + SRV* ADS-TQ mergency

3. N + Chugging + SRV* ADS-TQ + SE Emergency

4. .N + SSE + AP ,

Emergency '

5. N + SSE + C@-1 Emergency ,

I O *

- V *SR AMQ and SRV ADS are ec,ual.and are de envelope _ to l SRV and SRVASY-TQ, ALL-TQ ,

The seismic loads were combined with the pool dynamic loads by the SRSS method except for Co, where the absolute sum l method was used.

The acceptance criteria used for NSSS and BOP equipment l are given in Table 4.4-2 for both active and nonactive equipment and for fluid and nonfluid systems.

SQRT forms have.boea comoleted for all pio:ns of aquipment located in the reactor building. !

I. Nonactive fluid system equipment has been checked for the same loading combinations and the corresponding ASME Section III design limits.

4.4-2

O -3 (OOOOOOOdlif0RRDOOO . _

0000 000 h 0000000 000, 000 0000 i OOO -

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l CHANNEL putLR00 PELLET WATEmmoo CIM I.D. A e C 0 t p o H I DIM INCHES .4103 S.778 0 380 0 032 0 443 0.419 0 410 0391 0131 CONTROL 200* svNoLE LATTICE CtLL' OtMiD. J - L M N O P O Im 5 otMaNCHt$ 1 54 4 J 75 0260 0 640 0.157 0.154 0.103 4 261 0.261 12 00 C-Lattice 100-=11 Channel BWR 14/5 FIGURE 1

CONTROL R00 I

1 1 1 1 1 1 1 I 1 1 1 1 1 1 1 1 DESCRIPTION OF FUEL MATERI AL COMPOSITION 1 1 1 1 0 1 1 1 y

MATERIAL DE$1GNATION ENRICH ENT t t t t a;;;* 1 1 1 gg

. I 1 1 "[jja 1 1 1 1 A 0711 WATER 0 1 1 1 1 1 1 1 1 1' 1 1 1 1 1 1 1 1 1 1 1 't 1 1 1 ROD TYPE DISTRIBUTION RCD T**ES 1 2 h

\ l W

A A j $g ,,

R l

)

l i

i l

)

, If NUMBER OF E ACM ROD TYPE 62 2 BWR 4/5/6 0.711 SUNDLE Dir:ribution of Rod Types orni TheV Metreial Composition

.O ~

FIGURE 2

e C0ktm0LA00 .

(

4 3 2 2 2 2 3 4

'2 2 1 1 1 1 2 3 2 1 1 1 1 7 1 2 OEllGN ATION ",

2 1 1 8 WATER 1 1 2 A 2.20 RCD 8 1.70 6 C 1.50 2 1 1 WATim S 1 1 2 0 1.20 ROD N 0.711 2 1 7 1 1 1 2 2 , ,y G 1.70 2 2 1 1 1 2 2 3 4- 3 2 2 2 2 3 4 MOD TYPE Di$TRIBUTION TOP Op POOTYPEs SUNDLE 1 2 3 4 5 6 7 s TS 6' 6 8 y 6 in.

g in.

g 8

.n. en.

T6 en.

g in.

g en.

12 A

in.

I y 72 g 84 g 84 en. in. in .

W

'M '38 '"

A an.

e en, C

en.

D en E

l 38 36 4 36 A E in, in. en.

I 12 F

',"-4 18 o 38 in, in.

Nuussa a 6 6 e 6 6 g 6 y g g y g 0F EACH 'n. in. 'n- in. 'n. 'a . in .

R00 TYPE 24 22 8 4 2 1 2 1 i

BWR 4/51.76 BUNDLE narrih.orinn of Rod Tv.nes and Their Materia! Composition 5, I l

l FIGURE 3 l

g CONTROL A00

-i ,

q . .

CESCmiPTION OF FUEL MATEml AL Composition e 5 4 3 3 4 s 8 g

M ATERI AL ENRICMMENT 8 4 2 1 1 1 3 3 DESIGNATION W/O U236 4 2 1 1 1 9 1 4 A 3.00

- . 2 1 1 10 3 C 2.20 3 1 1 1 1 D 3.00 E 1.70 3 1 1 to B 1 2 3 F 1.30 0 0.71' 4

4 1 9 1 1 2 2 3 J 1 70 4 5 K (WATER MOO) 5 3 1 1 2 2 6 5 4 3 3 4 6 6

-- ROO TYPES TOP OF ROD TYPE DISTRIBUTION 7 8 9 10 i SUNCLE 1 2 3 4 5 6 G 6 G 6 G 6 G 6 G 6 T6 C 0

'a .

Y6 in G 6 in. in in in , in in. in J 12 a in.

l P

( -

(

72 A 84 H 120 K 150 A 1 38 8 138 C 138 0 138 E 138 F 138 1

.n en in in in. in. .n en in. in H 36 H 34 in. en.

~ ~

12

I in. A gg i J

6 in J

6 in f \

in.

~~

6 j NUW6ER {

6 se.

7 6 g 6 in.

g 6

'a-g 6

'a T 6

'a g 6

'a.

g 6 in g

'a j OF E ACM in.

to 10 6 4 1 1 2 2 RCD TYPE 19 7 BWR 4/5 2.19 BUNDLE Diste;bution of Rod Types and Their Material Composition

\'O 1

. FIGURE 4

i G t ti t r.t t CLt u -

GA00LitilA ROD DATA 1

ROD AVERAGE AXIAL ROD TYPE GADOLINIA CONCENTRATION l

- 1.76 w/o U-235 Bundle 6 2.24 w/o 7 1.20 w/o 8 1.36 w/o ,

2.19 w/o U-2. Pundle J'8 1.20 w/o

'# 9 4.24 w/o

1 3.68 w/o O

TABLE 1

1 l

l

. i 7G4 Assezblles -d

{

, l

'[

3 3 3 !

3 3 3 3 1 Is-;)-. '

=

._, i ._ ,.

3 2 2 2 2 2 2 2 ,2 >

3 3 I2 2 2 2 2 '2 l 2 2 l3 g

3 2 2 2 2 2 2 2 2 2 \ 4~

3 2 2 2 2 ! 2 2 2 1 2 1- '5

-.__ i____.-, ,

E 3 3 2 2 2 2 ,

1 -2 1 2 1 1 6 3 2 2 2 2 2 2 7 1 1 2 -1 2 1

-._.. t 3 2 2 2 l 2 2 1 2 1 2 8

1 2 1 1 3 2 2l' 2 l2 1 2 {1 d2 1 l'I2 2 1 lf 9 s

1 :

L_..I'f2 -

t t __ _J t

1

.==q

8 -

3 2 2 2 2 ,i1 2 l Il 2 b1,_ 2 I 1 2k.1 1 1(

r3 t- 1I L_ ._ 1,I I V ~-

r 3 2 2 'l2

, 2 ):: .

2

{

i, 1 ll 2 1

t 2 [1 l l.___.li,2 1 2 1 I l. '

-(

1 3 2 2 l 2 2 1 2

[1 2 , 1 2

]1 2 1 1 iU j

l2 , ,

3 l 2 2 l 2 1 2 1 1 d2 1 2 1 2 1 c' 1 '-

3 2- 2 >

2 2 2 4 : I'

[1 1 2 1 2 1 2 1 1 3 2 2 2 1 1 ! 1 1 1 1 ! 1 1 I!

1 1 1

I--> 1 2 3 4 5 6 7 8 9 10 11 12 13 14 , 15

, initial Core Loading Man

1. Medium Enrichment - 240 Dundles

2. High Enrichment - 432 Dundles

3. Natural Uranium - 92 Dundles O FIGURE 5 1 O I l ,.

1

i:

8 x 81.ATTICE-l 0

ENRICHMfWY Cl5TA180710# MAP FOR 2.33 AVFRAGE ENRICNNfMT l

1 V

4 -

-- l

.. _..-. . I I 4 3 2 2 2 2 3 4 l

3 2 5 1 1 1 2 3 g 2- 5 1 1 1 1 1 2

- r. '

2 1 1 1 water 6 1 1 2

_iuke..

V6ter

]" 2 1 1 6 1 1 1 2

_ tube l 2 1 1 -1 1 1 5 2

.. l 3 2 1 1 1 5 2 3

- ' 4. 3 2, 2 2 2 3 4 FUEL TYPE-1 R00 K!NBER OF A005 2.33-4Gdl,0F) pin locations (6.3)(3,6)(4,4)(5,5) TYPE WTK f71 1 FT)! f 7

. FUEL TYPE-3 (6,3)(3,6)(4,4) 1 3.00 22 23

2. 33- Md[2 (.05) l f .04)J 23 FUEL TYPE-4 2.33-Md(.ot? pin locations (6.3)(3,6)(4,4) 2 2.10 20 20 20 3 1.80 8' 8 8 4 '.40 4 4

) 5 1

2.70 4 4 4

4 Gd* 1.40' 4 3 3

'O, Wherever a gadolinia md occurs in the enrichwnt distribution . map above the UO2 enrienunt is not that of rod type-1 Dut 1.4 wt2.

.y FIGURE 6

s. . v. , , . , .

l l

! CALC NO. 8AFETY RELATED SRRGENT 4 LUNDY PReacCT- LasaLLE UNIT REv 0 t#0tuttag - PROJECT M8 7043-73 12 FEB 86 OAMP!NG 0.020 PAGE SLC1NT I.

FREQUENCY IN CP3 000 0 .200 0 100 0 50.0 20 0 10 0 . 50 2.0 t.0 0.5 )

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(- SPECTRA N6 LC-1-NS

.) Ne0E ELEvaTieN 807 g 1 DIRECTION HSR ANDLE L9 CAT!8N REACT 6R BUILDING SLR8 l

l CALC N8. SAFETY RELATED l, . SARGENT 4 LUNDY PR6 JECT LA8ALLE UNIT REY 0 ;

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, 12 FEB 86 ogR SLC1NT l l

l

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I

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CALC NO. 3RFETY RELATED c SARGENT & LUNDY PReJECT LASALLE REV O ENQlNCER6 . PR8 JECT N8. 7043-73 13 FEB 86 $"o"g!$Ua, U ' '

SLEVEc PREPAEtH: M$,l%Mli i . 1 i REVIEWER: 7' Uh 2/GW w

FREPUENCY !N :.C 500 0 200.0 100 0 60 0 20.0 10 0 6.0 20 10 06 iiie iniinini ei i i ie i i uisiv e n e iiie i e i e nisiniai , , , i 20.g .sisi un i i ris ni siis sin riis ini- a i isa in siis ins siis sin i i sii us isiv iu5 20.'

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l ll l

CALC NB. SAFETY RELATED SARGENT 4 LUNDY PReJECT LRSALLE REv 0 :

('l tw0incue PR8 JECT NO. 7043-73 )

\_J 13 FEB 86 DRMP!NO 0.040 !

l PAGE { @

8 SLEVEC I PREPARER: 4 dx c/4 REVIEWER:ld %/d/A "

FREQUENCY IN CPA 600.0 200.0 100.0 50 0 20 0 10.0 6.0 20 10 06 20.0 -s' i ' ' ' ' " ' ' ' ' " ' ' ' ' ' ' ' ' '

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g 1 00. _t.00 g 0.80_

/ \ _3.80

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=

-8 0.8C 3 60 w

8060

~ ~ -

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.3.30 I

0 20_~ _3 20

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CALC N8. SAFETY RELATE 0 (q

)

SARGENT & LUNDY EN0!NEER8 .

PR8 JECT PRBJECT N8. 7043-73 LASALLE REV 0 i

! 13 FEB 86 UAMP!ND

( PAGEtj G l' O R F'M L REVEC PREPA mt M Nr$$

k REVIEWERk 06 zw >

v (

F(.ECUENCY IN CPS __

600 0 ' 200.0 1000I 30 0 .' 10.0 10.0 6.0 20 1.0 06 i sini t ii n i i ei e sii ie N Tr r;b'ininee 20.C ,i ,i, ,i sin i i ie e i ei ii interie i , , i i:: sei siiv viii sii su siis issi inii ini i i sai sii siis ii,u 20.0 16.C~ --

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MTE~ T 0C~ '71 1 l

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CHECKED BY 63 MTE '2" 72 SHEETC EOF I s a w. w o. l I sus - ic 7.$ i i

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' ' ' ' ' ' ' ' ' ' ' ' ' T 0 002 ' '0' '.004 0 006 0.010 0 020 0 040 0 060 0 100 0 203 0 400 0.000 10 2.0 O .C5 PERIOD IN SECBNDS HBRIZ RESPONSE SPECTER SPECTRR !!S. SA-119-HS ELEVRTION 843'-6" L6CRTIBN Reactor Building Slab REVISleN Ne, 0

Un bt '24-L':

REVISI0t; O C FCR LCSP.Lt.E-H353

,. SRRGENT 4 LUNDY rWU SRV-nSYtaMti DEStCnER F. uutnEcsh.ca T D 0:01ECn3 DESIDil SPECTT.R AT 01i:T/SL6D (s}

PEnns Nt0:::ED DY 20% t.N EACH SICI

!.2 c. VERT

'~'

03 JUN 79 DRitPltlG 0.C05 0.010 0.020 0.050 0.100 7

)

( 7118FH SHEET 38 or n2 PROJECT NOS. 4266/4267 CALC. NO. 165E FREQUElCY IN CPS 500 0 100.0 100.0 C0 0 20.0 10 0 5.0 2.0 10 0.5 t iI I I t ' t gg,g '44III I I t t i t t t t I f Ittit9i t ' f 1 t

0 4 19110 t t I t fli t f t i I t

= 56II I I ili 644 4IIi 6HI Ii44 ilii I 4 465 463 5438 3Ill 3454 3433 1 4 &ei e46 il I i ' a 3 3 44

15 0[ [13.0 10 0. -

.10.0

~

) .0 0 8 00[ ,

6 00 , q 3.C3 5 00 5.00 4.00. . b00 3 00

]-

h.00 sa > -

(m) 521.FD2.0.l --

(

l1.L3

- -\.L3 d

2 1 00 m .;t.C0 0

$ .tc ~ ]JWJ U 0.00:\. - :' .2 u 1 0 0.CC - /..C3 w 4 0.40,. % 40

~ ~

0.50 J.!D b c

- /- _g, 0 20 , 0.10 7 15 0 10~ l l 2 [ 4 I

r X4 hl v x4 : I E /// \\ V/e s \'% itJ '.cb

)

0 02 0 06 r' ' ' ' ' '

Nm V/,

\\1 a.08 1 l C 05

.C3 0.00t 0 004 0.00s 0.030 0.020 0.040 0.c:;a 0 100 0.t00 0.4c0 0.cco 1.0 20 l PER!eD IN SECONDS i l (

O VERT RESPONSE SPECTRR SPECTRR ID. SA-119-vS ELEVRT!eN 843'-6" LBCRT!6N Reactor Building Slab REVISleN N8. 0

.______-_-_O

it.- x -u4-:.3 RE'.'ISJON 0 KNU SRV-R$YttPTRIC FOR Lr: . -:J3 S 2 .

SARGENT 4 LUNDY DES 10nEag.ggy Cn:Csr ._;j W '

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PROJECT !;OS. 4 26 6/4 2 G"1 '

CALC. NO. 165E ,

FREQUEUCY IN CPS

, 500.0 200.0 100.0 50.0 20 0 10 0 5.0 20 10 0.5 '

)

20.0 dT

=

t! lu n e '$ '!!! 's ls In's!lus l ls ! s'u s n 'l' '!ll 's ln lls ! lu s lls ? ls u s 'l ' '!!! 's ls l ls ! s'u 20 0

=

15.0~ *

15.0 10 0_ 10 .0 8,00 b

'J.00 6.00 ,3 03 5.00 1

b.03 4.00_ t.03 b

3 00 3 00 Vs .

C 2 00,. '

,t.C0 E

50*

i a r "..E0 i

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g100 ---

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15 : 3 .t,0 g 0 00 ,

, ,0,00 8 0.00 -s O

a: -

0.40. d.LC

.C.40 5 f 0.30 f.n 0.20_ -

3 20 0.15, c .15 0 10.

0 10 3

0.06_ ~0.05

~

0 06 i 3.06

'O.05 ' ' ' "' ' ' ' ' ' '"' ' ' ' ' '"

.05 0 002 ".904 0 0 006' 0'.010 0 0Z0 0 040 0.050 0 100 0 200 '"'.400 0 0 600.0 1 2.0 PERIBD IN SECONDS l

H8RIZ RESPONSE SPECTRR SPECTRR NB. SA-120-HW

\ ELEVRTION 843'-6" LBCRT18N Reactor Building Wall REVISIBN NB. 0 I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J

.__, REVISI0ft 0 K6'U SRV-OSYrinCTRI j SARGENT 4 LUNDY OcSiCnEn ,q /j ,(CCnECaER FOR LDSRLLE-H302gg y .~ ac

>Et!DINEERS . DESIGN S/ECTfn RT J3!t!T/0LC3 0';2 VERT j

/^'t

(/

03 JUN 79 PERKS U13:GID DY C0% CN CECH E!DC DRtiPlt!G 0.00S 0.010 0.020 0.050 0 100 l

l

, 711BFH sarcT 40 or 112 )

PROJECT NOS. 4266/4267 l CALC. NO. 165E FRECUENCY IN CPS C00.0 200.0 100 0 C0.0 20 0 10 0 5.0 20 10 0.5

' ' ' ' ' l 20.0_l s', l i' u i 'I'((['ili 'I ' '(([ 'a Is Iii[

I /TY"/NT l i i[ s'u, iia l s's [ 4so i '(([ ' li i !

l i i /l E.~ty'"O O 4

E 3 15.0 ,

j15.0

~

10.0 ,. .10.0 8 00,, , _1.C0 e.0c a.00

, q 6.00 3.70

~

4.00_ d.00

_6 3 00~ =,'3 0 0 es _

b 2 00 ,

2.

5 ;; ] C0 j t.50[ ;'1. C O l !%.x )( : :

=

z 1.00 10.1 8 5 I

b g 0.$0, ~~

-_MB

d 5

d '*Sc _ ,

1 ?#'

8000-a: i--l9.

l

- ;J 0 40,. ---- 0 4 0 0.30 ,

,%00

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b4 W. N, :

0 10

[f/

// N^ fr/ / T\ :

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i

.N V Vi 5

".05 0.0s ' ' ' ' '# "" ' ' '" ' ' ' ' ' ' ' ' '" .:s i 0.002 " ".004 0 0.008 0".' ' 010 0.020 0.040 0.050 0 100 0.t00 ' ".400 0 0.500'\ ' ". 0 ' '

1 2.0

! PERIBD IN SEttNDS I

j f~h VERT RCSP8NSE SPECTRR SPECTER NB. S A- 12 0-W i ELEVRTICN 843'-6" 1 LeCRTISH Reactor Building Wall REVIS10!! N8. ,

i l ._____-____-____--__-______a

REVISION O SRRGENT 4 LUNDY nNuSRv-S!w0tpreRLRsRttE-wS20 DES!GnER 8. A CHECnER,9 5 9 W EWetNEERS . DESION SPECTRR RT J81NT/SLRB 328 RRDIRL

/~% #.

09 JUN 79 PERKS N!DENED BY 20% BN ERCH SIDE DAMP!NG 0.003 0.010 0.020 0.050 0.100 l

L/ 145BFH :SureT 25 or 112

( PROJECT NOS. 4266/4267 CALC. No. 165F _. _ . _ _ _ . .

FREQUENCY IN CPS 500.0 200.0 100.0 so.O 00 30.0 50 30 10 05

, , * - , sai ,,ui,,, i, , , ,, , , ,u,,,,,, ,, ,, ,, ,, , , , , , , , , , ,, , ,

un i i sai us sisi un iisi isu i e iis in si,i un assi usi e i sia sei siis s i n. 20 0

~

15.C[ ,

15 0

~ .

10.C _ ,t0.0 8% _

[3.00 1

0 00 - 3 00 5 00 :.00 4.00_~ ,'4.00

~

3.00[ 3 00 es 2 :

D 2.00 _

_2 00 E 3 INSIGNIFICANT

~

e 1 50., ,t.50

(' _/' ,1 00,. _1 00 H,,0 80 _ ,3 80 a - -

sa -

g 3 80 ,

3 60 8050- 3 50 sc -

0 40_ _3.40

~. :

0 30[ [3.30 0.20. .3.20

~

0 15[ 3 .15 0 10. -

_3 10

~ ~

0.00 _ ,3 08 0 08 30S

~

0.0sI' '

" ".004 0 006 0 010 0.040 0 000 "0'.10

"'"3.05 0 001 0 0 020 0 0 200 0 400 0 600 10 f.0 PERIBO IN SECBNDS i

( liBRIZ.'. [ RESP 8NSE SPECTRR SPECTRR No. SO-113-HS s

ELEVRT!eN 807'-0" L8CRT!BN Reactor Building Slab REVIS!BN NB.O l

1

KWU SRV-SINGLE F LR3RLLE_N339 REVISION O SARGENT 4 LUNDY DEStGNER F. & CHECKER,ShM ENotNEER3 . DESIGN SPECTRR RT JOINT /SLRB 339 RRDIRL PERKS WIDENED BY 20% DN ERCH S!OE (ob 09 JUN 79 ORtlPING 0.00S 0.010 0.020 0.0$0 0 100 ;

i U 1458FH SHEET 29 OF 112' '

PROJECT NOS. 4266/4267 l CALC. NO. 165F l i

FREQUENCY IN CPS j 500 0 200 0 100.0 50 0 20 0 10.0 5.0 20 10 05 '

20.C_,i ,i, ,f ,f,,, , f ,f f f ,I,f ,f I, ,t , ,i ,f, ,I ,f,,, ,f ,f, ,f ,i,,, , I ,t t i,f ,f ,f f, ,I, ,f ,f, ,I ,f,,, ,f ,f, ,f ,f,,, , f ,f f f,f ,f ,f f, ,f , ,f , I, ,f , f, 320.0 15.C[ [15 0 l

1 i

10.0_ _10.0 j 1

8 00] [3 00

, : : i l S.00 ~

0 00 l l

5 00 5 00 .i l 4 00_ _4 00 i

~ ~

3 00 3 00 to _ _

!~. 2 00,-= _ 2.00 5 5 INSIGNIFICANT

~

m 1 50 _ ,,

1.50

/7 : _"

! ) - _

' Wmt . 00 : 1 00

~

h0.80 3 .80 0 2 -

3 g 0 80, 3.60 8 0.50 3 50 a - .

0.40,_ _3.40

~

0 30~ ,3.30 0.20_ _3 00

\

~

l 0 15 [

3.15 j 0 10 _ _3 10 0 00[ ~3 08 0.06 3 06 0 06 ' ' ' '

' ' 'I .3 0 5 0.002 0 004 0.006 0 010 0 020 0 040 0 060 0.100 0.E00 0 400 0.600 10 E.0 PERIOD IN SECONOS I ~

/

f4 \

H8RIZ. RESPONSE SPECTRA SPECTYR HB. 50-115-HS

(,/ ELEVRTION --

LBCRTION Fuel Pool Slabs REV! sten NB. 0

[

N5Vi51656~

KWU CRV-SING '

SARGENT 4 LUNDY A DES!ONER 3.LE F."I LH3ALLE-N359CsECxER ,5

= ENo!NEERS DES!ON SPECTRR RT J3!NT/SLRS 3S9 RR0!AL

. - / \ ',. 09 JUN 79 PERMS NIDENED BY 20% ON ERCH SIDE ORf1P!NG 0.005 0.010 0.020 0.050 0 100 VI 14SBFH SHEET 37 oF 112 FROJECT NOS. 4266/4267 CALC. No. 165F FJtEQUENCY IN CPS 300 0 200 0 100.0 50.0 20 0 10.0 5.0 20 10 f f 05 30 . ..I i .i i

,,,, f,f f f nii f f f f fi i i , , f, ,f ,f,,, ,f , f , ,f f f ,f f f ,f ,f ,f f, i , .f . f. f ,f,,, ,f , f , ,t t g

,t t i,g,,

( i t, ,, ,

, ii., , ,,,, , ,i , t , ,g ,9, , uto.O s.0- ,

i5.0 l 10.-- ~ _

10.0 i

~

1 e.0:_ . s ;

h.00

. 00 -

g..

5.DC 5 00 4.00_ 4.00-3.00, 3.03 n

O,t.00-

.=

~

[0.00 m 15C_

INSIGNIFICANT :

t.50 D : :

G "A t

? .00b b.00 g 0.80_ 0.c0 m -

4 w -

g 0.60_ 4 0.60

~

8 0.50 0.50 K -

0.40_

(0.40 I

0.30, h i

,0.30 j 0.20_ ~ _

0.00 0 16~ -

~

0 15 l .-

O.10_ 0 10 0.0s" -

~

. -0.08

~

8.08 .06

0. 0 5 ' ' ' ' '' ' ' ' ' '"' ' ' ' '"' ' ' ' ' '

.05 0 002 0.004 0.006 0.010 0.020 0.040 0.060 ' .100 0 0.t00 0.400 0.600 10 2.0 PERIGO IN SECONDS

~

N6RII. RESPONSE SPECTRR SPECTER NO. SO-119-HS s_ EttVRT!eN 843'-6" LBCRT!eg Reactor Building Slab REVIS!eN No. 0

I REVISION O KWU SRV-S!NGLE FBR LASRLLE-N SRRGENT 4 LUNDY DESIGNER 8.Afu CHECnE p r'y @

EN0!NEERs . DESIGN SPECTRA RT/ JOINT /$LRB 331 RADIRL PERKS W10ENED BY 207. BN ERCH SLDE

/

,-~s 09 JUN 79 ORtlPING, 0.003 0.010 0.020 0.030 0 100 0' (" 145BFH satrT 27 Or 112 I PROJECT NOS. 4266/4267 CALC. NO. 165F FREQUENCY IN CPS 500 0 200 0 100.0 50 0 20 0 10.0 5.0 20 10 05 20.C ' i t s' s'u i i ' i 's'e'i' 'n' i ises ##u a' i i s' s'i n i i 's' a'i i n' i i i s' s'i n i a'i s' a'u s i i 's' i nu' i iisi s 'u20 0 15.C [ [15.0 10.C_- _ 10 0 8 00[ [3.00 8.00 - -

3.00 5 00 '.00 4 00 ,, _4 00

~

3 00 ~3 00 n . .

!; 2 00 . .2 00 5 3 INSIGNIFICANT E 1 50_ ,

1.50 p* :

\.

g 1 00,, .1 00 5050

~

~3.80 g : :

m - .

a 0.60 3.60 u - .

8050 .- _

3 50 0 40,. _3.40

~

0.30 [3.30 0.20_~ _3 20

~

0 15[ [3 15 0 10_ 3 10

' ~

0 00 ,. _3.08 0 03 3 05 00 ' ' ' '

l 0 001 ' ' 0".004 0 006'0".010 0.020 0 040 0.060 ' 0' .10 0 0.200 ''.400 0 0 600' 10 ' ' 20

' .3 . 0 5 PERIBO IN SECONDS

(

,- H8RIZ RESPONSE SPECTR3 SPECTRR NB. S0-ll4-HW (q ,/ ELEVRT!BN 807'-0" LBCRTION Reactor Building Wall REVIS!BN NB. 0

OC-SE-05-LS REVISION O KWU SRV-31NG FOR LRSALLE-N342 SARGENT 4 LUNDY DESiONEas.dLJy CsECnER A M w i EN0!NEERs .

DESIGN SPECTRR RT J31NT/SLRB 342 RADIAL g") ('

09 JUN 79 PERMS WIDENED BY 207. ON ERCH SICE ORMPING 0.00S 0.010 0.020 0.0S0 0.100

, 1438FH SHerT n Or n2

. PROJECT NOS. 4266/4267 CALC. NO. 165F . . . .

FREQUENCY IN CPS 500.0 200.0 100.0 50 0 20.0 10.0 5.0 2.0 1.0 0.5 20 0 -' s' ' '

u's' i s i' 'a 'i u sisi ius i "i ' 's'i a' 's u'i' n 'i i' "e' 'i i s' 'a s 'u2'00 i s i un i s 'u si i s s' a 's u i ' "e ' 'i i s' 'u's s' i i s' c

~

15 0 - ~

15.0

~ .

~

10 0. - ; 10 0

~ .

8 00 ~

3 .00

~

8 00

0.00 5.00 ' -~~ ~ ~

5 00 4 00_ 4 00

~

l 3 00_ -

3 00

~

es U t.00_ _ -

~

_2 00 5 3 INSIGNIFICANT ~

, 1.50 _ 1 50 I I

.~

v - !

_ i g1.00 .

_1 00 g 0.00_ .

~

0 .60 ;

e - '

W -

.8060 w 0 8050_ q.60 .

g .

0 0 40_

q.50

_0 40 {

l 0.30- . 0 30

{

. 1

. j 0.20. -

_0 20 0 15 . .

3 15

~

\

0 10.~ _ 3 10 l 1

0.0e_ ,

0 08 l

~

0.00- -0 06 0.05 ' ' ' ' ' ' ' ' '' ' '

'I.05 O 0.002 0.004 0.006 0.010 0.020 0.040 0.060 0.100 0.200 0.400 0.6c0 1.0 2.0 PERIOD IN SECONCS I

~

O, / HBRIZ. . RESPONSE Sf'ECTRR SPECTER N8. S0-ll6-HW V

ELEVRTION --

LSCRTttN Fuel Pools / Reactor Bldg. Wall REVISISN N3 0

DC-SE-05-LS REVISION O RWU SRV-SING OR LASALLC-N362 SARGENT 4 LUNDY Oc3Dueng[L cacent,,g fg ENDINEtas . OESION SPECTRR 362 RTRR0!RLJOINT /SL ,

PERKS WIDENED BY 207. 8N ERCH S!OE

'd r~'

09 JUN 79 ORMP!ND 0.005 0.010 0.020 n.nmq 0.100

)

( 146BFH SHEET 39 OF 112 PROJECT NOS. 4266/4267 CALC. NO. 165F ,

FREQUENCY IN Cr'S 500.0 200.0 100.0 50.0 20.0 . 10.0 5.0 2.0 10 0.5 t I t t titttiftt i f f f I f f f li t t i t t t I t t t t t t t t fitftttt I t t t j 20.0 sisi sin i i sie in inii siis inii iiii e i sei in siis sin assi sisi e i sii sie iisi siit to.C

~

i :

15 0 [

~15.0

- - 1 10 0 ,,, _10.0 3 00 , , ,0.00 6.00 0.00 5 00 5.00 4.00. ~

,4.00 3.00~ -

~3.00 n

i :

a - .

U f.00,. 2.00 5 : INSIGNIFICANT k

( l.50~ 1.50 g 1 00,. _1 00 g 0.80_ _0.00 5J : :

0.60 0.60 kJ .

8 0.50 0.50 0.40. 0 40

~ ~

0.30- -

.0.30 0 20,. _0.:'O 0 15~ [0 15 0 10_ -

_0 10

~ ~

0.05 ,

,0.03 0.05 _0.06 0'.05 1.C5 0.002. 0.004 0.006 0.030 0.020 C.040 0.060 C.100 0.200 0.400 0.600 10 2.0 PERIGO IN SECONOS

~~

HeR11 RESP 8NSE SPECTRR SPECTRR Ne. S0-120-HW i 1

ELEVRT!eN 8 4 3 ' - 6 *'

LeCRTieN Reactor Building Wall REVISION Ns. 0

~ ~

RNU 3RV-3 INGLE F8R.LR3RLLE-N328 REVISION 0 SRRGENT A LUNDY DEstoNERp.,1(q CHECKER ,575 f M j

>EWo! WEIR 3 .

DESIGN SPECTRB RT NOINT/SLRS 328 VERT l rERns NICENED of 207. en ERCH siOE 07 JUN 79 i b),

> ORNr!NG 0.005 0.010 0.020 0.050 0 100 i 615BFH SffEET 26 OF 112

l g PROJECT NOS. 4266/4267 l CALC. NO. 165F l

)

FREQUENCY IN CP5 l son.o too.o too.o so.o so.o to.o s.o t.o a.o o.s j i,,, ,,, , , , , i to.o g,,, ,,,, , . . . .,,, . ,,,

, , , ,,,,,,,,,,,,,,,,,,,,,,iii,.,,..,,,,e,,3g0.0 j

15.0 , ,15 0 lo.0 . _10.0

~

9.o0 [:.00 8.00 - _

.00 5.o0 0.03 4.00 _ _4.00

~ ~

3 00 3.00 U t.00 ,, _2.00

= _

D . :

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1 50

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/"~%

V)' a.00

,t.00 N 0.80~ ~3 50 g : :

~

U w

0 90 _ _

3.60 8050 - _

3.50 C.40,, ,

3.40

'~

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0 30 3.30

--h

[--m :

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o.10

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0.cs

E

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,ie eiii iiii

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l o.001 0.004 0.006 0.010 0.020 0.040 0 060 0 100 0.t00 0.400 0 600 10 2.C j l FER!a0 IN SECBROS {

l l

8 l[,,_ 'YERT RE3reRSE 3rECTRR SPECTRR NO. S0-113-VS (s\

() ELEVRT!eN 807'-0" LOCRT!8N Reactor Building Slab REV! sten Ne. 0

l, - .. ,

"d**" v RWU 3RV-3 INGLE f8R LR3RLLE-N339 SRRGENT-& LUNDY otarowCR R. A cweenERA gfe.pe:.A CNGlWECAS . oE3 tow 3rECTRR RT Je!NT/3LR5 339 VERT rERR3 uloEwCo av roz ew ERew sipE

~rO .07 JUN 79, oRnrino o.cos o.oto a.oro c.oSo a.too Li 615BFH , . SHEET 30 OF 112 :

.( PROJECT NOS. 4266/4267 CALC. NO. 165F . .

i rREcuCuev IN cr3 !

see.e ses.e . ice.e so.e me.o so.e s.s e.e i .e e.s i a t i E i a f i I I, fe.-

t 9 i i iti t t i e i t t t t I i i i ttle t iI E i 'ili t i I I i f siis i

0.0

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le.0 ,,

l le.; ,

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g : :

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3.=

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ea 3.50 8 0.so. .

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o. set e.cos o.cos o.cto c.ato c.c4n o.oso c.100 c .t00 c.400 0.sco 1.0 t.o PERIBO IN SECBNDS i

g .

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LOCRTISH Fuel Pool Slabs REVIS18N No. 0 f j i

i l

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.Eu0: wrens . OEs!cu SrEcrRR RT aatwinchs sse VERT O 14 06 JUN 79 PERKS W10ENED BY 20% ON ERCH SIDE

( ORf1 PING 0.005 0.010 0.020 0.050 0.100 v0 379BFH SHEET 38 0F 112 '

I PROJECT NOS. 4266/4267 CALC NO. 165F

{

FREQUENCY IN CPS ]

500 0 200.0 100.0 50.0 10.0 10 0 5.0 2.0 10 05 I 20*0 ' i i s' i' s ' ' ' ' '''' ' ' ' ' ' '

i i i s' s'i s i e ' ' 's' i i sii i i i s' iii i0.0 u i ' a' ' ' a' su'i' i a' i i s' s'i i i iisi s'i i s i i sia in iisi sui i l

15.0_ -

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ML20237H120

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