ML17206A471

Responds to 780517 NRC & Ltr & Questionnaire Re Control of Heavy Loads Near Spent Fuel.Includes 3 Procedures Governing Movement of Heavy Loads.No Further Rev of Tech Specs Needed. Attached Oversized Drawing Available in CF Only

ML17206A471
Person / Time
Site:	Saint Lucie
Issue date:	10/04/1978
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Stello V Office of Nuclear Reactor Regulation
References
L-78-326, NUDOCS 7810110077
Download: ML17206A471 (61)

Text

REGULATORY XNFORHATXON DXSTRX BUTXON SYSTEM DOCKET NBR: 050-335 DOC DATE: 781004 RECIPIEAT: -

Stello, V. NORO ACCESS XON NBR: 7810110077 ORXGXNATOR- Uhri R.E. EUTFPL COPXES RECEIVED:

Florida Pwr. 6 Light Co. LTR 3 ENCL SUB JECT= SIZE: 45 Responds to 780517 NRC ltr questionnaire re "Control of Heavy Loads Near E

Spent Fuel." Includes 3 procedures governing movement of heavy loads.

No further rev of Tech Specs needed. Attached oversized drawing available in CF only. ko c Re P. Erickson (2).Advan'ced FOR ACTION

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~4 0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 J~v QN W~*y+

MEMORANDUM FOR: TERA Corp.

s FROM: US NRC/TIDC/Distribution Services Branch SUBJECT Special Document Handling Requirements

1. Please use the following special distribution list for the attached document.

Re@ F<a-e e9 P. ERIC'4$ eIhI (R) g404QCca4 2.~ The attached document requires the following special considerations:

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Do not send oversize enclosure to the NRC PDR.

0 Only one oversize enclosure return for Regulatory File storage.

was received please Q Proprietary information the NRC PDR send affidavit only to Q other: (specify) Qgyg T $ e~p+ QgII~ g ) p To Ip'0 L. XI ssT. pea p. KIp scesem IO-Io ag cc: DSB Files TIDC/DSB Authorized Signature

P. O. BOX 013100, MIAiVlli FL 33101 FLORIDA POWER 8( I.IGHT COMPANY october 4, 1978 L-78-326 Director of Nuclear Reactor Regulation At tenti.on: Hr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washing ton, D. C. 20555

'ear Hr. Stello:

Re: St. Lucie Unit 1 Docket Yo. 50-335 Responses to the NRC's information request of Hay 17, 1978, regarding "Control of Heavy Loads Near Spent Fuel" are attached. The Staff's letter makes mention of the possibility of radiation releases in excess.

of 10 CFR Part 100 guidelines as the basis for. its request. lt should be noted at this point that the licensing requirements for postulated radiological releases to the environment and potential radiation exposures to inplant personnel resulting from accidents involving spent fuel were reviewed and approved 'cy the Staff during the licensing process for St. Lucie Unit No. 1. These are reflected in the unit's Techn'cal Specifications. Conservative analyses of postulated radiological releases demonstrate that the resultant off-site doses are well below 10 CFR 100 guidelines. The facility emergency plan and procedures administratively provide appropriate assurance that doses to inplant personnel are acceptably low and vill not impact post-accident unit safety requirements.

Regarding the Stafx's statement on improving margins, it is further noted that in its Summary of Meeting to Discuss %i rgin in dated iIay 13, 1976, fol'owing a meeting in response to Technical'pecifications",

FPl letter dated March 11, 1976, the Sta f stated "...that it's (sic) 'ntent to impose additional safety margins in th Techn'cal it is rot Specifications oeyond those considered to exist in the staff's safety evaluation. But, that it is one of the functions of the Technical PEOPLE... Sc:RVliRG PEOPLE

Director of Nuclear Reactor Regulation Page Wo Specifications to assure that the safety margins considered to exist in the staff's safety evaluation do, in fact, continue to exist throughout the life of the facility". Since the St. Lucie Unit No. 1 facility Technical Specifications currently provide this assurance, further revision is neither indicated nor required.

b rt E. Uhrig Vice President REU/~4AAS/cpc Attachment cc: Hr. James P. O'Reilly, Region II Harold F. Reis, Esquire

ATTACHMENT Re: St. Lucie Unit 1 Docket; No. 50-335 Control of Hea Loads Question 1: Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.

Response 1: The attached drawings, 8770M-073 and 8770M-065, provide the general arrangement of the Reactor Building and the Fuel Handling Building and the laydown areas for heavy loads that are required to be moved over the reactor (during refueling), or the spent fuel storage pool.

(These drawings are also shown in the St. Lucie Unit 1 FSAR, Figures 1.2-8 and 1.2-18, respectively.)

Question 2: Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool. For each object listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying weight) and the frequency of movement.

Response 2: The following table delineates all objects required to be moved over the reactor core (during refueling) after the reactor vessel head is removed from the vessel:

NOMINAL ST. LUCIE DATA UNIT 1 Approxima te Approximate Approximate Approximate Carryigg Anticipat~d Size Wei ht ~Fre uenc~

Reactor Vessel Head 205" dia. x 14'58,400 lbs. 30 ft.

8'50" Reactor Vessel sq. x 128,800 lbsi 11 Upper Internals (with lifting rig)

Upper Internal Lifting Rig 200" dia. x 238" 14,000 lbs. 20 fthm Fuel Handling Tool 3" dia. x 35'"

600 lbs. 25 ft. 520 Spent Fuel Assemblies sq x 157" 1,579 lbs 4 ft 60 New Fuel Assemblies 8" sq. x 157" 1,579 lbs. 4 ft 60 1

Loads are moved from their point of origin to the laydown area as shown on drawings provided in response to Question l.

The objects required to be, moved over the spent fuel storage pool are; Fuel Handling Tool 42'ong 100 lbs 5 ft. 60 Spent Fuel Shipping Cask 50" dia. x 200" 50,000 lbs 42 ft. As Required Spent Fuel Assemblies 8" sq. x 157" 1,280 lbs. 5 ft ~ 60 Shipping Cask Cover 25-1/2" dia. x 8-3/8" 750 lbs. 5 As Required 2

Approximate height above Reactor Vessel Flange or Spent Fuel Racks 3

Frequency per refueling or per year

Question 3: What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?

Response 3: The following is a table of spent fuel casks which have been used or are currently available for use at St. Lucie No. 1 Cask Heieht Base Diameter ~e~ceht ~she e National Lead Xndustry *193 n 33N 25 tons right circular NLZ 1/2 LWT (1) cylinder Nuclear Assurance Corp. *200 N 4*50 >>

25 tons right circular NAC - 1 (2) (NFS-4) cylinder

• Shipping lid removed during fuel handling operations.

<<*Base of cask; body diameter >39.2" ~

(1) Docket No. 71-9010 (2) Docket No. 71-6698

I Question 4: Identify any heavy load or cask drop analyses performed to date for your facility. Provide a copy of all such analyses not previously submitted to the NRC staff.

Response 4: Section 9.1.4.3 of the FSAR provides two postulated cask drop accidents for St. Lucie. A vertical drop is analyzed to determine if the leaktight barrier of the spent fuel pool can be breached. As per our response to Question 6, the leaktight integrity of the Spent Fuel Pool is maintained for this case.

A tipped cask drop was also considered. The radiological consequences of the tipped cask drop were provided in FSAR Section 15.4.3 and were subsequently updated by the "Spent Fuel Storage Facility Modification Safety Analysis Report" to accommodate the increased spent fuel storage capability. Reportable Occurrence 335-78-25 dated August 7, 1978, notified the Staff of an error in the original FSAR cask drop analysis. A reanalysis, wherein it is conservatively assumed that all spent fuel can be struck by the cask drop, has been completed. The appropriate Technical Specification, bases, and associated safety evaluation were transmitted with the proposed Technical Specification amendment by letter dated October 2, 1978 (L-78-317).

Question 5: Identify any heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the time the load is moved. Identify what equipment could be affected in the event of. a heavy load handling accident (piping, cabling, pumps, etc.) and discuss the feasibility of such an accident affecting this equipment. Describe the basis for your conclusions.

Response: St. Lucie Unit 1 is an operating plant 'and as such no movement of heavy loads over equipment required for safe plant shutdown at the time. the load is moved would be expected within con-tainment or other indoor areas (RAB, D/G building) containing safe shutdown related equipment. All roads in the plant area for Unit 1 are designed for H-20 loading in accordance with the American Association. of State Highway Officials (AASHO). All pipes and duct banks under on-site roads are designed to resist H-20 wheel loads.

Roads along the route used by the fuel handling cask transporter are designed for the transporter wheel loads. All duct banks and pipes under these roads are designed to withstand. the loads from the fuel handling cask transporter wheels. There is no safe

.shutdown equipment along the fuel handling cask transporter route.

I'uring transportation of Unit 2 NSSS components, the transport path from the NSSS component laydown area to the construction hatch in the Unit 2'Containment Building will be provided with cribbing or other load distribution devices as required to

. assure proper load distribution on plant roads. All buried facilities in the path of these heavy equipment loads are designed to accommodate these load distributions. NSSS transport vehicle tuxning radius and speed will be administratively controlled, thus, the overturning of the transport vehicle is. highly-unlikely.

Question 6: If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a 'handling accident which could result in water, leakage severe enough to uncover the spent fuel. Describe the basis for your conclusions.

Response: Section 9.1.4.3 of the FSAR provides an analysis for a 25 ton cask drop from the maximum lift height of 58 feet. The analyzed target area for this cask drop analysis was the cask storage area in the northeast corner of the pool. The results of this analysis demonstrate." that spent fuel pool leaktight integrity it is maintained. Additionally should be noted that by design the wall betweenthe cask storage area and the spent 'fuel pool if

'precludes uncovering of the spent fuel even leakage in the cask storage area is postulated. It should be further noted that in the event that leakage is postulated there are numerous alternative makeup water sources available to the spent fuel pool as discussed in FSAR Section 9.2..3.

Question 7: Describe any design features of your facility which affect the potential for a heavy load handling accident involving spent fuel, e.g., utilization of a single failure-proof crane.

Response 7: The St. Lucie Unit 1 fuel handling system is designed by means of interlocks, travel limit devices, and other protective devices to minimize the probability of malfunction or operator initiated actions that could cause spent fuel damage. As discussed in Section 9.1.4 of the PSAR.

a) The fuel cask handling crane does not allow the cask to travel over spent fuel because of the geometrical design of the crane runway, the physical design of the building, and the travel limit switch interlock circuitry.

b) The crane is equipped with a two cable system with an associated safety factor of 6 9 Zn the unlikely event of a cable failure the safety factor is reduced by only one-half.

c) The hoist motors are torque limited to approximately 200%; when this torque is reached the electrical circuit is tripped.

d) Diverse and redundant upper limit switches preclude block engagement.

e) With loss of electrical power both stopping/holding brakes automatically set. They are capable of stopping a 105 ton load within 1" assuming maximum lowering speed. Zn the unlikely event of a brake failure, the remaining brake can stop this load, in 2".

Question 8: Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or ecpxipment recpaired for the safe shutdown of a plant that is operating at the time the move occurs ~

Response 8: Procedures currently in effect at St. Lucie for movement of heavy loads near spent fuel are attached:

M-0305 Reactor Vessel Closure Head - Removal and Installation M-0306 Reactor Vessel Internals - Removal and Installation M-0913 General Operating Procedure for Handling and Loading of the NFS-4 cask

Question 9: Discuss the degree to which your facility complies with the eight (8) regulatory .positions delineated in Regulatory Guide 1.13 (Revision 1, December, 1975) regarding Spent Fuel Storage Facility Design. Basis.

Ludie Unit Nl meets the intent of the regulatory positions of

Response

" St.

Safety Guide 1.13 (3/10/71) as presented in the FSAR sections, referenced below:

The .following is a listing of. the FSAR sections wheze a repsonse to each position may be found=

Regulatozy Position 1: 3.7.5, 3.8, 9.1.2.3 Regulatory Position 2: '3.2; 3.8, '9.1.2.3 Regulatory Position 3: 3.7i 9.1.2.3 Regulatory Position 4: 7.6.1.2, 9.4.6('12.2.2.5~ 15.4.3 Regulatory Position 5: 9.1.2.3, 9.1.4.3*, 15.4.3 Regulatory Position 6: 9.1.3.4 Regulatory Position 7: 9.1.2.5, 9.1.3.6, 12.1.4 Regulatory Position 8: 9.1.3.4

~As modified by the Spent Fuel Storage Facility Modification Safety Analysis Report transmitted via L-77-273, dated 8/31/77. As described therein, no other modifications were recpxired in the above. Referenced FSAR/Regulatory Guide 1.13 positions are applicable.

A review of the changes in Revision 1 shows that the facility design is capable of meeting the intent of the,l2/75 version of the Regulatory Guide as well.

I Revision 3 I

FLORIDA POHER & LIGHT COMPANY 'r STe LUCIE PLANT FflH INFtI8MA. ll) NONLII GENERAL MAINTENANcE PRocEDURE No. M-0305 This document is not controlled. before use verify information with a controlled document.

l. 0

Title:

REACTOR VESSEL CLOSURE HEAD - REMOVAL AND INSTALLATION 2 0 Review and A royal:

Reviewed by the Plant Nuclear Safety Committee . '974'.

Approved by c . - Ai Plant Manager ~

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Rev. 3 Reviewed by the FZG 1978 Approved by Plant  ?~ger a 1978

3. 0 Pureeee:

This procedure delineates the instructions necessary for the removal and installation of the reactor vessel closure head.

4.0 Precautions and Limits:

4.1 All work shall be performed in accordance with a radiation work permit.

4.2 The reactor coolant system water level is being controlled below the reactor vessel flange.

4.3 Do not use hammer blows on the vessel'r closure head.

4.4 Hold Points, as delineated in this procedure, sha11 be adhered to.

5 0 'Related S stem Status:

5.1 The shutdown cooling system shall be in operation.

6.0

References:

1 6.1 St. Lucie Plant Quality Instructions 5, 13, and 17.

6.2 Reactor Vessel Assembly Instruction Manual, Volume I 7.0 Records Re uired:

7.1 Completed portions of this procedure as specified in the authorizing'P.N.O. shall be attached to the P.M.O." record copy and filed per PSL Tech. Spec. 6.10.2

age 2 of 8

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evision 3 GENERA/ MAINTENANCE PROCEDURE NO. M-0305 REACTOR VESSEL CLOSURE HEAD REMOVAL AND INSTALLATION 8 0 Materials and E ui ment Re uired:

8.1 Reactor Vessel Closure Head Lift Rig Assembly.

8.2 Two Reactor Vessel Alignment Pin Assemblies.

8.3 Two

'I Alignment Pin Pipe Plugs 8 4 Two Alignment Pin O-rings.

8.5 Two Alignment Pin Lifting Eye Bolts.

8.6 One Alignment Pin Wrench.

8.7 Fifty-Two (52) Closure Head Stud'Hole Plugs.

8. 8 Lubricants:

8.8.1 Super Moly No. 40240 8.8. 2 Neolube 8.8.3 Dow Corning 44 8.9 Cleaning Materials:

8.9.1 Approved solvent 8.9.2 Lmt free rags 8.9.3 Stainless steel wire brushes 8.9.4 Utility buckets

age 3 of 8

~ ~ evision 3 GENERAL MAINTENANCE PROCEDURE NO. M-0305 REACTOR VESSEL CLOSURE HEAD REMOVAL AND INSTALLATION 9.0 Detailed Procedure: Only applicable portions of this procedure need be performed.

9.1 Reactor Vessel Closure Head Removal 911 Place new reactor head 0-Rings within the head support columns.

9.1 2 Remove number one and number twentyeight reactor vessel head studs, studs, nuts and washers and store in stud

9. 1.3 Attach the reactor vessel closure head lugs on the closure head.

lift rig to the NOTE .'., The lift rig shallshownbe oriented relative to the closure head as in Appendix A, Sheet 1 of thee procedure.

9.1 4 HOLD POINT - Clean the reactor vessel head alignment pins QC Verify and the reactor vessel flange stud holes numbers one (1) and twenty-eight (28) in accordance with Quality Instruction 13 PR/PSL-2, "Cleaning of 0>>acuity Controlled Material."

9.1.5 . Install the reactor vessel alignment. pin 0-rings on the alignment pins.

NOTE: Neolube lubricant should be used to facilitate proper installation and positioning of the O-rings.

9 1.6 Install the reactor vessel alignment pin lifting eye'bolts in the top of the alignment pins.

9.1.7 Remove the reactor vessel alignment pin pipe plugs to provide venting of the alignment pins during installation.

9.1.8 HOLD POINT - Lubricate the reactor vessel head alignment QC Verify pin threads with pre-added Super Moly No.

40240 lubricant.

NOTE: Apply lubricant only to the alignment pin threads.

Do not lubricate the reactor vessel flange stud holes or allow lubricant to come in contact with stainless steel or Ni-Cr-Fe alloy surfaces.

9.1.9 Install the reactor vessel alignment pin assembly (PC. 216-01) in reactor vessel flange stud hole number one (1) and alignment pin assembly (PC. 216-06) in flange stud hole number twenty-eight (28) until each pin is tightly bottomed in its respective hole.

ge 4 of 8 Revision 3 GENERAL MAINTENANCE PROCEDURE NO. M-0305 REACTOR VESSEL CLOSURE HEAD - REMOVAL AND INSTALLATION 9 0 Detailed Procedure: (Cont'd.)

9.1 Reactor Vessel Closure Head Removal (Cont'd.)

Torque the reactor vessel alignment pin assemblies snugly.R3 using the alignment pin wrench. R3 9.1. 11 Reinstall the reactor vessel alignment pin pipe plugs in the alignment pins.

9.1.12 Deleted 9.1.13 Slowly raise the reactor vessel closure head assembly and check the elevation of the mating surface of the closure head with a transit or level at three points 120 apart and directly below the "pick-up points" of the closure head.

NOTE: The reactor vessel closure head mating surface should be parallel to the reactor vessel mating surface within 0.005 inches per foot during lifting operations.

9.1.14 Remove the reactor vessel closure head from the reactor vessel and apply Dom:Corning 44 to flange surface to prevent corrosion; then place the closure head on the closure head stand.

9.2 Reactor Vessel Closure Head Installation 9.2. 1 Remove and discard the. closure head 0-rings from the closure head flange.

NOTE: Do not discard the 0-ring retainer clips and rings.

These items will be used in subsequent 0-ring installations.

9.2.2 HOLD POINT Clean all mating surfaces and 0-ring grooves QC Verify on both the closure head and vessel in accordance with Quality Instruction 13 PR/PSL-2, "Cleaning of Quality Controlled Material."

age 5 of 8 Revision GENERAL MAINTENANCE PROCEDURE NO M-0305 REACTOR VESSEL CLOSURE HEAD REMOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.2 Reactor Vessel Closure Head Installation (Cont'd.)

o 9.2,3 HOLD POINT - Clean two new metal closure head 0-rings QC Verify in accordance with Quality Instruction 13 PR/PSL-2, "Cleaning of Quality Controlled Haterial."

9.2.4 Install the new closure head 0-rings into the grooves provided on the mating surface of the closure head.

Secure the 0-rings to the closure head with the 0-ring retainer clips and rings.

9.2.5 Slowly raise the reactor vessel closure head assembly and check the elevation of the mating surface of the closure head with a transit or level at three points 120 apart and directly below the "pick-up points" of the closure head.

NOTE: The reactor vessel closure head mating surface should be level to within 0.005 inches per foot during lowering operations 9 2 6 Orient the axes of the closure head assembly to the corres-ponding axes. of the reactor vessel.

9.2.7 Center the closure head assembly abov'e and to within one (1) inch of the reactor vessel centerline.

9.2.8 Slowly lower the closure head assembly to engage the reactor vessel alignment pin assemblies; then continue to lower the closure head assembly until the 0-rings rest on the mating surface of the reactor vessel flange.

9.2.9 Remove the reactor vessel alignment pin pipe plugs to provide venting of the alignment pins during removal.

9.2.10 Loosen the reactor vessel alignment pin assemblies using the alignment pin wrench.

9 2 11 Remove the reactor vessel alignment pin assemblies from the reactor vessel flange.

9.2 12 Remove the reactor vessel stud hole plugs from each of the fifty-two (52) remaining stud holes.

NOTE: Caution should be exercised when decreasing the diameter of the expandable stud hole plugs (turning the T-handle counter-clockwise) to prevent dissen-gagement of the T-handle from the plug body.

9.2.13 HOLD POINT Clean each stud hole in accordance with QI 13 QC Verify PR/PSL-2 and run the GO NO/GO gauge in each hole to assure that the threads are clean and in good condition.

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I I I "APPENDIX A, Sheet 3" Closure Head Assembly

Page 1 of 14 Revision 3 FLORIDA POHER & LIGHT COMPANY ST. LUCIE PLANT GYRAL MAINTENANCE PROCEDURE NO'. M-0306

1.0 Title

IM RS 8 5"""'-~ '-'"~--: II:-'ll

document is not controIfed. Hefore use, I'EACTOR VESSEL INTERNALS - REMOVAL AND IN 5'N s controlled document, 2.0 Review and A royal:

Reviewed by the Facility Review Group '97( .

Approved by ~'..".- ...>> Ice Plant Manager ~ (.-ii 19 7 r..

r iMvision 3 i<eviewed by FdQ 1978 Approved by LJ Plant 'wnager Z. 1~7G

3. 0 Puruose:

'his procedure delineates the instructions necessary for the removal and installation of the reactor vessel internals.

~.0 Precautions and Limits:

4.1 All work shall be performed in accordance with a radiation work permit.

4.2 The reactor coolant system water level is being controlled below the reactor vessel flange.

R/3 4.3 Do not use hammer blows on the vessel.

4.4 Personnel shall not be allowed on the lift rigs during lifting operations.

4.5 At no time shall jogging of the crane be allowed when the lift rigs are being used.

4.6 The lift rig tie rods shall maintain a minimum thread engagement lifting and of five (5) inches during lowering operations.

4.7 The maximum deviation from the horizontal on any of the structural components when lifted by the lift rigs shall not exceed 0.005 inches per foot.

4.8 The polar crane shall be operational.

4.9 Hold Points, as delineated in this procedure, shall be adhered to.

Revision 3 GENERAL MAINTENANCE PROCEDURE NO. M-0306 REACTOR VESSEL INTERNALS REMOVAL AND INSTALLATION 5.0 Related S stem Status:

5.1 The shutdown cooling system shall be in operation.

6.0

References:

6.1 St. Lucie Plant Quality Instructions 5, 13, and 17.

6.2 Reactor Vessel Assembly Instruction Manual Volumes I and II.

6.3 Appendix "A".

7.0 Records Re uired:

7.1 Completed portions of this procedure as specified in R/3 the authorizing P.W.O. shall be attached to the P.W.O.

record copy and filed per PSL Tech. Spec. 6.10.2 8.0 Materials and E ui ment Re uired:

8.1 Standard mechanic's tool box.

8.2 Lift rig tie rod assembly.

8.3 Upper guide structure lit t r98.

8.4 8.5 Core. support barrel lift rig.

Core support barrel lifting bolt wrench assembly.

8.6 Lubricants.

8.6.1 Neolube 8.7 Cleaning materials.

8.7.1 Approved solvent.

8.7.2 Lift free rags.

8.7.3 Stainless steel wire brush.

8.7.4 Utility buckets.

8.8 100 ft.-lb Torque Wrench R/3

Page 3 of 14 Revision 3 P

GENERAL MAINTENANCE PROCEDURE NO.,H-0306 REACTOR VESSEL INTERNALS RPfOVAL AND INSTALLATION 9.0 Detailed Procedure: Only applicable portions of this procedure R/ 3 need be performed.

.9.1 Upper Guide Structure Removal from the Reactor Vessel 9.1.1 Position and center the polar crane hook over the upper guide structure lift lift rig; then engage the polar crane hook to the rig clavis pin.

9.1.2 Slowly hoist the upper guide structure lift rig from the storage area and position it on the, operating floor of the containment building.

9.1. 3 Notify the Operations Department to increase the water level in the refueling cavity to an elevation of fifty-five (55) feet.

9.1.4 HOLD POINT Clean the threads and the underside of the QC Verify bolt heads on the upper guide structure lift rig lifting bolts in accordance with Quality Instruction 13 .PR/PSL-2, "Cleaning of Quali.ty Controlled Haterial."

9.1.5 HOLD POINT Lubricate the threads and the underside of QC Verify the bolt heads on the upper guide structure liftNeolube.

rig lifting bolts with two (2) coats of 9.1.6 Raise the lift rig lifting bolt wrench assemblies until the hook on the wrench assembly, shaft protrudes from the lifting bolt guide tube (approximately one (1) foot)';

then attach the hook on the lip of the guide tube. The wrench assemblies are now in their storage positions.

9.1. 7 Slowly hoist the upper guide structure lift rig and center above and to within one (1) inch of the reactor vessel centerline.

9.1.8 Orient the axes of the upper guide structure lift rig to the corresponding axes of the reactor vessel.

9.1.9 Slowly lower the upper guide structure lift rig until the lift rig guide bushings engage the reactor vessel guide pins; then continue to lower the upper guide structure lift rig until it rests on the reactor vessel and the load on the polar crane is released.

9.1.10 Raise the lift rig lifting bolt wrench assemblies them from their storage positions; then and slowly disengage lower the lifting bolts into the threaded holes of the upper guide structure.

t Page 4 Revision of 14 3

GENERAL MAINTENANCE PROCEDURE NO. M-0306 REACTOR VESSEL INTERNALS R&fOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.1 (Cont'd.)

9.1.11 Thread the three (3) lifting bolts into the upper guide structure top flange and torque to fifty (50) ft-lbs.

9.1.12 Detach the polar crane hook from the upper guide structure lift rig clevis pin.

9.1. 13 Attach the instrumentation hoist sling assembly to the polar .crane hook.

9.1.14 Raise the instrumhntation hoist sling assembly over the center of the lift rig.

NOTE: Ensure that the instrumentation hoist sling cables straddle the tie rod assembly of the lift rig.

9.1.15 Tilt the instrumentation hoist sling assembly laydown bars outwards 90 Slowly raise the instrumentation h ist "1'ng a"-cmb y unt'1 the instrumentation pick-up adapter is above the lift rig working platform.

9. 1. 17 HOLD POINT Clean the threads on the instrumentation QC Verify pick-up adapter in accordance with Quality Instruction 13 PR/PSL-2, "Cleaning, of Quality Controlled Material."

9. 1. 18 HOLD POINT Lubricate the threads on the instrumentation QC Verify pick-up adapter with two (2) coats of Neolube.

9.3.. 19 Slowly lower the entire instrumentation hoist sling assembly and observe that the pick-up adapter enters the center hole of the instrument plate. Stop the crane when a small amount of slack appears in the sling cables.

NOTE: During the lowering operation, the hoist sling cable guide plate should be positioned on the lift rig working platform. It may be necessary to adjust the polar crane position to ensure that no rubbing of the hoist sling cables on the guide plate occurs.

9.1.20 Manually lower the instrument hoist tool; then insert the hoist tool into the instrumentation pick-up adapter.

9.1.21 Turn the instrument hoist tool clockwise to thread the instrumentation pick-up adapter into the instrument plate.

Torque to fifty (50) ft-lbs.

t Page 5 Revision of 14 3

MAINTENANCE PROCEDURE NO. M-0306 REACTOR VESSEL INTERNALS REMOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.1 (Cont'd.)

9.1.22 Remove the instrument hoist tool from the instrumentation pick-up adapter.

9.1.23 Raise the instrument package at six (6) inches per minute for approximately threp (3) feet.

CAUTION: During this lifting evolution, continuously monitor the load sensing device for hang-ups.

Weight of the instrument package is seven thousand (7000) pounds. Stop the crane if this load is exceeded by six hundred (600) pounds. Investigate and correct hang-up conditions.

5 9.1. 24 Continue to raise the instrument package at six (6) feet per minute until the top of the instrumentation pick-up adapter is above the hoist sling assembly laydown bars.

9.1. 25 Tilt the hoist "linc assembly laydown bors upward; then slowly lower the hoist sling assemoiy until tne pick-up adapter rests on the laydown bars.

NOTE: Ensure that the locating pins on the laydown bars are engaged into the pick-up adapter.

9.1. 26 Detach the polar crane hook fzom the i'nstrumentation hoist sling; then attach the polar crane hook to the upper guide structure lift rig clevis pin.

9.1.27 Raise the upper guide structure at a maximum speed of six (6) inches per minute for approximately three (3) feet.

CAUTION: During this lifting evolution, continuously monitor the load sensing device for hang-ups.

Weight of the instrument package, upper guide structure, and lift rig is one-hundred twenty-six thousand eight hundred (126,800) pounds.

Stop the crane if this load is exceeded by five correct thousand (5000) pounds. Investigate and hang-up conditions.

9.1.28 Raise the upper guide structure clear of the reactor vessel and reactor vessel guide pins.

9. 1. 29 Center the upper guide structure ovez the storage area; then lower the guide structure until it rests in the storage area and the load on the polar crane is released.

Page 6 of 14 Revision 3 GENERAL MAINTENANCE PROCEDURE NO. Ef-0306 REACTOR VESSEL INTERNAL'S RBIOVAL AND INSTALLATION

9. 0 Detailed Procedure: (Con'd. )

9.1 (Cont,'d.)

9.1.30 Detach the tie rod assembly from the upper guide structure lift rig and store in a safe place.

CAUTION: The tie, rod assembly shall be removed from the upper guide structure lift rig at all times while the lift rig is in storage with the upper guide structure to gain clearance for the refueling machine.

9.2 Upper Guide Structure Assembly to the Reactor Vessel 9.2.1 Notify the Operations Department to lower the water level in the refueling cavity to a level of fifty-five (55) feet to provide access to the upper guide structure lift rig platform.

9.2..2 Attach the tie rod assembly to the upper guide structure lift rig.

9.2. 3 Ho'f st tll+ util&7 Auida st ever>> retro e~aa va 1 c~ v4

~q Ja <<aaa i ~

sJ g cavoc l. 1.

latUJ y

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clear of the storage area; then center the upper guide structure and lift rig assembly above and to within one (1) inch of the reactor vessel centerline.

9.2.4 Orient the axes of the upper guide structure and lift rig. assembly to the corresponding azes of the reactor vessel.

9.2.5 Slowly lower the upper guide structure and until the lift lift rig assembly rig guide bushings engage the reactor vessel guide pins; then continue to lower the upper guide structure and lift rig assembly until rests on the reactor vessel and the load on the polar it crane is released.

CAUTION: Lower the last three (3) at slow speed, six (6) inches per minute maximum, and monitor the load sensing device for hang-ups. Investigate

'nd correct hang-up conditions.

9.2. 6 Detach the polar crane hook from the upper guide structure lift rig clevis pin.

9.2.7 Attach the instrumentation hoist sling assembly to the polar crane hook.

Page 7 of 14 Revision 3 GENERAL 5!AINTENANCE PROCEDL'RE NO. 1&0306 REACTOR VESSEL INTERNALS I.:":OVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.2 (Cont'd.)

9.2. 8 Position the instrumentation hoist sling assembly over the center of the lift rig.

NOTE: Ensure that the instrumentation hoist sling cables straddle..the tie rod assembly of the lift rig.

9.2.9 Slowly raise the instrument package until the top of the instrumentation pick-up adapter is approximately six (6) inches above the, hoist sling assembly laydown bars.

9.2.10 Tilt the instrumentation hoist sling assembly laydown bars outward 90 9.2.11 Slowly lower the instrument package until the load is released from the polar crane.

NOTE: It may be necessary to adj L 'he polar crane position to ensure that no rubbing of the instrumentation hoist sling cables on the guide plate occurs.

9.2.12 Manually lower the instrument hoist tool; then insert the hoist tool into the instrumentation pick-up adapter.

9.2.13 Turn the instrument hoist tool counter-clockwise to enscrew the instrumentation pick-up adapter from the instrument plate; then raise the pick-up adapter approximately one (1) foot.

9.2. 14 Remove the instrument hoist tool from the instrumentation pick-up adapter.

9.2.15 Raise the instrumentation hoist sling assembly until I

the top of the instrumentation pick-up adapter is above the hoist sling assembly laydown bars.

9.2.16 Tilt the hoist sling assembly laydown bars upward; then slowly lower the hoist sling assembly until the pick-up adapter rests on the laydown bars.

NOTE: Ensure that the locating pins on the laydown bars aze engaged into the pick-up adapter.

Page 8 of 14 Revision 3 GENERAL MAINTENANCE PROCEDURE NO. If-0306 REACTOR VESSEL INTERNALS REMOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.2 (Cont'd.)

9.2.17 Detach the polar crane hook from the instrumentation hoist sling; then attach the polar crane hook to the upper guide structure lift rig clevis pin.

9.2.18 Turn the lift rig lifting bolt wrench assemblies counter-clockwise to unscrew the lifting bolts from the upper guide structure.

9.2.19 Raise the lift rig lifting bolt wrench assemblies until the hook on the wrench assembly shaft protrudes from the lifting bolt guide tube (approximately one (1) foot);

then attach the hook on the lip of the guide tube. The wrench assemblies are now in their storage positions.

9.2.20 Raise the upper guide structure lift rig until it clears the reactor vessel guide pins; then store the in the storage area.

lift rig 9 3 Core Support 3arre Remove from thc Rcacto Vessel

9. 3.1 Remove the upper guide structure in accordance with Section 9.1 of this procedure.

9.3.2 Ensure that all fuel has been removed from the reactor vessel.

9.3.3 Attach the tie rod assembly to the core support barrel lift rig.

9.3.4 Notify the Operations Department to lower the water level in the refueling cavity to an elevation of forty-five (45) feet to avoid submerging the polar crane hook.

9.3.5 Slowly hoist the core support barrel lift rig and center above and to within one (1) inch of the reactor vessel centerline.

9.3. 6 Orient the axes of the core support barrel lift rig to the corresponding axes of the reactor vessel.

9;3. 7 Slowly lower the core support barrel lift rig until the lift rig guide bushings engage the reactor vessel guide lift rig until pins; then lower the core support barrel it rests on the reactor vessel and the load on the polar crane is released.

page 9 of 14 Revision 3 GENERAL MAINTENANCE PROCEDURE No. M-0306 REACTOR VESSEL INTERNALS REMOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.3 (Cont'd.)

9.3.8 Detach the polar crane hook from the tie rod assembly and hoist the hook away from the lift rig.

9.3.9 Move the refueling machine over the reactor vessel.

9.3.10 Manually lower the core support barrel lifting bolt wrench assembly to engage one (1) of the core support barrel lifting bolts.

9.3.11 Slowly turn the lifting bolt wrench assembly in the clockwise direction to disengage the lifting bolt from its auxiliary thread.

CAUTION: Maintain a firm grip on the wrench to prevent a sudden drop of the lifting bolt into the threaded hole of the core support barrel when the lifting bolt auxiliary thread is disengaged.

9.3.12 Slowly 3ower the. lifting bolt into the threaded hole of thc core support barre19 taaera a.uia'1 tali litting bola.

wrench assembly clockwise to thread the lifting bolt into the core support barrel.

ft-lbs.

Torque to fifty (50) 9.3.13 Repeat Steps 9.3.10 through 9.3.12 for the two remaining lifting bolts.

NO. 1 N0.2 9.3.10 9.3.10 9.3.11 9. 3.11 9.3.12 9.3; 12 9.3. 14 Move the refueling machine over the upper guide structure storage area.

9.3.15 'enter the polar crane hook above and to within one (1) inch of the reactor vessel centerline; then attach the hook to the tie rod assembly.

9.3.16 Raise the core support barrel at six (6) inches per minute maximum for approximately three (3) feet.

CAUTION: During this lifting evolution, continuously monitor the load sensing device for hang-ups.

Weight of the core support barrel and assembly is two hundred fifty-eight lift thousand rig

Page 10 of 14 Revision GENERAL NAIHTENANCE PROCEDURE NO. H-0306 REACTOR VESSEL INTERNALS <<RBfOVAL AND INSTALLATION

9. 0 Detailed Procedure: (Cont 'd. )

9.3 (Cont'd.)

9.3.16 (Cont'd.)

(258,000) pounds. Stop the crane load is exceeded by twenty-five thousand if this (25,000) pounds. Investigate and correct hang<<up conditions.

9.3.17 Notify. the Operations Department to 'commence filling the refueling cavity to maximum refueling level; then continue to raise the core support barrel at six (6) feet per minute maximum until the core support barrel is clear of the reactor vessel and reactor vessel guide pins.

9.3.18 Center the core support barrel over the storage area; then lower the core support barrel until it rests in the storage area and the load on the polar crane is released.

Detach the polar crane hook from the tie rod assembly.

'.3.19 9.4 Core Support isarrei Assembly to the Reactor Vessel 9.4.1 Position and center the polar crane over the core support barrel storage area; then engage the polar crane hook to the lift rig tie rod assembly.

9. 4.2 Raise the core support barrel assembly to clear the reactor vessel and ractor vessel guide pins.

9.4. 3 Center the core support barrel assembly above and to within one (1) inch of the reactor vessel centerline.

9.4.4 Orient the axes of the core support barrel -lift rig to the corresponding axes of the reactor vessel.

9.4.5 Notify the Operations Department to commence lowering the water level in the refueling cavity to an elevation of forty-five (45) feet to avoid submerging the polar crane hook.

9.4.6 Slowly lower core support barrel assembly until the lift rigthenguidethebushings engage the reactor vessel guide pins; on the lower the core support barrel until reactor vessel it and the load on the polar crane rests is released.

age ll of Revision 14 GENERAL MAINTENANCE PROCEDURE NO. M-0306 REACTOR VESSEL INTERNALS REMOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont'd.)

9.4 (Cont'd.)

9.4 ' (Cont'd.)

CAUTION: Lower the last three (3) feet at slow speed, six (6) inches per minute maximum, and monitor the load sensing device for hang-ups. Inves-tigate and correct hang-up conditions.

9.4.7 Detach the polar crane hook from the tie rod assembly and hoist the hook away from the lift rig.

9.4.8 Move the refueling machine over the reactor vessel.

9.4.9 Manually lower the coze support barrel lifting bolt wrench assembly to engage one (1) of the core support barrel lifting bolts.

9.4.10 Slowly turn the lifting bolt wrench assembly in the counter-clockwise direction to disengage the lifting bolt from the core support barrel.

9.4.11 Slowly raise the lifting bolt (approximately 1/4 inche );

then turn the lifting bolt wrench assembly in the counter-clockwise direction to engage the lifting bolt auxiliary threads to the lift rig. Turn the wzench assembly at least five (5) full turns to ensure safe storage of the lifting bolt in the lift rig.

9.4.12 Repeat Steps 9.4.9 through 9.4.11 for the two remaining lifting bolts.

NO. 1 NO.Z 9.4.9 9.4.9

9. 4. 10 9.4.10 9.4.11 9.4.11 9.4.13 Move the refueling machine over the upper guide structure storage area.

9.4.14 Center the polar crane hook above and to within one (1) inch of the reactor vessel centerline; then attach the hook to the tie rod assembly.

9.4.15 Raise the core support barrel lift rig until it clears lift rig in the reactor vessel guide pins; then store the the storage azea.

9.4. 16 Detach the polar crane hook from the tie rod assembly.

t Page 12 Rev.

of .14 GENERAL MAINTENANCE PROCEDURE HO. i&0306 REACTOR VESSEL INTERNALS RRfOVAL AND INSTALLATION 9.0 Detailed Procedure: (Cont.)

9.5 Removal of CEDM Extension Shafts From The Upper Guide Structure 9.5'.1 Couple extension 'shaft handling tool to extension shaft in accordance with Operations Procedure 80110022, "Coupling and Uncoupling of CEA Exten-sion Shafts."

9.5.2 Remove extension shaft from upper guide structure and store with handling tool in designated storage area.

9.6 Installation of CEDM Extension Shafts In The Upper Guide Structure 9.6.1 Couple extension shaft handling tool to extension shaft in accordance with Operations Proc'.~ure 80110022, "Coupling and Uncoupling of CEA Exten-sion Shafts."

9.6.2 Install extension shaft in upper guide structure.

9.6.3 Uncouple extension shaft handliug tool from exten-sion shaft in accordance with Operations Procedure 80110022, "Coupliag and Uncoupling of CEA Extension Shafts."

R/3

Page l3 oE 1st

~

General Maintenance Procedure No. M-0306 Revision ICI HOI S LIFT POINT FOR CRANE HOOK ASSEMBLY UPPER

~

GUIDE STRUCTURE LIFT R I G

~

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UP-POSIi10'.I);",~-*'~~~)-',4 ~Q>(-.~Pj~g STALK OP"-i~l ING EADER B-'Al

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Page >4. of (q.

General Haintenance Proce'dure NO. >f-0306 Revision g APPED)IX A, Sheet 2 1tFT PO1NT FOR CRANE STAND'RD CORE SUPPORT BARREL LIFT R IG 4

i)ljl i I ii, II',

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~ TIE ROD ASSE MBLY LIFT BOLT I

ilk 05$

TORQUE TOOL

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GUIDE BUSHING FOR AirACHWENi-, R.V GUI" pO

'OINT (3 PLACES)

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~ APPENDIX A Pa~e l6 'of l6 CEA EXTENSION SKKFT

~ ~ INSTAI LATION 13ACKINC LOG Page 2 CEA Hole CEA Extension Number Shaft Number Initial Date 49 50.

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Page 1 l978 of 10 ST- LUCIE PLANT UNIT NO. 1 SaOBlloe~ugg~

GENERAL MAINTENANCE PROCEDURE NO. M0915l 3 A t 3 g g ~

REVISION 2

1. 0 TITLE:

GEiLERAL OPERATING PROCEDURE FOR HAG)LING AK) LOADING OF THE NFS-4 CASK 2 0 APPROVAL:

Reviewed by Faciligp Review Group W!>Sf.

Approved by, . ar/':<~>~ g~~

I Plant Manager.

Rev.2 Reviewed by FRG 1978 Approved by Plant Manag 1978 3 0 PURPOSE/SCOPE:

3.1 This procedure applies to the general building and loading of the NFS-4 cask. It covers all movements of the cask from the trailer to the spent fuel pool and return to the trailer.

4.0 REFERENCES

4.1 Outline drawing lA-A-1104 gives a brief description of the cask.,

e

. 4.2 Drawing lA-A-'1102 shows the cask on the trailer and bei~ re-moved from the trailer. The drawing shows all critical dimen-sions and'weight's (cask and: axle loading).

4.3 Drawing M~ -A-1104 shows the removable baskets for various type fuels (PWR-BWR). The baskets are installed such that the on the basket straddle the two locking tabs near the strong'ack'ribs mouth of the cask cavity. Alternate liner arrangements may be used for radwaste or sample specimens. R2 4.4 The vent, gasket check (pressure test), and pressure relief valve ports located near the top of the cask (cask vertical) are identified as "V", "GC", and "R", respectively by cask markings. One of two drain ports (marked "D") located near the bottom of the cask is permanently plugged (no valve) and is not normally used.

4.5 It is generally helpful if crane locations are noted or id-entification points established to assist in subsequent pickS and movements.

f ]HinfOIINATIW)IItIL'f This document is not controlled. Befon. use, verify information with a controlled document.

ge 2 of 10 MAINTENANCE PROCEDURE NO- M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK

,r 5.0 PRECAUTIONS AND LDfETATIONS:

5.1 The cask cavity pressure may be as high as 160 psig.

• 5.2 The neutron shield tank (outer tank on cask) may be as thermally hot as 320 F and pressurized as high as 100 psig.*

5.3 The cask may not be immersed in 70 F water when the cask surface temperature exceeds 170 F (100oF max. temperature difference) to prevent thermally shocking the cask structure.

• 5.4 Insure that drain plug from cask wash down to the Waste Manage-ment System is open and plug to the storm drain shut.

5.5 The cask surface may not be cleaned with steel wool or any other abrasive material. The dull appearance of the cask sur-face must be maintained. No polishing of the cask exterior is permitted.

5.6 The cask trailer is light in weight and fragile. Extreme care must be taken when loading or unloading the cask to prevent damage to the trailer.

5.7 The cask exterior is constructed of 1/4 inch and 3/16 inch stainless sheet metal and care must oe exercised wnen handling to prevent denting the cask.

5.8 The cask trailer with

~

the cask shall only be moved by a tractor "

having a side oscillating (front to back and left to right pivot) fifth wheel.

5.9 Exercise care in loading the cask to prevent scratching the /R2 flange 0-ring seating surface.

• These high limits would be found only with a fueled cask loaded to it' maximum heat capaci,ty (11.5 KW) which has been sitting in still air (130 F) and direct sun for an extended period of time. The cask will likely be at or near room temperature conditions for many shipments; however, caution should be exercised to assure that this potential hazard is not overlooked under frequent association with low tempera-tures and pressure operations.

e 3of MAINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING 6 LOADING OF THE NFS-4 CASK

6. 0 INITIAL CONDITIONS:

6.1 Appropriate Health Physics'afety measure shall have been pre-pared and implemented.

6.2 The Spent Fuel Cask Crane and Operator are available.

7.1 To assure that all critical functions are performed, the Appendix A is to be filled in for each shipment of the cask.

The checkoff sheets and biU.s of lading shall be kept on permanent file.

8.0 E UIPMENT CHECK LIST.'.1 NFS - Furnished Items 8.1.1 NFS-4 Lifting Yoke (Dvg. No. E-10099) 8.1.2 NFS-4 Lid Spider and Four 1 In. Dia. x 1-1/2 In. Lg. Bo;--.

8.1.3 (SST) (Dwg. No. E-10101) 8.l 4 Female quick oisconnects (Snap tites) for connection to c~c (1/2" female NPT connection)

..,:: Gasket -Check. Equi pr;ent (Dwg. No.:1C-'T-1087) s.l.5 NFS-4 Cask (Dvg..No. 1A-A-1104) 8.l.6 NFS-'4 Cask and T'raiTer(Dwg. No. 1A-A-1102) 8.1.7 NFS-4 Valve Opening Tool and Valve Cover Spanner Wrench 81.8 NFS-4 Cask License and Referenced Documentation 8-1.9 Removable Impact Limiter - Special A'lien Mrench 8-2 Uti lity-Furnished Items 8.2.1 Cask Unloading Crane (Min. 25 Tons) Compatible with 8.2.2 Supplied Cask Yoke (A-1) 8.2.3 Auxiliary Crane (Min. 1/2 Ton - Optional) for Cask Ljd 8.2.4 Lid Lifting Tool or Hook Compatible with Lid Spider (A-2)

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'MAINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK 8.0

~ E UIPMENT.~ CHECK LIST: (Cont)

Utility-Furnished Items (Cont) 8.2.4 Service Bridge Cask Inspection and Oecon Scaffold l

8.2.6 Decon Equipment, Solutions, Mater, Protective Clothing, Etc.

8.6.7 Tools 8.2.7.1 Torque Mrench, 1000 ft lbs-, with 2 in G point socket

. (or equivalent with multiplyir g wrench) Maximum socket

0. D. = 3 inches.

8.2-7-2 Torque Mrench, 100 ft lbs, with 1/2 in; drive 8 2 7 3 Ratchet and Breaker Bar wi th 1/2 in. dri ve 8.2.7.4 Mire Cutter, Screwdriver I

(medium) 1 Lock Mlr n a Gal T g

.. 8.2.9 .Plywood (approx, 1/2". x 4' 4') or equivalent for cask sitdown

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8.2.l0 Health and Safety quipment including Neutron and Gamma Survey Instrumentation

'I 8.2.11 Yent and Drain Hoses for use with Snap tites for connection to cask.

Page 5 of MAINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK F

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9 ~p Loadi n Procedure 9.1

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Receive. the cask and trailer at

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handling. area and perform radiation.

survey. Note time of cask arrival on site on bill of lading.

9.2 Release front (upper) cask tie-downs and rear (bottom) tie-downs (over center lever clamp).

9.3 Unbolt lid impact limiter from cask (four in. socket head bolts) 1 and roll it forward on the sling carriage built into the trailer.

9.4. Using an overhead crane (min 25 tons), attach the lifting yoke to upper trunnions on cask.* The yoke movable lift arm must then be locked in place using the attached Ball-loc pin.

9.5 Rotate cask to the. vertical position on the trailer while keeping crane cables vertical at.all times.

9.6 Remove cask from traile~, trove trailer from handling area (if required) .

C A

9.7 Inspect cask for damage. Rinse road dirt off exterior and remove tape covering ports as necessary. Cask should be set on, and attached to, clean plywood (or equivalent) to prevent embedding of foreign material (radioactive) into the cask surface.

9 8 Attach lid lifting spider to cask lid using four 1 in. bolts (finger tight) .

9.9 Remove port covers (5) using special spanner tool supplied. Do not use hammer or equivalent due to thin (.005) blow out section T

on pressure relief valve port cover.

~The

~ orientation of the overhead crane hook's throat relative to the yoke's lay down ear may be significant under certain. plant layouts.

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e6 of 10 MAINTENANCE PROCEDURE NO, M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK 9.0 LOADING PROCEDURE: (Cont) 9.10 Attach vent and drain lines to the quick disconnects on the lines to the vent and drain valves* (Ref. Dwg. No. 1A-A-1104). Open both the vent ard drain valves. This will allow the cask to drain' as it is removed from the fuel storage pool.

9.11 Remove cask lid bolts (six 1-1/4 in. dia. hex head). Remove cask Tid (optional**). Visually inspect 0-rings for damage and replace if required. Vacuum grease may be used to hold the gaskets in plac if necessary. The 0-rings are normally replaced periodically .by Re cask owner.: Depending upon the length of the radwaste being shipped, a spacer may be bolted to the bottom surface o the lid.

9.12 Lower cask to bottom of pool. Allow"yoke to rotate horizontally until its ear rests on the cask and remove crane hook (if necessary).

9 13 Veri fy liner cover attachment (i f required) and load samples into

/R2

.. cask .. Use caution;to prevent touching orscratching flange:(gasket) surface. Assure assembly or basket identification is established as may be necessary for accountability. purposes.

9.14 Place lid on cask, aligning A mark on lid with v mark on the cask.

9.15 Raise cask to surface of pool and monitor for neutron and gamma radiation. Such radiation shall neither exceed 10 mr/hr total at eight (8) feet from cask (equivalent to 6 feet from the surface of the transport vehicle) per DOT regulations nor have 27 times the neutron dose rate plus 1.4 times the gamma dose rate greater than I'

The quick disconnects are valved type and'the cask cannot be vented or drained without the female disconnect attached to open the valve in the male disconnect. ~

~ Depending upon reactor layout and equipment,

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it

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may be more desirable to

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remove the lid after, the cask is lowered to the bottom of the pool.

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e 7 of 10 MAINTENANCE PROCEDURE NO. M0913REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK

9. 0 LOADING PROCEDURE: (Cont) 1,000 mr/hr at three feet from the surface of the cask per.

.license requirements. (This is to assure acceptable radiation levels if shield tank liquid is lost under accident conditions).

9.16 .Install 'a'minieum of one'r two 1-1/'4 in. hex 1'id 'bolts finger tight (Caution: Bolts to be lubricated with NOLY-KOTE only).

9.17 Raise cask over pool while rinsing with clean water. Allow cask

/Rz to drain completely.

9.18 Close both the vent and drain valves; remove quick discornect lines. Move cask to decon area. -/R2 9 .19 Install remaining lid bolts (6 total) and torque tu 600 ft lbs using a 1,4,2,5,3,6, pattern; then, with the same sequence, torque Q -'9.20 all bolts to 1,000 ft lbs.

Pressurise- annU1us::be>een. doub'le.0-ring seal's to 80. to--100 psig;- =. -'=.

isolate, hold for 10 minutes, and check for zero pressure leakdown with supplied pressure test equipment. Note: There may be a small pressure transient while temperature equalizes. If leakage is noted, repeat test with the test valve closed to verify that leakage is not in the test assembly or quick disconnects. Close 0-ring test valve.

Replace 0-ring(s) if leakage is found and repeat the test. Spare 0-rings are in cask tool box.

9 .21 Pressurize cask cavity with pressure (gasket test equipment) to between 80 and 120 psig through the vent line. Monitor the pres-sure for 10 minutes, minimum, while visually inspecting the- pres-sure relief, drain and vent fittings (4 ports) for leakage. To check the valves for leakage a female Snap-Tite must be installed

e Sof 10

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MAINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK

9. 0 LOADING PROCEDURE: (Cont) on the male Snap-Tite connection to open the fitting's check valve. If any leakage is noted, repair per NFS procedures and repeat the .test.

9.22 Pull the reli.ef valve override ring and note no pressure relief (audible). Vent off the cavity pressure. Close the'ent valve l

and repeat the pressure test to assure tightness of the vent valve.

If any leakage is noted, repair per NFS procedures and repeat test.

9 .23 Remove lid lifting spider.

9.24 Decon all exposed cask surfaces using high'pressure water and wash with sponges and an approved decon solution is required. DO NOT scrub cask with any abrasives. Rinse and wipe exposed cask surfaces dry; 9 .25 Lock wire and 1 ead seal tag two bolts. /R2 9.26 Replace valve port covers finger tight and lock wire in place.

9.27 Check cask surface for contamination and visually check surfaces for neutron shield tank leakage. It is recomnended that the burst disc openings be taped to keep out wood dirt during transit.

9 .28 Load cask onto trailer by carefully placin'g lower trunnions into tie-down at aft end of the trailer. Lower cask to horizontal position while, keeping crane cables vertical. Disengage Ball-loc pin from yoke arm and remove yoke from the cas'k. Latch fore (2) and aft (2) trunnion tie-downs.

9 ~ 29 Attach lid impact limiter to cask (torque four 1 in. bolts to 50 to 70 lbs.).

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~ge 9 of 10.

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'AINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE FOR HANDLING & LOADING OF THE NFS-4 CASK 9.0 LOADING PROCEDURE: (Cont) 9.30 Close and latch trailer doors (4), turn EflPTY signs (2) to

'pposite side and attach proper placard: Rotate DRIVE SAFELY signs (4) to RADIOACTIVE. Remove EtlPTY label from impact limiter.

9 ~ 31 Perform radi atjon survey (gamma and neutron) .

9.32 Obtain Heal th Physics release. /R2 9.33 If tractor has been removed from trailer, inspect fifth wheel to assure latch level is in fully opened position. During con-nection inspect to assure that the latch lever swings to a closed position behind lock. Verify connection of brak'e and electrical lines and "tug" with trailer brakes applied.

9 34 Operator and Health & Safety Technician to complete checkoff sheet and have Shift Supervisor sign off and keep on permanent

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L- ~

file at the reactor station.

9,35 Bill of lading for..the cask and fuel are to be signed and two {2)

I 'w '

copies given to the truck driver after completing:

9.35,1.Cask ID number (NFS-4A, -4B, etc.)

9.35.2 Shipment description. , /R2 9.35.3 Time of arrival at site 9.35.4 Time of departure from site.

9.35.5 Time cask is ready for departure if different from "d".

One copy is retained for site records. /R2 9.36 Remove cask and trailer from handling area.

9.37 Notify Chem-Nuclear Transportation Supervisor (803-259-3588) at time of departure. Also notify of any problems in handling the cask or the use of any spare parts from the tool box.

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e 10 of 10 sl

'AINTENANCE PROCEDURE NO. M0913, REV. 2 GENERAL OPERATING PROCEDURE 'FOR HANDLING & LOADING OF THE NFS-4 CASK APPENDIX A USER CHECKOFF SHEET USER C11ECKOFF SllEET Date Haste Identification Shipment Number Operator(s),

H 8 S Technician(s) Est. Heat Rate KM 2.5 K!1 i/)ay..)

Time of Arrival at Plant Time of Loading of Fuel Snipper Time of Departure from Area Driver . Time of Departure from Gat=

Item (please initial)

~

Item ~

Op.

~ Supvr.

Storm Drain Closed &

Waste Drain Open Op. Supvr . 'R2 Cavity Drained a

Drain,'ent'I)l Test Valves'losed Lid Bolts Torqued (1,000 ft lbs) Bolts 8 Port Covers Lock Mired Lid Leak Checked Cask Released.

mr/hr mr/hr (at 6 feet from trailer)

Y = mr/nr mr/hr (at 3 feet from cask) l Smearable (DPN <</100 Cm2) = Smearable (DPN g/100 Cm2) =

op. Supv.

Waste drain closed

& storm drain open Lid Impact Limiter Bolted to Cask, Cask Secured on Trailer, Trailer Doors Closed, EJ1PTY Sign Turned, Placard Attached, Bill of Lading Given to Driver Latching of Tractor to Trailer Verified

APERTURE CARD REQUEST

~o. g 0//0 0 y7 Mother Ano. 7 8 O'0 48x 24x Job Flow Avail.

4 Oversize Date Sent To Be Filmed 4 l~ SC B7 L J8 Date Filmed

f'I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: REID R IJ ORG: UHRIG R E DOCDATE: 10/02/78 NRC FL PWR 5 LIGHT DATE RCVD: 10/06/78 <

DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 3 ENCL 0 FURNISHI'NG NOTIFICATION GF CERTAIN ACTIVITIES WHICII APPLICANT HAS UNDER REVIEW WlTH RE TO THE STEAM GENERATORS AT UNIT 1 TO A SURE SATISFACTORY OPERATION AND AVOID POTENTIAL FUTURE PROBLEMS.

PLANl NAME: Sl LUCIE $ 1

~~>>4~>>4~>>~:.~-3H~>H~4:>~I<>> DISTRIBUTION GF THIS MATERIAL IS AS FOLLOWS REVIEWER DISTRIBUTOR INITIAL:~

INITIAL: X JM

.GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRlBUTlON CODE A001)

FOR ACTION: BR CI-IIEF ORSee BC~>>LTR ONLY<7)

INTERNAL: NRC PDR<>>LTR ONLY< 1) a C~~LTR ONLY(a) GELD%>>LTR ONLY(i)

IRANAUEIR~~>>LTR ONLY( 1) CORE PERFORMANCE BR<4LTR ONLY>>>LTR ONLY(i) ENGINEERING BR>>+LTR ONLY (1 )

REACTOR SAFETY BR>>4LTR ONLY(1) PLANT SYSTEMS BR%+LTR ONLY(i)

EEB~:>>LTR ONLY(i) EFFLUENT TREAT SYS>+LTR ONLY(i)

J MCGOUGIS+.>>I TR ONLY< 1)

EXTERNAL' LPDR'S FT PIERCEi FL>>@LTR ONLY(1)

TERA>>>>LTR ONLY< 1)

NSIC4->>LTR ONLY(1)

ACRS CAT B >+LTIR ONI Y ( 16)

DISTRIBUTION: I TR nO ENCL 0 CONTROL NBR: 7807 0328 IZE: gr

>>~~>>~H~>>~p-w>>~~:>>~>>>>>>>>>>~H~~>>>>~~>>~~~'>>>>>>>>~~>> THE -ND 4.%%%>>>>%%%4>>%4 %%%%>>%%%%%%%%%%%%%%%

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~ r O. BOX 013100, MIAMI, FL 33101 m~

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Pire ve"v FLORIDA POWER 8( LIGHT COMPANY October 2, 1978 L-78-318 Office of Nuclear Reactor Regulation C) CQ P%

Attn: ter. Robert W. Rei d, Chief tIa

~ffl Operating Reactors Branch No. 4 L3 Division of Operating Reactors (CD U. S. Nuclear Regulatory Commission

~

Q C7CD PlC Washington, D. C. 20555 CO~

n C MCtS rCS

Dear Mr. Reid:

~ i>>

R~iirvtI p.0<'lv'~ UIt graf 5CD, m

Cll Re: St. Locie Uni ko. Steam Generators The purpose of this letter is to advise you of certain. activities which FPL presently has under review with regard to the steam generators at St. Lucie Unit No. 1 ~ At present, no problems have been noted in the operation of'he steam generators. One generator was inspected during the April 1978 refueling outage, and a summary of the results has been

'submitted to the NRC. Those results indicate a high degree of clean-liness, relatively insignificant denting in a small number of tubes, and no wastage or thinning requiring tube plugging. Despite the favorable experience this far, FPL has elected to pursue the following activities to further assure satisfactory operation and avoid potential future problems.

FPL's primary emphasis is being placed upon the development of a program leading to chemical cleaning of the steam generators at St. Lucie I during the Cycle 3 refueling outage expected to begin in April 1979.

This program is being developed in cooperation with Combustion - Engineer-

,ing, Inc. (C-E), the NSSS supplier, and consists of the following major steps:

l. gualification and selection of solvent vendor

2. Conduct of pot boiler and model boiler testing

3. Conduct of vibration characteristics analysis and testing

4. Development of process engineering v

5. Identification and satisfaction of licensing requirements The determination of whether chemical cleaning can proceed as planned is dependent upon the outcome of, each step and its effect on the overall schedule. FPL has already conducted one meeting with your staff and fully intends to continue to'keep the NRC informed of the status of the program through periodic updates. At present, we expect to be able to meet with members of the NRC staff after mid-October following completion of the solvent vendor selection phase, and will contact your staff to arrange a mutually agreeable date and time.

7807503Z8 PEOPLE... VING PEOPLE

.- Mr. Robert M. Reid, Chief Operating Reactors Branch No. 4 Oivision of Operating Reactors October 2, 1978 Page 2 It is our understanding that the condition of the upper partial drilled support plates at the time of cleaning is one of the factors to be considered in our determination of whether the cleaning can proceed pursuant to the provisions of 10 CFR 50.59. To provide information necessary to that determination, FPL plans to undertake a brief outage during early November to conduct an inspection of the steam generators.

Should that inspection indicate that it may be prudent to cut the upper partial drilled support plates free from the shroud in each steam gen-erator prior to cleaning, a decision to do so might be made at that time.

This modification would be similar to that performed on the C-E steam generators at Millstone 2, Maine Yankee, and Arkansas Nuclear One Unit 2, and FPL would perform it pursuant to the provisions of 10 CFR 50.59.

l<e will advise your staff of our determinations as soon as they become available.

Yours very truly, Robert E. Uhrig Vice President Advanced Systems 5 Technology REU:MAS:cf cc: Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire

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