L-87-104, Forwards Addl Info Re 860702 Application for Amend to License NPF-16,establishing Option of Storing Spent Fuel from Unit 1 in Unit 2 Spent Fuel Pool,In Response to 870123 request.W/12 Oversize Drawings
| ML17219A393 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/02/1987 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17219A394 | List:
|
| References | |
| L-87-104, NUDOCS 8703060021 | |
| Download: ML17219A393 (29) | |
Text
REQULATORY FORMATION DISTRIBUTION SY
<<N (RIDS)
ACCESSION NBR:870308)002}
DOC. DATE: 87/03/02 NOTARIZED:
NO FACIL:50-335 St.
Lucie Plant>
Unit 1> Florida Power 8c Light Co.
50-389 St.
Luci e Plant>
Unit 2>.Florida Power Zc Light Co.
AUTH. NANE AUTHOR AFFILIATION NOODY> C. 0 Florida Power Sr Light Co.
RECIP. NANE RECIPIENT AFFILIATION Document'ontrol Branch (Document Control Desk)
DOCKET 0 05000335 05000389 i8~ l~
SUBJECT:
Forwards addi info re 860702 appl ication For amend Licnese NPF 16 to establish option of storing spent Fuel from Unit 1
in Unit 2 spent fuel pool> in responnse to 870123 request. N/
12 oversize encl.~iWGS DISTRIBUTION CODE:
AOO}D COPIES RECEIVED'TR ENCL SIZE:
TITLE:
OR,, Submittal:
Qeneral Distribution NOTES:
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P. o. B 000, JUNO BEACH, FL 33408.0420 lp'Ul g'4g IIIlARCH OP ]987 L-87-I04 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re:
St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 S ent Fuel Transfer By letter L-86-250, dated July 2, l986, Florida Power & Light Company (FPL) proposed to amend the St. Lucie Unit 2 operating license NPF-16 to establish the option of storing spent fuel from St. Lucie Unit I in the St. Lucie Unit 2 spent fuel pool.
The Unit I spent fuel pool will lose full core reserve capacity as a result of the l987 refueling outage, and the planned Unit I spent fuel pool rerack cannot be accomplished prior to l988.
If, in the interim, full core off-load of Unit I should be necessary~,Unit I spent fuel could be stored in the Unit 2 spent fuel pool.
By letter dated January 23, l987 (E. G. Tourigny to C. O. Woody) the NRC Staff requested additional information required to continue their review of this proposed license amendment.
Attached is FPL's response to this request.
If additional information is required on this topic, please contact us.
Very truly yours, Nuclear Energy COW/EJW/gp Attachments cc:
Dr. J. Nelson Grace, Region II, USNRC USNRC Resident Inspector, St. Lucie Plant 87030bOOZ1 870302 PDR ADQCK 050003//
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ATTACHMENT REQUEST FOR ADDITIONALINFORMATION PROPOSED LICENSE AMENDMENT SPENT FUEL TRANSFER ST. LUCIE UNIT2 The following requests pertain to Florida Power & Light Company's submittal to the NRC Staff dated July 2, l 986.
The Licensee is asked to respond to the following items regarding details of spent fuel transfer from St. Lucie Unit I to St. Lucie Unit 2 as described in their "Safety Evaluation/No Significant Hazards Consideration" report.
Item No. I:
Section 2.4 of the Licensee's submit'tal states that "Two transporter Vehicles were considered in the load path evaluation.
The maximum wheel loads for each of these transporters were found to be acceptable considering the effects on all surfaces including the roadway, missile protection slab, and underground facilities (i.e., pipes, electric conduit,
- manholes, and catch basins)."
Please provide the following structural details and data which support the above statement:
a.
Structure data of the spent fuel shipping cask which will be used to transfer spent fuel assemblies from Unit I to Unit 2 spent fuel pool (configuration and basic dimensions, total
- weight, shipping position..etc.).
b.
Wheel arrangements, maximum recommended wheel loads and dead weight of the two transporter vehicles.
c.
Structural details and plan layouts of missile protection slab and underground facilities to be crossed by the transporter vehicles along the shipping load path.
d.
Results of stress analysis calculations indicating that every structural component listed in item c above shall withstand prescribed sustained and live loads with acceptable margin of safety.
~Res onse a.
As discussed in the responses to questions 2 and 4 in FPL letter L-87-48, dated February 9, l 987, the spent fuel shipping cask that would be used, if required, would be either the Model NAC-I or NLI-I/2.
These shipping casks have Certificates of Compliance No. 9I83, Rev. 3, dated November l4,
- l984, and" No. 90IO, Rev.
I7 dated August 28,
- l986, respectively, issued by the NRC. Further design details of these spent fuel shipping casks are included in Appendices A and B.
EJW4/008/2 b.
Wheel arrangements, maximum recommended wheel loads and dead weights of the two transporter vehicles are shown on Figure I.
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c.
Category I underground facilities that are in the path to be crossed by the spent fuel transporter vehicles are shown on Table I.
The Table lists the plan layout and structural detail drawings on which the underground facilities can be found (e.g.,
Manhole 127 (MH 127) is shown in plan on drawing 8770-G-408 Sheet I Revision 13 at coordinate J14).
Structural details are shown on drawing 8770-G-627 Revision 5 at coordinates E9 and J9 and drawing 8770-G-628 Sheet I Revision 2, in the "Notes".
Table 2 lists the attached plan layouts and structural detail drawings attached.
d.
Table I provides a summary of stress analysis results indicating that every Category I structural component discussed in Item Ic. above has the capability to withstand prescribed sustained and live load with an acceptable margin of safety (e.g., Manhole 127 (MH 127) was designed on the basis of ultimate strength design (USD) for an "original design live load" of 26.4 and yielded a margin of safety of 1.8kthe spent fuel transporter vehicles produce corresponding loads of 7.33 (RV) and 8.0 (0)).
The "margin of safety" shown in Table I is based upon the "original design live load".
By comparing the original design live loads with the spent fuel transporter vehicle wheel loads shown in Table I, it can be seen that the spent fuel transporter vehicle wheel loads are no more than half of the original design live loads.
Accordingly, the margins of, safety for the spent fuel transporter vehicles are considerably higher than the margin of safety shown in Table I.
Item No. 2:
Please provide detailed description of how a spent fuel assembly of Unit I
will be transferred safely from the shipping cask mounted on the transport vehicle to the designated spent fuel rack of Unit 2.
~Res ense The shipping cask will be moved into position under the Unit 2 cask crane after following the predetermined spent fuel transfer path from Unit I. The Unit 2 cask crane is moved into position and picks up the cask lifting yoke.
The trailer down-riggers are then lowered, wheel chocks are installed, the tractor is disconnected and driven to its parking place.
The bolts which retain the forward trunion mounts are removed and stored.
The cask lifting yoke is positioned over the upper lifting trunions and manually engaged to the lifting lugs.
The cask is lifted to the vertical position and then lifted clear of the transport trailer.
The cask is placed in the Unit 2 cask wash area" where it is prepared for movement into the Unit 2 spent fuel storage pool.
The inner head closure bolts are detensioned and the cask is lifted into position over the center of the pool cask area.
Demineralized water is sprayed on the cask as it is lowered into the pool through the wash down ring.
When the top of the cask is at a covenient height above the pool water level, the demineralized spray is stopped, the inner closure head bolts are removed and placed in storage, and the demineralized water is again started as the cask is continued to be lowered to the bottom of the cask loading area floor.
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For the NAC-I, the cask crane hook is detached from the cask crane lifting yoke bale.
The hook is washed down with demineralized water as it is retracted out of the pool.
For the NLI-I/2, the cask lifting yoke arms are disconnected from the cask using the arm-mounted hydraulic actuating system.
The inner cask cover is removed as the yoke is lifted out of the pool.
A spray of demineralized water is again used to wash down the cable system, the crane hook, the liftingyoke and the inner cask cover.
After a period of drip drying, the trolly is backed out of the pool a sufficent distance to allow free access to the cask top by the Spent Fuel Bridge Crane (SFBC).
For the NAC-I, the SFBC is positioned over the cask and the inner cask cover lifting point is engaged.
The cover is then removed and placed in a designated temporary storage location for replacement after the fuel assembly has been removed from the cask.
The inner cover lifting tool is then placed in its designated temporary storage location.
For both the NAC-I and the NLI-I/2, the SFBC then moves into position over the cask opening to latch onto the fuel assembly.
Once latched, the fuel assembly is picked up by the SFBC, moved through the Unit 2 cask keyway door and taken to a predetermined pool storage location where it is lowered into place.
The SFBC unlatches from the fuel assembly and returns to its designated storage/parking position.
Item No. 3:
P lease provide the basic mechanical design parameters of the fuel assemblies manufactured by Exxon Nuclear Company (ENC) since Unit I is scheduled to operate with ENC fuel only (Cycle No. 8).
~Res onse The basic mechanical design parameters of ENC SFAs are described in ENC Topical Report XN-NF-82-09, which was submitted to the NRC in November l982. This Topical Report was approved by the staff in August l 983.
As discussed in the response to question I in FPL's letter L-87-48, dated February 9, 1987, FPL would initially plan to move only the fuel which has had the longest decay time.
As a result, Batch A assemblies, which were removed from the Unit I reactor at the end of Cycle I, would be moved, first.
These assemblies have almost nine years of decay time and are spent fuel assemblies (SFAs) of the Combustion Engineering (CE) design.
The basic mechanical design parameters of these CE-design SFAs are also discussed in the response to question I of L-87-48.
EJW4/008/4
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83-1. SOU U TABLE 1 UNDERGROUND FACILITIES CROSSED BY SPENT FUEL TRANSPORT VEHICLE ITEM IN PATH Missile Protection S
-. b over Pipe Tunnel PLAN DRAWING(3) 8770-G-671 DWG REV DRAWING STRUCTURAL DWG COORDINATE DRAWING(3)
G5 fo I5 8770M-671 8770M-672 8770&-673 Gs to I5 Nl
- G15, H15 USD 1 ~ 8 MARGIN DRAWING TYPE OF OP QQRIGHBJ3 ~XQS SPENT FUEL ORIGINAL TRANSPORTER DESIGN VEHICLE LIVE WHEEL LOAD W>~ 35 20 15k 7 33k 8 Ok 30"$CW-90 30"(CW-91 MH126 8770M-170shl 9
8770&-170shl 9
8770"G-408shl 13 Missile Protection 8770-G-671 Slab over Pipe Tunnel J17 l
8770M-628 Sh 1 2
G9 to I9 8770-G-671 8770~672 8770-G-673 Fll to F14 N/A Pll to Fl4 N/A G9 to S9 N3 & N5 Hll E9& J9 Notes USD 1.8 USD Deflection 1.77 Deflection 1.77 26 3k 7 33k S2.2Sk 22" 52.25 22 bk 7 33K 8.Ok 16k lb" 8.UK MH127 8770&-408snl 13 J14 8770-G-627 5
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& J9 8770M-628 Sh 1 2
Notes USD 1.8 4k 7 ~ 33K e.ok MH129 MH130 MH136 MH137 8770-G-408shl 13 J13 8770-G-388 24 L8 8770&-388 24 L4 8770&-408shl 13 Ilo 8770&-40eshl 13 H7 8770-G-627 5
8770&-628 Sh i 2
8770&-627 5
8770-G-b28 Sh 1 2
8770-G-627 5
8770M-628 Sh 1
2 8770-G-627 5
8770&-628 Sh 1 2
8770-G-627 5
8770&-628 Sh 1 2
D9
& I9 Notes E9 &19 Notes F9& J9 Notes D9
& I9 Notes D9
& 19 Notes USD USD USD USD USD 1.8 1.8 1.8 1.8 1.8 2b.4 7.33 26 'K 7 33k 26 ~4k 7 33 64k 733k 26.4k e.ok e.uk e.ok 8.Ok 8.Ok MH299X MH299Y 2998-G"057801 1
H3 2998-G-057Sol I
H3 2998-G"628 Sh 7
0 2998&-627 7
2998&-628 Sh 7
0 2998M-627 7
Elo Notes Elo Notes USD USD
- 1. 47(2) 26 7.33k 2b 7 33K B.Ok 8 Ok TABl E i (Continued)
I REPORT NU.
83-L.>OUU ITEN IN PATH HH299Z PLAN DRAWING(3)
DWG DRAWING STRUCTURAL ISK gglUIIJlhTI'RIH9 2998~057S01 1
H3 2998~28 Sh 7
2998M"627 MARGIN DWG DRAWING TYPE OF OF RE/
NQRDIHAXE MHALXgg $hEKU~
0 E10 USD 7
Notes 26k 7 33k 8 0 SPENT FUEL ORIGINAL TRANSPORTER DESIGN VEHICLE LIVE WHEEL LOAD Manhole Covers Various Electrical Conduit 877':-388S13 24 8770~408shl 13 n/a n/a WSD WSD 2.0 1 31 26k' 33 S2.uk 22k 8.0k 16k Missile Protection 877~408shl 13 over Electrical Conduit 877~07 Sh 1 14 A thru D13 USD 1.0 44k 7 33k 8.0" NOTES:
(1)
(2)
Hargin of safety (MS) for deflection is based on allowable deflection of 2 X of dianeterg actual deflection is 1.13 X
of dianeter; HS 2.0/1.13 1.77 Hargin of safety (MS) is based on a required area of steel of.81 sq. in and a provided area of steel of 1.19 sq. in.
HS 1.19/ 81 ~ 1 47 (3)
ABBREVIATIONS See Attachaent 4 for drawings.
USD Ultiaate strength design MH Manhole CW Circulating 6 Intake Cooling water systea WSD
'Working stress design R
Revision RV Spent Fuel Cask Transporter Rogers vehicle shown on Figure 1 0
Spent Fuel Cask Transporter shown on Figure 1
DEFINlTIONS FOR TERMS lN TABLE I Type of Analysis-This denotes the method of analysis used to determine a design that is acceptable.
Margin of safety-This defines the ratio between the original design requirements and original design allowables of the item. lt is based on the "original design live load".
Original Design Live Load-This is the live load that was applied at the road surface and used to design structures in the load path.
Transporter vehicle wheel load-This shows the wheel load from the vehicles that will transport the fuel between units.
The wheel loads are presented in a manner equivalent to those presented for "original design live load".
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~D 8770-G-I 70 Sh I
8770-G-388 8770-G-407 Sh I
8770-G-408 Sh I
8770-G-627 8770-G-628 Sh I
8770-G-67I 8770-G-672 8770-G-673 2998-G-057 SOI 2998-G-627 2998-G-628 Sh 7 Rev. No.
24 l4 l3 Title Yard Piping Sh No. IA Diesel Generator Building-Conduit, Grounding &Lighting Yard Duct Runs Yard Duct Runs and Lighting Plan, Sections and Details - Sh I
Electrical Manhole Details-M&R Sh I
Electrical Manhole Details-M&R Sh 2 Component Cooling Purnps-Foundations Masonry Component Cooling Pumps-Mas & Reinf Sh I
Component Cooling Pumps-Mas & Reinf Sh 2 Yard Composite Sh I
Elec. Manhole Details - M&R Elec. Manhole Details - M&R NOTE: 8770- denotes St. Lucie fk I drawings and 2998-St. Lucie /$2.
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APPENDIX A NUCLEAR ASSURANCE CORPORATION INFORMATION ON NAC-I SPENT FUEL SHIPP)NG CASK CERTIFICATE OF COMPLIANCE. No. 9I83, REV. 3 EJW4/008/5
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NAC-1 SHIPPING CASK DATA (t
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'ask weight, loaded, lbs.
Gross vehicle weight, lbs.
Overall cask length, inches.
Minimum loading height, inches Clearance above highest fixed object, inches Cask diameter, inches Internal cavity length, inches Internal cavity diameter, inches Shield thickness, inches lead water 50,000 73,280 214 200 258 50 178
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Irradiated Fuel Clad,'rradiated metallic natural uranium fuel rods.
21 rods or 10 encapsulated (defective) rods 1600 MWD/MTO average burn-up cooled for at least 730 days after irradiation 2.
Solid Non-fissile Irradiated Hardware.
3.
Maximum Allowable Deca Heat:
625 watts.
4.
Maximum Allowable Contained Wei ht, including baskets, canisters and or spacers:
3,700 pounds.
NY VA'LVE VENTVN.UE COVER CAVITYELASYD-MERSEALS(2}
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NAC-I CASK CONFIGURATION
APPENDIX 8 NUCLEAR ASSURANCE CORPORATION INFORMATION ON NLI-I/2 SPENT FUEL SHIPPING CASK CERTIFICATE OF COMPLIANCE No. 90I0, REV. I7 EJW4/008/6
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NL-1/2 SHIPPING CASK DATA 4
(I Cask weight, loaded, lbs.
Gross vehicle weight, lbs.
Overall cask length, (max) inches Minimum loading height, inches Clearance above highest fixed
- object, inches Cask diameter, inches Internal cavity length, inches Internal cavity diameter, inches Sliield thickness, inches lead 50,000
< 73,280 198 193 258 48
'7 13.375 2.125 depleted uranium water 2.75 5.0 Cask Descri tion The NL-1/2 shipping cask is designed and licensed to transport one PWR fuel
- assembly, two BMR fuel asselnblies, or irradiated nuclear components such as con-trol and poison rods.
In conjunction with its special trailer, it is a Legal Weight Truck cask capable of unrestricted travel.
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Contents - T e and Limits 1.
Fuel Assemblies
kg.
PWR 8.75 x 8.75 x 144 3.7 475 BWR 5.75 x 5.75 x 144 2.65 197 2.
B roduct and s ecial nuclear materials in the form of irradiated uranium ox>
e fue rods.
Maximum Enrichment w o U23 3.7 Maximum Fissile Mass Limit g e 3
+ p utonlum 4.0 3.
Radiation Source Terms Total-Gamma Energy Total neutron flux 3.074 x 10 Mev/sec 7.55 x 10
. n/sec Maximum allowable deca
- heat, kw
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