ML20195D425
| ML20195D425 | |
| Person / Time | |
|---|---|
| Site: | 07109206, 07109202 |
| Issue date: | 05/25/1999 |
| From: | Mazurowski B ENERGY, DEPT. OF |
| To: | Reid D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20195D432 | List: |
| References | |
| TAC-L22645, NUDOCS 9906090164 | |
| Download: ML20195D425 (4) | |
Text
t1.m a r[l - 9202.
7 / - 9 2.O lo i
T op
\\
4 Department of Energy i
Ohio Field Office i
C 1
West Valley Demonstration Project
\\
P.O. Box 191.
West Valley, NY.14171
'%nis 6 May 25, 1999 i
Mr. Dennis G. Reid i
Oflice ofNuclear Material Safety and Safeguards United States Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 06F18 Rockville, MD 20852
SUBJECT:
Minutes from February 4,1999, Meeting on Shipment of Damaged Fuel and Fuel Load Feasibility Study (TAC. No. L22645) 1
Dear Mr. Reid:
)
The enclosed meeting minutes document the Department of Energy's summary of our February 4,1999, meeting on shipment of damaged fuel. I have also enclosed a copy of a j
feasibility report prepared by Transnuclear Inc. regarding full load shipments. The feasibility i
report is useful in that it provides a comparison of material properties of the borated stainless ster 1 currently used in the Transnuclear Big Rock Point (TN-BRP) and Transnuclear Robert E.
Ginaa (TN-REG) casks with those specified by American Society of Testing Material (ASTM) l and Code Case 510.
Please contact Bryan C. Bower, of my staff, at (716) 942-4368 if you have questions regarding the meeting minutes or the feasibility study.
Sincerely, W
f Barbara A. Mazurowski, Director West Valley Demonstration Project
Enclosures:
- 1. Minutes from NRC Meeting on Shipment of Damaged Fuel in the TN-BRP and TN-REG Cask l
- 2. BRP/ REG Full Load Transportation Feasibility Study
- /
cc: C. M. Hansen, DOE-HQ, EM-67, 2057/CLOV, w/enct.
A. R. Griffith, DOE-HQ, EM-65, 2086/CLOV, w/encs.
BCB:067 - 64829 - 415.4
. g., i i ! l 4 BCB/bma 9906090164 990525 j
PDR C
F^
i e
l MINUTES FROM NRC MEETING ON SHIPMENT OF DAMAGE FUEL IN THE TN-BRP AND TN-REG CASKS February 4,1999 Attendees:
See attached list
Purpose:
To discuss with the Nuclear Regulatory Commission (NRC) that the use of"end caps" in the top and bottom of basket compartment in the TN BRP and TN-REG casks meets the requirements for canning damaged fuel as stated in the NRC Spent Fuel Project Office (SFPO) Interim Staff Guidance - 1 (ISG-1).
Summary:
After introductions, Andrew Griffith (DOE-HQ) gave a short explanation of the importance of the West Valley Fuel shipment.
Tony Suda (WVNS) opened the formal presentations with a description of the casks and the spent nuclear fuel (SNF). During the discussion of the casks, Marissa Bailey (NRC) asked what the leak rate of the casks was. William Bracey (TN) provided the answer. During the description of the Big Rock Point SNF, Ms. Bailey asked a question regarding the initial enrichment of the MOx Fuel. Tony Suda provided the answer.
Mr. Suda then discussed the WVDP video inspections and summarized the damaged fuel. Susan Shankman (NRC) asked if we had reactor records. Ms. Shankman stated that the reactor records are the primary source ofinformation to prove that the fuel is undamaged, and that video inspections are a secondary source ofinformation. After significant discussion, Bryan Bower (OH/WVDP) asked NRC if the Interim Staff Guidance for Damaged Fuel (ISG-1) should be interpreted to mean that " failed fuel" should be considered to be damaged (i.e., greater than hairline cracks or pinhole leaks) unless proven otherwise. The NRC agreed that this was their position. Mr. Suda concluded the discussion by showing a composite video of previously identified damaged assemblies.
Mr. Bower walked the NRC through the Department of Energy's (DOE) decision-making process that resulted in the preferred approach being presented to the NRC. Mr. Bracey concluded the formal presentation with a description of the implementation of the preferred approach.
l Ms. Bailey stated that the "end cap" concept appears to meet the intent of canning, however, DOE must demonstrate that the gross particulates are confined to a known subcritical geometry.
J
i Subsequent to the meeting, Mr. Bower contacted Dennis Reid (NR.C Project Manager) for clarification on several points not resolved during the meeting. Mr. Bower specifically asked if the "end caps", in conjunctior, with the borated stainless steel basket, met the intent of ISG-1.
Mr. Reid assembled a technical team to review this question, and on March 3,1999, informed
. Mr. Bower that, consistent with their previous position, the NRC would not permit credit for the
- borated stainless steel basket in the accident condition. Mr. Bower then discussed with Mr. Reid issues associated with replacing the borated stainless steel with 304 stainless steel. On March 23,1999, Mr. Reid informed Mr. Bower that the proposed modification has the potential to result in a " dash 85" relicensing.
==
Conclusions:==
The 'end cap" concept meets the intent of canning as described in ISG-1, provided DOE -
can demonstrate that the damaged fuel remains in a known suberitical geomentry Reactor records must be used as the primary source ofinformation regarding damaged fuel. Video inspection provide only secondary information.
Known failed fuel must be considered to be " damaged fuel" until proven otherwise.
At present, credit can not be assumed for the borated stainless steel baskets in the accident condition.
Replacing the borated stainless steel with 304 stainless steel may result in a " dash 85" relicensing.
' Attachments:
Agenda Handouts Attendance List A
4
NRC SIEN IN SHEET N# I 6F MEETING:.$%f/vja/ g.( hp) Kje/
2[f/fj7 DATE:
/
V Name Affiliation Phone Dennl$ $PJY kk[-
000 AIddnSfM b/N/F85TS 7]YOxw & av
S rs r a n k A r c d
/
bM-s$-7eus P4QM
?W t.
\\_) "o RE (we a t-va u ex3 (1tr )qqt-53tce s
[nhohv Soh wed Vallev belea Services w - M2-2452.
b reb L Beeht.
LMirtb (20s)S21,-9e,9 SbdCervNwh s & k $ ls..a w 2rca c' scu u u a N#E (W GRoot soi-n2.mt4 cum, s ww z sn,m sc,eurna inc.
- v. - u s-un
'-CY Bus:str) E n
..S 3 0 E - FC kw'
.33/- ?d3 : ?2 %
+
Q,w G,.& A v 5 Oct- HQ ((rm )
se, Ac L 71ix
('e,,' /
/h e,eg C ilJL m a v,.
Manssa N'ha\\m N (Lc i s F Po ses - 41s -mi Wita /w L
/l~AAm zo2burisyn s'+ < u a B~ der ik / rkd'
.w wr-stry u >> _ h ' % cc.;,
,t a./ n.
-n. -
M S4wtz-DGe'Is PPO B6i MC 9T50 o
===.
i c
i AGENDA FOR NRC MEETING ON SHIPMENT OF DAMAGED FUEL IN THE TN-BRP AND TN-REG CASKS I.
Background / Overview of Casks and Fuel Tony Suda II.
Summary of Visual Inspection of the Damaged Foel Tony Suda III.
Alternatives for Shipment of the Damaged Fuel Bryan Bower
- Utilizing the TN-REG and TN-BRP Casks
- Utilizing Other Casks IV.
Description of Preferred Approach for Shipment Bill Bracey of the Damaged Fuel
- In Situ Canning Using Basket Compartmeat End Caps V.
Discussion and NRC Feedback VI.
Conclusion and Path Forward i
)
e S
3 3
i Ib3
/.
5 6
\\
g u
i
/
u i
s 8
5
('
ss
\\
t 1 y*
N v.
)
M t.
s i., /
l l-
./
\\
\\
\\
., s
^
A 7~J M
a 0
i
=q g.
g E
h-
/
at
",N il e
I9 d
C*
,e g
5 Q
it s
l}gtt g
1
/
3,5 g
ss to ce.at M M
T.Y
~
FIGURE 1-1 TN-REG PACKAGING ISOMETRIC VIEW TN-REG 1-s
1 OVERVIEW OF TN-BRP LICENSIN'G BASIS C OF C NUMBER 9202 EXPIRATION DATE: JUNE 30,1999 Forged steel containment vessel Viton O-rings 44 compartment borated stainless steel basket Each compartment accommodates 2 fuel assemblies or 1 fuel replacement insert i
i Peripheral aluminum inserts Licensed for transport for the following:
44 BWR spent fuel assemblies 14 year cooled fuel Maximum total decay heat 3.1 kW 25,000 MWD /MTU maximum burnup Shipments between April 1 and October 31
OVERVIEW OF TN-REG LICENSING BASIS C OF C NUMBER 9206 EXPIRATION DATE: MAY 31,2000 Forged steel containment vessel Viton 0-rings 40 compartment borated stainless steel basket Each compartment accommodates 1 fuel assembly or 1 fuel replacement insert Peripheral aluminum inserts Licensed for transport for the following:
20 PWR spent fuel assemblies 17 year cooled fuel Maximum total decay heat 2.7 kW 15,000 MWD /MTU maximum burnup Shipments between April 1 and October 31
SPENT FUEL DATA Reactor Name:
Big Rock Point Original Owner:
Consumers Power Company
. Reactor Location: Michigan Total number of fuel assemblies: 85 Length: 84 inches avg (213.36 cm)
Width: 6.516 inches (16.55 cm)
Weight: 488.6 lbs (221.6 Kg)
Type of fuel: BWR, Uranium Dioxide (UO )
2 Fuel type information:
Rod Matrix 7x7 8x8 9 x 9*
11 x 11 Quantity 4
2 73 6
kg Uranium / Assembly 133 113 141 132 (max)
(max)
Diameter ofrod (inches) 0.700 0.570 0.562 0.449 Enrichment % U-235 (avg.).
2.883 2.853 3.617 3.627 Three assemblies were originally charged with both uranium and plutonium oxide fuel Discharge dates: from June 1968 to May 1974 Cladding: Zircaloy Hardware: Zircaloy
SPENT FUEL DATA Reactor Name:
Robert E. Ginna Original Owner: Rochester Gas and Electric Reactor Location: New York Total number of fuel assemblies:
40 Length: 161.4 inches (409.96 cm)
Width: 7.766 inches (19.72 cm)
Weight: 1320 pounds (598.6 kg)
Type of fuel: PWR; Uranium Dioxide (UO )
2 Fuel type information Rod matrix: 14 x 14 kg Uranium per assembly: 382 Diameter of rods: 0.422 inches Initial Enrichment: 3.473 % U-235 Discharge dates: from March 1971 to May 1972 Burnable Poison Rod Assemblies-Quantity 8 @ 8 pin 29 @ 12 pin Rod diameter:
0.437 inches Rod material: Borosilicate glass pellets in S.S. tubing.
Control Rod assembly information-1 fuel assembly contains a Control Rod Material: 80% Silver,15% Indium,5% Cadium Absorber Two fuel assemblies contain neither poison rods nor control rods.
Cladding: Zircaloy Hardware: Stainless Steel, Inconel
O e
i
SUMMARY
OF DAMAGE The damaged fuel is still in the form of commercial reactor fuel elements The damaged SNF is not in the form of debris, particles, loose pellets, or fragmented rods or assemblies The damaged fuel can be handled in a normal refueling manner using normal refueling type tooling Based on NRC scale, West Valley damaged fuel fall in the middle category, and a case can be made for moving canning line
T N
EM TN N
s E
e I
r A
M e
e T
E ve N
L s
O RE S
u C
E E
er R
I G
L N O L
o E
T DB m
s B
O C EM s
U L
T E s
i A
s O
OE N S e
e i
D NR ES g
l a
b I
MA m
m
/
GS a
e A D d
s RO sl s
l R
k e a
FR O
a u r
e ef o
T l
CS e n s
T e
d u
A l
E N oh o
r E
h w R
n d
M S
F n
e i
D E pi t
G E
K g
n r
L CS o e e
N G E N
A A K b
m I
s L
RA k o g
N ME C E ct a
d A
AU L
a g fr C
DF E
r n N E ci d
I L e n n
e I
LO n n a
i a RH l
I
)
r c s
l A N
)
t l
i r
o a o b
e i
HP r
hf
(
l I
t l
t n
ne 3
e a
n o
ad 6
p c
h a 1
e e
S t
s T
y m
7 o
F m
t r
N e e R
o i
l t
l E
a ab F
n M
e c
n c
s i
i N
t r
e ga E
i a
O r
c o
c l
r L
c s
t i
I t
T E
t s t
n A
L y
ce r
r es e
a o
t f a p
p o
R E
i l
ec
(
U U
b d
t s
i C
G F
a gm n
b ir e
F R
v I
d ns e
e e
N O
ii ir d t d
l mf a
b O
T d
t v
C C
e a
o e
u A
r r
lc e n
m D
E g
s o
R R
n d n i
g D
r e o a
o A
i f
l t
c t
D D
d c
N E
n es n
e a
A G
a pe h
d h
s z o
t n
T A
(
ui n
n C
s S
M g
g mg i
a r
l D
n o o e
A c
e u
i ne f
N r
l n
U n
wf b
n t
a i
of E
n na n
e n
N p
t a
KS o
S n
T I
DC C
D a
S IR P
VIDEO INSPECTION OF BRP & REG FUEL ASSEMBLIES An external video inspection of the BRP and REG fuel assemblies was performed in July and August of 1989.
Two BRP assemblies and five REG assemblies were considered damaged.
The observed damage is listed below:
BRP Fuel
- CE-50
- broken rod
- D-60
- elongated hole REG Fuel
- C-12
- missing bottom plug
- C-34
- cladding rack
- C-30
- split, bulged, and collapsed rods
- C-19
- elongated hole
- C-23
- small round hole j
Reevaluation of videos in 1998 BRP D-60 considered undamaged (abrasion of cladding surface, not through wall)
Two REG fuel assemblies added:
- C small hole
- C fractured rod
ALTERNATIVES FOR SHIPMENT OF DAMAGED FUEL Utilize the TN-REG and TN-BRP Casks Designed specifically for one-time shipment of REG and BRP SNF at West Valley to INEEL Insufficient room for a canister The damaged fuel can be shipped uncanned:
Structural integrity not compromised No special handling required for loading No handling at INEEL prior to interim storage Confinement of gross fuel particles addressed by use of end caps Offers flexibility to ship additional damaged fuel assemblies
t Utilize Other Casks Currently Licensed Cask NAC NLI 1/2 only cask licensed for shipment of damaged fuel assemblies (only one cask in this configuration)
Holds only 1 REG or BRP BRP enrichment and cross section larger than authorized in C of C Would triple handling of damaged fuel Would increase handling of casks Increase occupational exposure Additional procedures, training, readiness assessments If shipped by rail, would require modification of settlement agreement limit of 7 rail shipments If shipped by truck, would impact public acceptance / stakeholder involvement Increased cost of shipments
7 l-Relicensing a Cask l
TN-8L has enough space for a canister, but:
Not licensed for damaged fuel Not licensed for BWR assemblies l
Only holds three assemblies Enrichment of REG assemblies (3.473%) greater than maximum C of C value (3.2%)
Similar operational concerns as NLI 1/2 Additional procedures, training, readiness assessments Increased cost of shipments TN/NuPac - 125B Could hold up to seven assemblies Designed for dry loading, must be modified for wet loading at WVDP Enrichment and burnup of both REG and BRP exceed C of C value Requires significant revision to SAR Significant review effort by NRC required Similar operational concerns as NLI 1/2 Additional procedures, training, readiness assessments Increased cost of shipments
o o
e Figure 1 Conceptual Design, Basket Cap, REG (BRP Similar)
BOTTOM OF LID
)
\\
/
VENT & SCREEN #k h COMPARTMENT CA
[
/-
\\ s MAT'L: 304 SST s
s MAT'L: 304 SST s
/
N N
N N
N s
N N
-=%
.06' h.
.h m
~
W'
- REG FUEL S'
l
'Q k
(
8.05-N COMPARTMENT s
k
\\
k N
I
(
BASKET PLATE r
s y
D
\\
\\'
-=W.06 1.00' q
N 7
3, a
(y/p *, ',
vd ' ' '/M
/
t SCREEN MA T'L: 304SST
'50' DRAIN HOLE CASK BOTTOM COMPARTMENT STOOL MAT'L: 304SST 3034 CAP
o i
TN-REG Basket Arrangement with Periphery Inserts and Fuct Replacement Inserts B.P.I.
TYPE V B.P.I.
FtTEL BASKIT
[ TYPE IV PLATES -
g (TYPICAL)
B.P.I.
(,cjZ [
> r B.P.I.
h
(
["
TYPE II bl 2.
i'
\\
B.,.I
(
""i N
8
[ 5?
M e
s e
s
,/
y F.R.I.
gg_
h 2.
,1
\\,
g
,k k k w
I 7
N M
3 FUEL ASSEMBLY (201 cat ons)
I/
cAsx
[
BODY 1
i
A
/
ANALYTICAL SUPPORT FOR END CAP APPROACH i
Criticality Fissile mass conserved per compartment j
End cap approach will confine particle greater than 0.2 inches in diameter Minimum dimension of fuel pellets is 0.367 inches j
Particle size controlled by chamfers in " egg crate" Fuel rods more reactive than pellets lumped in bottom of compartment Loose pellets not expected in fuel of this vintage Cladding collapse Creep Pellet swelling Containment Update source term Revise for additional decay time Include damaged fuelin source term
9 1
s OPERATIONS SEQUENCE ASSUME 2 HALF-LOAD SHIPMENTS Installation of bottom caps in selected compartments of each basket before first shipment:
Install bottom cap by sliding into place with an insertion tool.
Verify fit of top caps.
First shipment to include no damaged fuel. Top caps not required.
Installation of top caps for second shipment:
Install failed fuel in compartments that have bottom caps.
Place cap over top of assembly with grappling tool, slide into compartment until it bottoms on the fuel assembly.
No fasteners required. The cask lid retains the cap.
Caps remain in place for storage.
O E
SUMMARY
Use of end caps is the best and safest approach:
Provides in-situ canning
. Reduces occupational exposure ALARA Limits extent of physical modifications and SAR revisions
=
Minimizes handling of damaged fuel Minimizes handling of casks Minimizes impact on procedures and training for cask loading Lowest shipment cost
-1 Least impact on shipping schedule and route plan j
Meets intent ofISG-1