ML17297B105
| ML17297B105 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/11/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| ANPP-19677-JMA, NUDOCS 8112180362 | |
| Download: ML17297B105 (8) | |
Text
"AOCBSSION NBR:811 FA OIL: STN 50,.528 STN"50"529 STN 50 '530
'AUTH INANE VAN BRUNTPE ~ ED TRBC IP ~ NAME TEDESCOgR ~ LE 2180362 DOC ~ DATE: -81/12/11 NOTAR I'2ED:
YES lpalo Verde, Nuclear Stations Unilt ii Arizona Publ
~Palo Verde Nuclear Station<
Unilt 2g "Arizona Publ WPalo Verde Nuclear Stations Unilt T3~ Arizona Publ AUTHOR AFFILIATION
'Arizcna Publ ic Ser vice -Co ~
RECIPIENT AFFILIATION Assistant Director for Licensin'g DO:
0 05000529 05000530
SUBJECT:
Forwards response to Confirmatory Item 22 of SER re spent fuel pool. Info will be incorporated into.future FSAR amend, DI'STRIBUT ION CODE:
800 1'S TCOP I ES TRECEI VED: LTR
-ENCL 8 I2E e,
/
/
TITLE: PSAR/FSAR At<DTS and Related Correspondence NOTES:Standardized iPlant,i cy:C Grimes
'Standardized IPlant F 1 cy,'C Grimes
-Standardized IPlant F 1 cy'.C Grimes 05000528 05000529
.05000530
-RECIPIENT ID CODE/NAP'E ACTION:
A/D LIGENSNG LIC BR P3 LA INTERAL: ELD IE/DEP/EPDB 35 MPA NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/NTEB 17 NRR/DE/SAB 2Q NRR/DHFS/HFEB40 NRR/DHFS/OL'8 3Q NRR/DS I/AEB 26 NRR/DS I/CP8 10 NRR/DSI/ETSB 12 NRR/DSI/PSB 19 NRR RSB 23 00 EXTERNAL: ACRS 41
,FERA REP DI V 39 NRC PDR 02 NTI' ICOPIES LTTR ENCL 1
0 1
0
'1 0
1 1
1
.0 3
3 2
2.
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
16 16 1
1 1
1 1
1 RECIPIENT ID CODE/NAVE LIC BR 03 BC KERR IGANE'J, 01 IE 06 IE/DEP/EPLB 36 NRR/DE/CEB 11 NRR/DE/GB 28 NRR/DE/NEB 18 NRR/DE/GAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DHFS/PTRB20 NRR/DSI/ASB 27 NRR/DSI/CSB 09 NRR/DS I/ICSB 16 NRR/DSI/RAB 22 NRR/DST/I GB 33 BNL(AVDTS ONLY)
LPDR 03
- NSIC, 05 COPIES LTlTR ENCL 1
0 1
1 3
3 3
3 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1
-1 1
1 1
1 1
1 1
$ 1 iTOTAL NUMBER OF COPIES REQUIRED:
LTTR Q
ENCL
$8
IRUfHlllCP KHS!It5IEI OXSHBkZP STA.
P.O. SOX 21666 PHOENIX, ARIZONA85036 December ll, 1981 ANPP-19677 JMA/KEJ Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
H'<t-U DL.C 17 1981~ pg KiI~~I,>k I',Pr SR Palo Verde Nuclear Generating Stati nr~p, (PVNGS) Units 1, 2, and 3
Docket Nos.
STN-50-528/529/530 I'~
File:
81-056-026; G.1.10
Reference:
NUREG-0857, Safety Evaluation Report related to the Operation of Palo Verde Nuclear. Generating Station, Units 1, 2, and 3 dated
- November, 1981
Dear Mr. Tedesco:
Please find attached our response to confirmatory Item No.
22 of the referenced PVNGS SER concerning the spent fuel pool (9.1.2 Part II).
The attached information amends our response to NRC Question 282.1 (PVNGS FSAR Question 9A.39) submitted in Amendment 4 of the FSAR, along with a des-cription of the design of the spent fuel pool poison tubes.
This infor-mation also discusses the compatability of the poison tubes with the spent fuel storage pool environment.
This information was submitted informally to your Mr. Bernard Turovlin of the Corrosion Engineering Section of the Chemical Engineering Branch on November 9, 1981.
The FSAR will be updated in a future amendment to incor-porate this information.
If you have any questions, please contact me.
Very truly yours, EEVBJr/KEJ/av Attachment cc:
J. Kerrigan (w/a)
P. Hourihan (w/a)
Sll2180362 Bii2ii PDR ADOCK 05000528 E
PDR'.
E. Van Brunt Jr.
APS Vice Presi ent, Nuclear Projects ANPP Project Director A. C. Gehr (w/a)
B. Turovlin (w/a) goo>
S
,/'t
STATE OF ARIZONA
)
)
as'OUNTY OF MARICOPA)
I, John M. Allen, represent that I am Nuclear Engineering Manager of Arizona Public Service Company, that the foregoing document has been signed by me for Edwin E. Van Brunt, Jr., Vice President Nuclear Projects, on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
ohn M. Allen Sworn to before me thde~lP day of wO 8~~35 1981.
Notary Public My Commission expires:
g Provide fabrication details of the Boral tube inserts to be
.'used in the spent fuel storage pool.
Provide details of the kind and thickness of the cladding of the Boral.
Explain how exposed Boral matrix (Boron carbide) is protected from the borated pool water.
Describe corrosion protection of the Boral tube.
~Res ense:
The poison material used in the spent fuel pool poison tubes will be Boraflex.
Boralfex is not a corrosive material and will retain sufficient properties in borated water to exceed a postulated 40-year design lifetime.
Attachment 1
summarizes the behavior of Boraflex in borated water.
At;tachment 2 show"a monolith arrangement of the poison tube.
s The poison tube is a 'vented design, and is supported and locked in place in the same manners as the "L" inserts All material is 304 stainless, therefore corrosion is not a problem.
The Boraflex material is held in place. as shown in Attachment 2.
The foil, holding the poison in place, is folded completely around the 0.060" thick spent fuel box and poison material sub-assembly with a slight overlap.
A resistance tack weld is provided 2" on center over the full length of the foil, as shown in Section A-A of Attachment 2.
In addition, resistance or tack welds (1" on center) are provided at the top and bottom of the foil as shown in Attachment 2.
Note:
1.
"L" inserts are shown on FSAR figures 9.1-4 through 9.1-6.
ATTACHMENT 1 Accelerated A in of Boraflex in Borated Water Accelerated thermal aging of the Boraflex spent fuel rack poison material in borated ~ater
~as carried out in a pressure autoclave maintaineo at 240oF.
Using the Arrhenius methodology (see attached Table 2) and assuming a doubling of the reaction rate for each 10oC increase in temperature, 46 days-at 240oF is equivalent to 40 years at 90oF.
The Boraflex was aged in borated water (6,000 ppm B as H3B03).
At appropriate times the autoclave was opened and test specimens were removed
'nd tested.
Tne data are presented below and in the attached figure.
'able 1
Autoclave A in of Boraflex at 240oF in Borated Hater Days at 240oF 0
13 42 71 114 145 Equivalent Aging Time years 0
11.2 36.3 61.3 98.5 125 Hardness Shore "A"
ASTM 02200 84 86 87 89 93 90 Tensile Strength (psi)
ASTM 0412 740 530 355 325 300
.255 Elongation at Break
/)
ASTM 04l2 40 50 30 25 10 20 As can be seer from the data,'lthough there is a drop in tensile strength and elongation as the aging continued, the Boraflex retained approximate'.y 50X of its or:ginal strength at the 40 year equivalent aging time.
The material retained 34K of its original strength and 50/ or its ultimate elongation eve:n at the 125 year equivalent aging time (145 days).
These samples retained suff'icient flexibility and strength to function as a, neutron attenuator within the constraints of the C-E design.
Data taken fron Bisco Report 8748-21 show that after 199 days at 240oF in a 3,000 ppm B solution samples of Boraflex showed a linear dimensional change of -0.93'/. and a weight change of +0.241.
These numbers represent an average of measurements ta'ken on 6 samples.
Table 2
Accelerated A in Calculation The 10-degree rule states that for each 10oC rise in temperature, the specific reaction rate doubles.
Thus:
~d C x 2 f(T2 - Tl)/10)
,dt whe re.
q
= the extent of reaction at 'any given time (t)
C = an experimental constant
" T = temperature in degrees C
integrating with respect to time yields q
=
C x 2 f(T2 - Tl)/10)t comparing reaction at 2 sets of time and temperature conditions yields:- --
=
q2/ql
=. (t2/tl) 2((T2-Tl)/10) where subscript 2 refers to accelerated conditions and
. subscript 1 refers to service conditions
'I since q2
= ql
'= 21(T2 - Tl)/10I t2 Substituting the values for the accelerated autoclave aging v'alue where tl = 40 years (14610 days) and Tl
= 90oF (32.2oC)
~ and t2
= (to be determined T2
= 240oF (115.5oC) t2
= 14610 days 2 8.3)
= 46.3 days therefore according to the 10-degree rule 46.3 days at 240oF is equivalent to 40 years at 90oF
~ ~
'IENSiZ STRB ~8 (PSD SPENT FUEL STORAGE RACK POISON EFFECT 0-". AUTOCLAVE AGiho 763 Silicone/B<C-KR(ta) i.K DAYS AT 248 F
CVSCOalCrC LOCaTIOIr COM8USTION ENGINEERING. INC, WINDSOR. CONN.
CC..~*
C C
~
WO. No.
III' IIr Dare 4/adO4Z7h'ZZsrsrc'r&r47 47dRASE' CFOUL err' ow oar 2nrsEz,7 c
I
~
ATTACP:KNT 2 C
I 'I I
lg rouoN 2nl~iCT
~
~
pfwrocrrg rcoc7vcs
,rgb w~cc. (Jo4 o.sr.)
8.sos'I l,~ g l"J"
~ So'Il GigiiacSS -.GI2.>
o(o -<.0 L. l.css-ADIT as)
Tcgp ic.a) 5 4m~ A O5="
ICI P lILCS I
I I
I~'l
-'I' I.
~I
~I a
5C aaS porto@
p/jItjA'rrcc fOC.
sTrIHD os 4'PrIJt P.wzs PO
./SO Pal)4 nM7%otC
~
~
g~ C~nrcyny Talc oc'ccsis)aaLQSpat
~(')cia I gca4rs I
-,oeo 5 faarlr59 8<%wc,ss.
Tac,l og RcsIS Ia cc.
SIIsk 4cA4
'2 C.CIskcrs pVSC SCrIri~( SuZrri Cr.
SII Ot craacarar
~ arr. Icra ~