ML072550304
| ML072550304 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/11/2007 |
| From: | Katz B Southern California Edison Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML072550304 (30) | |
Text
Brian Katz
_ ISOUTHERN
_ CALIFORNIA Vice President An EDISON INTERNATIONAL`- Company September 11, 2007 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Docket Nos. 50-361 and 50-362 Amendment Application Numbers 243, Supplement 2 and 227, Supplement 2, Proposed Change Number (PCN) 556, Revision 2 San Onofre Nuclear Generating Station Units 2 and 3
References:
- 1) Letter from Brian Katz (SCE) to the U. S. Nuclear Regulatory Commission dated June 15, 2007;
Subject:
Docket Nos. 50-361 and 50-362, Amendment Application Numbers 243 Supplement 1 and 227 Supplement 1, Proposed Change Number (PCN) 556, Revision 1, Request to Revise Fuel Storage Pool Boron Concentration, San Onofre Nuclear Generating Station Units 2 and 3
- 2) Letter A. E. Scherer (SCE) to the U. S. Nuclear Regulator Commission (Document Control Desk) dated July 27, 2007,
Subject:
Docket Nos. 50-361 and 50-362, Response to Request for Additional Information in Support of Amendment Application Numbers 243 and 227, Proposed Change Number (PCN) 556, Revision 1, Request to Revise Fuel Storage Pool Boron Concentration, San Onofre Nuclear Generating Station Units 2 and 3
Dear Sir or Madam:
By letter dated June 15, 2007 (Reference 1) Southern California Edison (SCE) requested approval of Amendment Application Numbers 243 Supplement 1 and 227 Supplement 1, which consist of PCN 556 Revision 1. PCN 556 Revision 1 proposes to revise Technical Specifications 3.7.17, "Fuel Storage Pool Boron Concentration,"
3.7.18, "Spent Fuel Assembly Storage," and 4.3, "Fuel Storage." This proposed change will increase the minimum allowed boron concentration of the spent fuel pool and allow credit for soluble boron, guide tube inserts (GT-Inserts) made from borated stainless steel, and fuel storage patterns in place of Boraflex.
P.O. Box 128 San Clemente, CA 92674-0128 949-368-9275
/.AoD/
Fax 949-368-9881
Document Control Desk September 11, 2007 By letter dated July 27, 2007 (Reference 2), SCE provided additional information in the form of responses to NRC request for additional information (RAI) questions 25 and 26.
The response to NRC question 26 included commitment to apply a 6.6% reduction to the CECOR computer code determination of fuel assembly burnup for all fuel assemblies prior to determination of the allowable storage location per the proposed Technical Specification 4.3.1 and Licensee Controlled Specification 4.0.100.
This letter provides a clarification to the SCE response to NRC question 25. Also included are revised pages for Attachments C, D, E, F, I, and J of PCN 556 to incorporate the SCE commitment related to fuel assembly burnup determination. In addition to the 6.6% reduction for Units 2 and 3 fuel a burnup reduction of 10.0% will be applied to Unit 1 fuel. These revised pages are provided as Amendment Application Numbers 243, Supplement 2 and 227, Supplement 2, consisting of PCN 556, Revision 2.
SCE has evaluated PCN 556, Revision 2 under the standards set forth in 10CFR50.92(c) and determined that SCE's original finding of "no significant hazards consideration" is not changed.
If you have any questions or require additional information, please contact Ms. Linda T. Conklin at (949) 368-9443.
Sincerely,
Enclosures:
- 1) Notarized Affidavits for Amendment Applications 243, Supplement 2 and 227, Supplement 2
- 2) Revised responses to NRC Question 25
- 3) Replacement pages for Attachments C, D, E, F, I and J of PCN 556 Revision 1 cc: B. S. Mallett, Regional Administrator, NRC Region IV N. Kalyanam, NRC Project Manager, San Onofre Units 2 and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, California Department of Health Services, Radiologic Health Branch
Enclosure 1 Notarized Affidavits
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, ET AL. for a Class 103 ) Docket No. 50-361 License to Acquire, Possess, and Use )
a Utilization Facility as Part of ) Amendment Application Unit No. 2 of the San Onofre Nuclear ) No. 243, Supplement 2 Generating Station )
SOUTHERN CALIFORNIA EDISON COMPANY et al., pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 243, Supplement 2. This amendment application consists of proposed change No. NPF-10-556, Revision 2 to Facility Operating License NPF-10. Proposed change No. NPF-10-556, Revision 2 provides revised pages to Attachments C, D, E, F, I, and J in support of the request to revise Technical Specification 3.7.17, "Fuel Storage Pool Boron Concentration," 3.7.18, "Spent Fuel Assembly Storage," 4.3, "Fuel Storage," and Licensee Controlled Specification 4.0.100, "Fuel Storage Patterns." This proposed change will revise the minimum allowed boron concentration of the spent fuel pool and implement a Fuel Storage Program to allow credit for soluble boron, guide tube inserts, and Fuel Storage Patterns in place of Boraflex.
State of California County of San Diego Brian Katz, Vice Pre nt Subscribed and sworn to () before me this 1 day of S-e Io~k m b yv-,e 2007.
by: KA-I*-z-KY*+io-i personally known to me or prowd to mc on thc basis of satisfacto.' evidenco to be the person who appeared before me. DAWN A. FARRELL I *-. Commlsaon # 1623105 Notary Public
,0 1MyoM.Exkw~o20091
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )
EDISON COMPANY, ET AL. for a Class 103 ) Docket No. 50-362 License to Acquire, Possess, and Use )
a Utilization Facility as Part of ) Amendment Application Unit No. 3 of the San Onofre Nuclear ) No. 227, Supplement 2 Generating Station )
SOUTHERN CALIFORNIA EDISON COMPANY et al., pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 227, Supplement 2. This amendment application consists of proposed change No. NPF-1 5-556, Revision 2 to Facility Operating License NPF-15. Proposed change No. NPF-15-556, Revision 2 provides revised pages to Attachments C, D, E, F, I, and J in support of the request to revise Technical Specification 3.7.17, "Fuel Storage Pool Boron Concentration," 3.7.18, "Spent Fuel Assembly Storage," 4.3, "Fuel Storage," and Licensee Controlled Specification 4.0.100, "Fuel Storage Patterns." This proposed change will revise the minimum allowed boron concentration of the spent fuel pool and implement a Fuel Storage Program to allow credit for soluble boron, guide tube inserts, and Fuel Storage Patterns in place of Boraflex.
State of California County of San Diego Brian Katz, Vice Presi&+t Subscribed and sworn to (a ) before me this I1-'- day of
___________-e
_ ___, 2007.
by:
- L..i personally known to me cr.,,.vtid to be the person who appeared before me.
Notary Public - h co ,*
Enclosure 2 Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
SCE revised response to Question 25, Part (a) (iii):
(iii) The pool temperature bias has been evaluated for both Region I and Region II storage patterns. An infinite 2-D CASMO-3 model is used for both Region I and Region I1. For both storage regions, the temperature range is from 68 0 F to 160 0 F, and the soluble boron range is from 0 ppm to 1000 ppm. One-thousand ppm bounds the total soluble boron requirement of 970 ppm to maintain Keff less than or equal to 0.95. The Region I enrichment range is from 1.85 weight percent (w/o) to 5.1 w/o. (The effective fresh fuel enrichment limit for Region I is 2.47 w/o). The Region II enrichment range is from 1.20 w/o to 1.85 w/o. (The effective fresh fuel enrichment limit for Region II is 1.23 w/o.) See Table 4-1 of Attachment L of PCN 556, Revision 1 (Reference 1). The most adverse value for the whole enrichment range and from 0 ppm to 1000 ppm for each SFP region is used. This is an additional conservatism for the no soluble boron Keff < 1 .0 cases.
As shown in Table 4-1, a conservative bias is used. For example, a temperature reactivity bias of 0.00285 derived from 1.85 w/o at 1000 ppm will be used for the 0 ppm case which exhibits a decrease in reactivity with increasing temperature.
68 0 F is the lowest expected temperature. The upper temperature limit of 160'F is the maximum expected non-accident spent fuel pool temperature from UFSAR Section 9.1.3.1.
For Region I, the fuel temperature bias is determined for up to 5.1 w/o which bounds the effective fresh fuel enrichment of 2.47 w/o, which is the highest fresh fuel enrichment for unrestricted storage in Region I. As shown in Table 4-1 of Attachment L to the submittal, the highest temperature bias which occurs at 5.1 w/o is selected. For Region II which doesn't have a water gap between storage cells, the temperature reactivity effect is significantly smaller than the Region I values and is negative (more conservative) at 0 ppm. A conservative temperature bias of 0.003 based on the 1000 ppm case is used for both the 0 ppm case and the borated cases. This value is more conservative than the temperature reactivity for the effective fresh fuel enrichment limit of 1.23 w/o, As shown in the Beaver Valley Unit 2 Spent Fuel Rack Criticality Analysis With Credit For Soluble Boron (CAA-98-158-Rev 1, November 1998), the pool temperature bias Ak decreases as less ( 3-out-of-4, 2-out-of four, etc) than a fully loaded rack (every location contains an assembly) is modeled. Thus SCE has analyzed the worst fuel pattern (fully loaded rack) to determine the pool temperature bias.
In addition, the fuel assembly grids are not modeled. The negative reactivity provided by the grids (0.11% Ap), which is applicable to 0 ppm and borated cases, would also compensate for enrichment and fuel pattern effects.
Page 1 of 5
Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
Furthermore, as described in Section 5 of Attachment L to the submittal, a discretionary conservative allowance (margin) of 154 ppm is included in the soluble boron requirement. As discussed in response to RAI #14, this discretionary margin is equivalent to an additional conservatism of 0.017 Ak for borated cases.
SCE revised response to Question 25, Part (b):
"Axial Burnup Effect" refers to the potential non-conservative results due to the 2D approximation that uses the axially averaged assembly burnup values in the criticality calculation. Initially, fuel in the reactor will deplete with a slightly skewed cosine power shape. As burnup progresses, the power distribution will tend to flatten due to the more highly burned fuel in the central regions than in the upper and lower regions. At high burnups, the more reactive fuel near the ends of the fuel assembly occurs in regions of high neutron leakage (top and bottom of the assembly). Consequently, it is expected that over most of the burnup history, fuel assemblies with distributed burnups will exhibit a slightly lower reactivity than that calculated for the uniform average burnup. As burnup increases, the distribution tend to be self-regulating as controlled by the axial power distribution, precluding the existence of large regions of significantly reduced burnup. The effect was evaluated in a paper by S. E. Turner, "Uncertainty Analyses -
Burnup Distributions," presented at the DOE/SANDIA Technical Meeting on Fuel Burnup Credit, Special Section, ANS/ENS Conference, Washington D.C., November 2, 1988." In summary, the effect is typically minor and generally negative reactivity effect of the axially distributed burnups at values less than about 30 GWD/T with small positive reactivity effects at higher burnup values.
However, depending on plant designs, the top region of the assembly may have burnups significantly lower than the average for highly depleted assemblies. For example, the use of Axial Power Shaping Rod (APSR) in B&W reactors may result in a highly skewed axial burnup profile with low burnups in the top region. In this instance, the axial burnup effect may be significant.
Section 3.2.5 of Attachment L of the SCE submittal discussed the process used to determine whether the use of conservative temperatures can override the "axial burnup effect" for SONGS fuel. The process is summarized below.
Step 1. Construct a single assembly SIMULATE-3 model in 3D geometry for the assembly of interest. Deplete the assembly with the nominal moderator and fuel temperatures to various burnup points of interest. These temperatures produce a realistic, axially-varying isotopic inventory.
Step 2. Construct a single assembly SIMULATE-3 model in 2D geometry for the assembly in Step 1 above. Instead of the nominal moderator and fuel temperatures, the 2D depletion was performed at a constant moderator temperature of 600'F and a constant fuel temperature of 1200'F. These constant temperatures produce a more conservative isotopic make-up due to the harder neutron spectrum. The burnup and temperature history were expanded to the 3D geometry consistent with the geometry in Page 2 of 5
Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
Step 1 above. All axial elevations of the fuel will have the same burnup and temperature history. This is consistent with the 2D modeling employed in CASMO-3.
Step 3. Using the results from Steps 1 and 2 above, perform SIMULATE-3 restarts at burnup values of 0, 10, 20, 30, 40, 50, and 60 GWD/T; at 0 ppm; 68°F; and no xenon to simulate the spent fuel rack conditions. Keff values from the case with the conservative moderator and fuel temperatures (Step 2) and the case with nominal temperatures (Step 1) were compared to verify that the conservative temperature approach was sufficient to override the axial burnup effect.
As shown in response to RAI #10, the conservative temperature approach (2D) was more conservative. Therefore, the axial burnup bias is conservatively set at 0.0 Ak.
Additional calculations have been performed to bound the off-nominal temperature/power operations. The calculations have been performed for enrichment values of 1.87 w/o, 4.45 w/o, and 5.0 w/o. For each enrichment, the 3-D depletion was performed at inlet temperatures of 533 0 F and 560 0 F. This temperature range bounds the SONGS Tech. Spec limit of 535 0 F to 558 0 F. In addition, another 3-D depletion was performed at 533 0 F and at 30 percent power to bound extended part power operations.
As shown in Tables 1, 2, and 3 below, the 2-D depletion with conservatively high coolant temperature of 600'F resulted in the most conservative Keff values for all enrichment cases. For example, for the 5.00 w/o fuel, at 50 GWD/T, the 2-D, high coolant temperature approach is more conservative by 0.005 Ak. This is due to the hardening of the neutron spectrum resulting in a more conservative isotopic make-up.
The above calculations were performed at a spent fuel pool temperature of 68 0 F.
Another check case was performed at 160°F to verify that the conclusion is valid for the entire spent fuel pool temperature range (68°F to 160 0 F. The enrichment selected is 3.00 w/o, which is about the mid-range of the enrichment of interest. As shown in Table 4, the 2-D depletion with conservatively high coolant temperature of 600°F resulted in the most conservative Keff values at the spent fuel pool temperature of 160°F also.
Oak Ridge report, NUREG/CR-6801, "Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses," presents studies of the axial burnup effect using axial burnup profiles provided by PWR plants of various designs. As described in Section 4.2.2 of the report, CE fuel types tend to exhibit a smaller end effect on average. As shown in Figures 31, 32, 33, and 34 of the report, Ak values for CE fuel are close to zero and are very small as compared to a maximum axial burnup effect of up to 0.04 Ak for B&W fuel. The small end effect of CE fuel is the key reason that contributes to the conservative results in the SONGS approach. This is consistent with Calvert Cliffs (another CE plant) results using plant specific axial burnup profiles (See Calvert Cliffs Three-Dimensional to Two Dimensional Reactivity Bias table in Section 9.E.2.1 of the Calvert Cliffs submittal dated September 30, 2003, ADAMS number ML033140579).
Page 3 of 5
Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
In the submittal approved in Reference 6, an independent method was used to show that the San Onofre fuel assembly axial bias is 0.0 Ak. The burnup distribution from a discharged San Onofre assembly was converted to equivalent fresh enrichments. The equivalent fresh enrichments were input to a 3-D KENO model. A second 3-D KENO model with uniform enrichment corresponding to the assembly average burnup was also set up. This comparison also showed that the 2-D (uniform axial distribution) approach is conservative for San Onofre fuel.
Table 1: Comparison of 3-D to 2-D Keff for 1.87 w/o fuel, 68 0 F Enrichment: 1.87 w/o T-inlet=600°F T-inlet=560°F T-inlet=533 0 F T-inlet=533 0 F Burnup Full Power DepI Full Power DepI 30% Power DepI (GWD/T) 2D Keff 3D Keff 3D Keff 3D Keff 0 1.24454 1.24454 1.24454 1.24454 10 1.11561 1.10850 1.10709 1.10490 20 1.01562 1.00878 1.00496 1.00046 30 0.94019 0.93346 0.92798 0.92199 40 0.88513 0.87830 0.87189 0.86544 50 0.84777 0.84081 0.83401 0.82774 60 0.82274 0.81489 0.80810 0.80236 Table 2: Comparison of 3-D to 2-D Keff for 4.45 w/o fuel, 68°F Enrichment: 4.45 w/o T-inlet=600°F T-inlet=560°F T-inlet=533°F T-inlet=533 0 F Burnup Full Power DepI Full Power DepI 30% Power Depi (GWD/T) 2D Keff 3D Keff 3D Keff 3D Keff 0 1.45672 1.45671 1.45671 1.45671 10 1.34135 1.33419 1.33383 1.33329 20 1.25052 1.24340 1.24148 1.23945 30 1.16868 1.16173 1.15776 1.15397 40 1.08984 1.08362 1.07724 1.07167 50 1.01564 1.00999 1.00110 0.99401 60 0.94916 0.94295 0.93176 0.92361 Page 4 of 5
Revised Response to NRC Question 25 Part (a) (iii) and Part (b)
Table 3: Comparison of 3-D to 2-D K~ff for 5.00 w/o fuel, 68 0 F Enrichment: 5.00 w/o T-inlet=600°F T-inlet=560 0 F T-inlet=533 0 F T-inlet=533 0 F Burnup Full Power Depl Full Power Depl 30% Power Depl (GWD/T) 2D Keff 3D Keff 3D Keff 3D Keff 0 1.47775 1.47774 1.47774 1.47774 10 1.36755 1.36062 1.36044 1.35994 20 1.28119 1.27421 1.27278 1.27097 30 1.20332 1.19638 1.19324 1.18980 40 1.12761 1.12133 1.11607 1.11090 50 1.05452 1.04890 1.04122 1.03439 60 0.98617 0.98034 0.97014 0.96187 Table 4: Comparison of 3-D to 2-D Keff for 3.00 w/o fuel, 160'F Enrichment: 3.00 w/o, 160'F T-inlet=600°F T-inlet=560°F T-inlet=533°F T-inlet=533°F Burnup Full Power DepI Full Power Depl 30% Power Depl (GWD/T) 2D Keff 3D Keff 3D Keff 3D Keff 0 1.36674 1.36674 1.36674 1.36674 10 1.23654 1.22858 1.22746 1.22673 20 1.13529 1.12735 1.12365 1.12108 30 1.04856 1.04078 1.03439 1.03000 40 0.97298 0.96564 0.95704 0.95120 50 0.91215 0.90480 0.89511 0.88843 60 0.86677 0.85836 0.84846 0.84161 Page 5 of 5
Enclosure 3 Replacement pages for Attachments C, D, E, F, I, and J of PCN 556, Revision 2
PCN-556 Revision 2 Attachment C (Proposed Technical Specification Pages)
(Revised Page 4.0-4a)
(Redline and Strikeout, Unit 2)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.1 Criticality (continued)
-g. P .rj..... oo ..... c.r". t. ri. .Lco 3.7 .18 aznd LCS1/4-4.':10l0ý, teo: ingiic ertainPt ie s wil
- be6 ~appl i~edl
.R) the .cýalculae*,*ae.sci ta'q*,eburup.of. San Onofre Uni 2 'nd2 .asls~enmblltes w.iwl*be .! ,,educed, 2r _ _
- . .. .. wi I' ýb rodtb -. b;*'T#":
66%.
(2)' Th e lb urn ,.o'f, San, :Onofre f.: ...;asisie i s ls 4 be bil reducedd by
....... I f, "" .........
- . u .
h,., Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7..1.:8-1 are allowed unrestricted storage in Region -14';
i.i Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-2 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 f;ces toward the spentifuel-pool walls of Region +I+T;;
&T
-- - - --- i 1ow~ed ur re-str'i ct"ed',sd g~,,g.1i~,4j
- k. t~ 2 a ~:ass6HiýesWit,,h; abu-rnup ih th "acep~tablil,'.: e i J 7an18-4 'aire allTow~ed unrsti~" s a, iii the Ob ý~i heral pool.
1o~cati ons wjtiý,h b1 ý~2.atest~ r d ,he sp-ent fuel pool wal is bf , Re'~- 11*II Uits 2 and 3, Ffue I assemblies with a burnup in the Unl.
"nacceptable raq"of 1-L .gr IjJ'ý: and Figure 3.7.18--&
will be stored in compliance with *the-Licensee Controlled Specification 4.0.100 -1 2t, ý,dated i--m/x'~xx;and t.mThie-burnp--eof--etach SONGS 1 uranium dioxide spent f~uel asýsembly stored in Region II shall be-grieater~
than or equal t 14.0 CW-/T for interior locatiamns
~-r--~--5GWDT fr R'eripheral laeations, or the fuel em-y-44 be stored in accordance with.
I irc~n. o -flnrolled Specification 4.0.100 Rev,.'2, dated xx/'x/-x.
(conti nued)
SAN ONOFRE--UNIT 2 4.0-4a Amendment No. 127, 131
PCN 556 Revision 2 Attachment D (Proposed Technical Specification Pages)
(Revised Page 4.0-4a)
(Redline and Strikeout, Unit 3)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.1 Criticality (continued) fy ror to, usijnq ý&aq;,cri-teri aof LC0372 "and' 'LCS 4 Oý.'o0',:0 't:heý-,fol, wiguneraInie wl lbe "a'pplied:
(1)..The caca.t eddlscha _. urnupo uo San :Onorrne Units 2sand 3 assembiIes..wI.. be, reduced b f.~..
.;,,e. .- .of. w*ý, r.
. .,Thee c.' . -. :e bu..n u=p 1Unt .l.le* _ -**!*e
- reledi otf;.Sae U O re 4Th. *Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-1 are allowed unrestricted storage in Region -I+1;
-gfl. Units 2 and 3 fuel assemblies with a burnup in the acceptable range" of Figure 3.7.18-2 are allrowed unrestricted storage in the peripheral pool i, locations with 1 or 2 faces toward the spent fuel pool walls of Region H-l;
-Lls-an ;I~id u&elas iem wiha*s -brn b"e u1hl"h urih estriit e t-i,]iag* e i:nJRegi-on I . ;
- .sd k , t*Uns 2 and 3.:fuel assemblies with a burnu', . the "unacceptable rianqe" of qFiure 3 7 18-4i.. alioý.q, d wilbestoricted.in ompli6aqe iw the-rithhe ra*1-Lo6es Control1 ed Speciir 2 on face .,O the -spn*fu*
41-f eTt.sL1 ased `3, fue assemblies with a burnup in the "unacceptable,wi:ixx:anI d ranqe of Figure 3.7.18-1. FlI , Ugqirl
'3.71& i~e 8 and Figure 3.7.1-4 will be stored in compliance with the-Licensee Controlled Specification 4.0.100 Rev.*1 **.2:d and (cxnt/x u; m.T-he -- btr9, --#~c SNS 1 uranium dioxide spent fuel asse'mb'ly' stored in Region II shall e-reater r W'or r eihr-1 loations, or hc-, fuepl
~eb-Y , be s;tored in accordance with.
n.
c..aa rr +'-v-~olled Specification 4.0.100Re.2 chtd xx/xx/"kx .
(conti nued)
SAN ONOFRE-UNIT 3 4.0-4a Amendment No. 1-6, 120
PCN 556 Revision 2 Attachment E (Revised Pages 4.0-4 and 4.0-4a)
(Proposed Technical Specification Pages, Unit 2)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent;
- b. Keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- c. Keff : 0.95 if fully flooded with water borated to 1700 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- d. Three or five Borated stainless steel guide tube inserts (GT-Insert) may be used. When three-,
Borated stainless steel guide tube inserts ar.e used, they will be installed in an assembly's center guide tube, the guide tube associated with the serial number, and the diagonally opposite guide tube. Fuel containing GT-Inserts may be placed in either Region I or Region II. However, credit for GT-Inserts is only taken for Region II storage.
A five-finger CEA may be installed in an assembly.
Fuel containing a five-finger CEA may be placed in either Region I or Region II. Credit for inserted 5-finger CEAs is taken for both Region I and Region II.
- e. A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II;
- f. A nominal 10.40 inch center to center distance between fuel assemblies placed in Region I; Ira-(continued)
SAN ONOFRE--UNIT 2 4.0-4 Amendment No.
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.1 Criticality (continued)
- g. Prior to using the storage criteria of LCO 3.7.18 and LCS 4.0.100, the following uncertainties will be applied:
(1) The calculated discharge burnup of San Onofre Units 2 and 3 assemblies will be reduced by 6.6%.
(2) The calculated discharge burnup of San Onofre Unit 1 fuel assemblies will be reduced by 10.0%.
- h. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-1 are allowed unrestricted storage in Region I;
- i. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-2 are allowed unrestricted storage in the peripheral pool :
locations with 1 or 2 faces toward the spent fuel pool walls of Region I;
- j. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of.Figure 3.7.18-3 are allowed unrestricted storage in Region II;
- k. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-4 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region II;
- 1. Units 2 and 3 fuel assemblies with a burnup in the "unacceptable range" of Figure 3.7.18-1, Figure 3.7.18-2, Figure 3.7.18-3, and Figure 3.7.18-4 will be stored in compliance with Licensee Controlled Specification 4.0.100 Rev. 2, dated xx/xx/xx; and
- m. Each SONGS I uranium dioxide spent fuel assembly stored in Region II shall be stored in accordance with Licensee Controlled Specification 4.0.100 Rev. 2, dated xx/xx/xx.
(continued)
SAN ONOFRE--UNIT 2 4.0-4a Amendment No.
PCN-556 Revision 2 Attachment F (Revised Pages 4.0-4 and 4.0-4a)
(Proposed Technical Specification Pages, Unit 3)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent;
- b. Keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as
.-- d es-c-ri-b edi-n.--S-ec-t on--9-.-1--of.-he--U.FSAR;.......
- c. Keff : 0.95 i.f fully flooded with water borated to 1700 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- d. Three or five Borated stainless steel guide t~ube inserts (GT-Inserts) may be used. When three Borated stainless steel guide tube inserts areý used, they will be installed in an assembly's center guide tube, the guide tube associated wi-th the serial number, and the diagonally opposite guide tube. Fuel containing GT-Inserts may be placed in either Region I or Region II. However, credit for GT-Inserts is only taken for Region. II storage.
A five-finger CEA may be installed in an assembly.
Fuel containing a five-finger CEA may be placed in either Region I or Region II. Credit for inserted 5-finger CEAs is taken for both Region I and Region II.
- e. A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II;
- f. A nominal 10.40 inch center to center distance between fuel assemblies placed in Region I; (continued)
SAN ONOFRE-UNIT 3 4.0-4 Amendment No.
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.1 Criticality (continued)
- g. Prior to using the storage criteria of LCO 3.7.18 and LCS 4.0.100, the following uncertainties will be applied:
(1) The calculated discharge burnup of San Onofre ,4-Units 2 and 3 assemblies will be reduced by 6.6%.
(2) The calculated discharge burnup of San Onofre Unit I fuel assemblies will be reduced by
-.. .. . .. .0.0. . . . .. . . . .. . . ..
- h. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-1 are allowed unrestricted storage in Region I;
- i. Units 2 and 3 fuel assemblies with a burnup in t.he "acceptable range" of Figure 3.7.18-2 are allowed unrestricted storage in the peripheral pool .
locations with 1 or 2 faces toward the spent fuel pool walls of Region I;
- j. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-3 areallowed unrestricted storage in Region II;.
- k. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.7.18-4 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region II;
- 1. Units 2 and 3 fuel assemblies with a burnup in the "unacceptable range" of Figure 3.7.18-1, Figure 3.7.18-2, Figure 3.7.18-3, and Figure 3.7.18-4 will be stored in compliance with Licensee Controlled Specification 4.0.100 Rev. 2, dated xx/xx/xx; and
- m. Each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be stored in accordance with Licensee Controlled Specification 4.0.100 Rev. 2, dated xx/xx/xx.
(continued)
SAN ONOFRE-UNIT 3 4.0-4a Amendment No.
PCN-556 Revision 2 Attachment I (Revised Pages 4.0-100-1 through 4.0-100-3)
(Proposed LCS 4.0.100 Unit 2)
(The date XX/XX/XX on each page of LCS 4.0.100 will be the date of NRC approval of License Amendment Application 243)
Fuel Storage Patterns for Region IIRa-ks LCS 4.0.100 4.0 DESIGN FEATURES LCS 4.0.100 Fuel Storage Patterns for Region IIRo*k* and Region-+
- Racks' t,.II,l'...""
Recons,, ""U Stati on "itution.
-I-on--' J, JCa i, -t-evlsaion number a date a eind in Techn"a, naSp cificaiqo-n AAlA1 uch e s to page;s 1 th'rou 4 Re2 ýdg8ted 1-.
-xxxkx~~
k -t~~sLS i e~ xcl diqP~h BAavKes',, 4 app~roqie~d, by.- th e%.NRC- -v~i a th
.'&pib~ e~nrnnt jp1"icfat ionm ipr,,es s ~in :oo'p~u~ncti onýý :1,~se &e eo ehi~ 1ýSpec ~icat" or4n 4; to o ýa'e jcri e"k ulcrtn be 1ebl Ipl' d IP Te. cAT.']u ated% dha.arq ' e bur-n:0; -f San~ -~2~
7'~ e~r e,:- uee Uni1t-s: 2ý and .3 f u, as semblires by 6 V 6 h) 00%a; I
VALIDITY STATEMENT: Rev. 2+ effective Upop',1R-C.'~~vT12+/-97 to be implemented within 3~1,80 days.
4j.0:.10.0 New or burned fuel (which does not meet the criteria of LCO 3.7.18 for unrestricted storage or storage at the pool periphery) may be stored in R)qi'""br-ýRRegi - I ifa*4li the .rn t
with". t"he al:fbowalb]I e .Sto -** 'scr.iedinji.- hi:s LO.s . afollowing ndit i*aons are met.
4.0.000.1I Reg-.ibon =Re'qir6 6 2 ',S~t'orage _Patterns, ýare'-giý'en: in -Tables` -
- 1hroug~h 1 '8and. Fi~gures I-f t~hrou~gi .1-9..
,Uc, Type 1 New or burned ,ul ,hich does not meet the criteria of L*O 3.7.18 for unrestricted storage or storage at the SAN ONOFRE-UNIT 2 4.0-100-1 Rev. 2
Fuel Storage Patterns for Rgior HI Raks LCS 4.0.100 4 .:0.:1:00.i2 Reg~io .= Re~g~ion S~ýonStordage_!Patterns are i n'in"Table'sini 4.~~sorg Fbel Region *-- inITbrsý:JI II.PT6dý
.3. Uý esl
- ý-t "J mee li7 6 r te, iE 5111 iUlý IIý.- g !m H ..
f r IU Tw - .1 (A)
N sHtial eTrichJmt :.t 4.1 Se shal be stored i in a checkrboe. pten. The for4) basic re*Our X--
L.JIR
,I,-!re.
(1)/ Typc 1 fuel asblsU I ca n.t bU iln a- Ae laI o Thecan, how"ver,*
be In -iag ! .locations .
(2) Tp1fu.e4 assemfblies stored in Reio 4MIIshall 1 haycv at least two (2) side (3) kcord ý;term does met~nee4d to (4) /IgJre 4.0.1I -IIUid1Ilutrati an em of *11. .. p abl I storagc pattern.
d.,~
04.00.&113 S111SJ '1 I. l l
.... .[.\ -F4-.4-,..;;, -T -t!! :-t~* -.. *'* , ,- ;- fz
.- -*,4-1,
÷ 4 4 .'0'. 10 0.4 ae~b 'tiiýf eaf6h','S'GN G-Si2U n, '4 urm1a"# Jdib'o td Ist :f t -
asseihb'y tlie owin 71
<*3:-.*,.- .... .. . ... ! fl]`:
e-*0 $0N*S*`**i:]t
",'-f u~ ":,:.' (C nrecnsti A lnfra]77
's **-..... *":*:'*:utiIoi s 1<":f station Iln:.*Bei imld
- "h1
-La# -'*en{I';fRis a """r::":z*<"r." ;cks:,cas epecilo1f --a checke~rbor pater. - 'T-he tabv~e .rtl-es -for%-
checkerboa "ing. permi-t a reconstitution tUi.o lull awhr in the Regioan 11 racks. Single o-r mnultbiple row reconstitution stations are pritte.bd. Figure .4.0.100 2 provides an ill~
u-tai on.g in Region 11 in a 'Three ouit of fou-r' pattern if the assembly 0i tUn atleast J.L, DJ/I T 4.0.v 100.6:4.1 * **' :'*f-VO ;:':- : t;v".,' :::"' ,k'iOnr s tr"i; cte*:7.*:m- :T .***T*'-** -:;*;.,7';'.** 7L -4;5,,*;t;;
- f,:"**:d,,.:,*'
,the.b:uirn*up's is*qlreate:.'t'hah 25;,000MWD/T., and
'the ..i.,*'- I e:a e tram5.e .
SAN ONOFRE-UNIT 2 4.0-100-2 Rev. z:,XX/X-X/Xx
Fuel Storage Patterns ar Rlegion 4 .0a.ks LCS 4.0.100 4.0.100-.4..2 SONGS. Ui*th:- , `1nomi na ,l 4: ,:00` w /6o assembl. .ies,can :b stored in the
- :ýJ _ O-j...:"*ý,si :d
. :: 3 :.,: -"'**:,** ' *"' " !* ..*,, . . . .. . . * " ' ". . ..".. .
Rgo'n:,j. Acks 'R .(u ifrJ lt.he :!budr-nurlS *i;s.,qri:e a*.er: -t~han :.26.,300 *;MW0/*T~,-a::,i6*d th.e bu nuprAnSr-',eater th-an 27,100 MW D/T, a~nd fh~eC-0o I~fm -i*s ~ 5 ea4 i icrea e tfr 2 ~0~W/~,ii o '~~~imi g~~~e e r' tfh an1y0 4.0.100.4.3 ~S;;NGS~jWniht-m1 naominJ~-s- aa4 ýj n:th
`hi ~b "tn rth~i~000M
`Y{e D/!Tb$, d6
-e`
Ur-q M-i, qg.ez erM
- 4. 0. 100 'Re ...... r':.d.eft*.,: s ': Tu b.e. Ins
. -.. r :s... Ig e 5 i0fi0 i_ ____ req on-AF,(15O i4YchY.,
.adhav~e- aý4Rn'iaium 'bo-r~ri .` of 002434t',,g'rasx B10 per tcnm
~iTj) o,*ervey, .f~xeel*.as s*emb 1-be-tbee 3) srnb uirý *y. 4wn t h...B3 ~u.de.- u'l*e.i &r-t s '
n qn2 A~ fin.qer,*'.fll,:lenqth Control Eli'*eme Assembly (C.QA) mb be un, u 'ml-aceof GT-inserts..
4.0.100.6 Design requirements For Erbia Assemblies containing 40 or 80 erbia rods shall have the erbia rods distributed per Figures 11-24 and 11-25. The minimum initial nominal erbia loading shall be 2.0 w/o Er203.
4.0.100.7 The Failed Fuel Rod Storage Basket (FFRSB)
The Failed Fuel Rod Storage Basket (FFRSB) shall be treated as if it were an assembly with enrichment and burnup of the rod in the basket with the most limiting combination of enrichment and burnup.
SAN ONOFRE-UNIT 2 4.0-100-3 Rev. 2.:XX/.XX/XX
PCN-556 Revision 2 Attachment J (Revised Pages 4.0-100-1 through 4.0-100-3)
(Proposed LCS 4.0.100 Unit 3)
(The date XX/XX/XX on each page of LCS 4.0.100 will be the date of NRC approval of License Amendment Application 227)
Fuel Storage Patterns for Region II Racks LCS 4.0.100 4.0 DESIGN FEATURES LCS 4.0.100 Fuel Storage Patterns for Region RIIRaks and Regio,,II Racks Rconstitution Statin T~s Llens~e e Conole~d Spe 1ficati*'n*Js lstedt bey i a~djd..a~S Se~cificatAtio~n p.~eii~
mu t bt be,, a.pproy, e.d' b:*:ýy,,;t he'. NR (*iv*!*a.:*:*. the amendment appi I'ca i,:ýon`prceissi- ginqwj th ;an aso ~~e change-,
':- e . " : '.i, - Y.....- - - -. "1: . -
- ,u,,;6
`4
- ,:- *'. '**'.,.:::.,.",.TE 2:
,::J*NO
- i f* */ :* .qA.":.':...
- h '..,.'..,,
,Y- *=/'.*
d -- h
-'bclclt-!ed un of San Oh:onpre A-LJT4i-62a-]dc 1',a, 2 ue J~ssii4ib Sra e-4 -b rei
(.2) e;C al u-l~ated ,,di ,.hia*e ;bu enu o f San..Orniofr-e P .f ue**
. ':.. . .,*l a s..i
. . :4-*' ,: '}* w. : fi'V b e.' r.e.d
" "u..c*
, e d...:' * .: S ' : .,: . st-VALIDITY STATEMENT: Rev. +Z effective upNR, Gn'Va.oal 12*197ov,to be implemented within 3O-1*8. days.
New or burned fuel (which does not meet the criteria of LCO 3.7.18 for unrestricted storage or storage at the OO] ieriphery) may be stored In ý oRe' I ageI* atf tal.he sptoreriphery may storedri be "L " T11,401
.- tiistoredi.
ac r aoeat -.. ' e ag a i 'ierns:-d descri bed ien.,t::;Is LICS .following *coditions are met.
C4. 0, 1i00.
Reg ion I1. RegQio n,!I St orage .Pa erns ciaeve n in Tablei:.-.I thlraugh-- I -BI: UIli+IIh1ough tiur I-9.
FueTe ~-New a, Litt, fe whi ch does not meet the criteria of [CO 3EG 1 for unrestriecled storage or storage at the SAN ONOFRE--UNIT 3 4.0-100-1 Rev. XX1'/.-X.--X.
Fuel Storage Patterns for Region II Raek*
LCS 4.0.100
,4; .. 00.2 Re~jon I Reqid TI So~ra~qe -Pternn~si _iax.Cqiv~en jin .TbsII1 L69 3.7..P do . t. .. cr i a of kn-i A r.,
I U4 I 1 T,,-
I . J; Il-lI II*I, VE 1 i bIm i 1 en ll IellllEllt t 4I' 8 (B .u cIII ec I a Ibe stared 3{o UI in a chec-'kerbard pattern. The ou (1) ruiremnt for Region! II torage .,re.
Type 1 fuel assemblies car not be in adjaccnt.. ýjoatos C-A" They can, however, (2) T'pl fu;lassembiesQ stored in Region (2l ha.e at 1cst, to (2) sides (3 facin nemtloation.
h121cc-bad atr does not need toý T*Jn oo vathlQN Unt"'I I rIu 'nV T. b ;&.1d' ýsp'eU 6L 6_1IE of~ailluslcfulstrgeptrtern.~ an _r! e kU_ rJ~ IbC
ý_U*I 6 LIlUA V I 5Le I IUY U IIIa U 1lI U 4.-100*.4 as~ib~2~iR~ion s~t6-~d ~I ~ I..lset~h~~orawge patterna.
ml Y rwU I ull I bbCt j tj_
tto iI
"'.. IA-ý I y bUp V.1 1. t k.kU.
-l m ae6 I .. t iE II J.ccror a gAi ii s tp,.m.j.1 pattern T ru aoe;us4o , t s ato anywhere in the Region II rackls. Single or utpkrow reconstitu~tion st Ati. arc,.,
Permitted. Figure 4.9.199 2 provides an J"1,,.tat onr4-.
(0)m ~aOnofrc UnI . . fuel assembi jes may be stared in Reio in a 'Three out of four' pattern ifth asembly burn- is at les 1.7 QWD/T.
44/
S 4.0 100nhdK ..1.S. silESUni.t Ud i'*f: 1 t.4..4 toe.,L. inI .*t R e g iji om ;I* I , :R a eck s ; -,,:( a n r st r ,*
- e . l . l,] :
11'1.1':1,111 *:**, II..lli:IU nlrI e si r **id: :I *ZII'L.:II : I:d
t~hb"ý'f.
- s "i""hup MWD;/ A theo~T.ini it-h. i,-;g,1eat&- 5yearss.
"tIa' SAN ONOFRE--UNIT 3 4.0-100-2 Rev. 2
Fuel Storage Patterns for Region II. Racks LCS 4.0.100 4".OO42 'SONGS ,Un~it 1 :nomi n-al ~4. w/o ass ibiTsý can bstrednth Region: Ala-cks (ubnre`stibr'eted) V:
e burnul .s Sth .qr-,eater- -t~ht'ain.2.6,3026 0- '/;T,. and th,*e cbi o .51n, mes ;g eter6 ; ht :yea~rs thejb~urnup. T~s ',reater thn2,00 -MWD/T, la~n th' ~b un u up.-., -s .ýýqrte e, j th, -200 MWdV/ n
,th e coo.giýiie: ,sireag heae.
a~n i-'Oiyea'rgs..
. . . . .. . . _a
].,-. ::m* *'*' .... . . ... i..*l... .-....
, . .- * *V o 4 i e .
tfj 000 q 1*MWD/TU d 4.0. 100.5 Design reurees or E Asseblie n aaee am s40ti brA ii e80Thi
~o ehbo :i c n h; se~ ~ : ~ Ž~ 3 ~ j - m b
~d
~ 3 p r c-, ~
p-1 *-
rods),GTd red er& Fig II-24 sures anda: owIe2d" hie or i enit it beed tuel sameStorgeB
, 5-f i nqeFr agef hm-ent E(Bl by r eAs'sem a (CEAsi niay. be used-,,J~,I-p-ce 'o~f :b-ds~t~h~~~ loir A~un mi n-urm foading ofminelerbi idjub~K
~shall beV ,Jert~
2.0 w/o Er203.~
4.0.100.6 Design requirements For Erbia Assemblies containing 40 or 80 erbia rods shall have the erbia rods distributed per Figures 11-24 and 11-25. The minimum initial nominal erbia loading shall be 2.0 w/o Er203.
4.0.100.7 The Failed Fuel Rod Storage Basket (FFRSB)
The Failed Fuel Rod Storage Basket (FFRSB) shall be treated as if it were an assembly with enrichment and burnup of the rod in the basket with the most limiting combination of enrichment and burnup.
SAN ONOFRE--UNIT 3 4.0-100-3 Rev. 2 XX/XX/-,M