ML19317D271
| ML19317D271 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/06/1978 |
| From: | Parker W DUKE POWER CO. |
| To: | Harold Denton, Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19317D272 | List: |
| References | |
| NUDOCS 7911190652 | |
| Download: ML19317D271 (12) | |
Text
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DI91RIBUTIOri FOR INCOt1ING r1ATERIAL 50-269 EC CEriiON H R ORO: PARKER W O DOCDATE: 09/06/79 NRC DUKE PWR DATE RCVD: 09/11/78 7FCTYPE. LETTER NOTARIZED: NO COPIES RECEIVED
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- C'.W:DINO DAU -t W; ENTITLED: "OCCNEE UNIT 1, CYCLE 5 RELOAD REPT", AND DVPLEMENT TO APPLICANT"O LTR CF i.M/26/78 REQUESTING LIC AMEND & TFCH $FEC LV I'3 IOtr.' TO SUPPORT THE OPERATION OF UNIT 1 AT FULL PWR FOR CYCLE 5 EASED ON i C'/rLE 4 LENOTil OF 255 PLUS-f1
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3?34:s3 September 6, 1978 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
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{! Washington, D. C. 20555 Attention: Mr. R. W. Reid, Chief Operating Reactors Branch #4 Re: Oconee Nuclear Station, Unit 1 Docket No. 50-269
Dear Mr. Denton:
My letter of June 26, 1978 provided an initial submittal requesting a license amendment and Technical Specification revisions to support the operation of Oconee Unit 1 at full power for Cycle 5 based on a Cycle 4 length of 235 i 10 EFFD. Subsequently, Oconee Unit 1 was operated to approximately 250 EFPD. An analysis of the effects of this increased length of Cycle 4 on Cycle 5 was performed by B&W. Attachment 1 provides the pages of BAW-1493, "Oconee Unit 1, Cycle 5 Reload Report," which have been affected with the corrected values noted. The analysis included verification of the operating limits provided previously in my letter of June 26, 1978 which indicated that all of the figures are conservative and no changes are required, with the exception of Figure 2.3-2A. A revised Figure 2.3-2A is provided in Attachment 2. These changes to the reload report are provided now in order to facilitate review and approval of the request by the NRC. A ecmplete smooth version of BAW-1493, Revision 2 will be submitted promptly upon receipt from Babcock and Wilcox. In a March 20, 1978 letter, a request was submitted to increase the allowable tilt linit to 6.03% for Cycle 4. Inasmuch as Unit 1 has shut down to refuel for Cycle 5, this change is no longer required and is hereoy rescinded. 782480292 N pc
i i ~ 1 i 4 j Mr. Harold R. Denton Page 2 September 6, 1978 This submittal is considered to supplement my earlier submittal and as j such no license fees are provided. As required, 40 copies of this i submittal are provided. i l Ve y truly yours, d u,.,L /.j. <.- N { William O. Parker, Jr. RLG:vr Attachments i r I 4 l 1 i e f l 4 1 f 1 ,,,,m,- c,_--, .,v,--., ,e w.y., ,~, -., -,,.,,, m.
ATTACHMENT 1 Revised Pages BAW-1493 OCONEE UNIT 1 - CYCLE 5 RELOAD REPORT Pages 2-1 3-3 4-2 4-4 5-3 5-4 5-5 7 's r )
9/5/78 2. OPERATING HISTORY The reference cycle for the nuclear and thermal-hydraulic analyses of Oconee 1, cycle 5 is the currently operating cycle 4. This cycle 5 design is based on a planned cycle 4 length of 250 EFPD rather than the design length of 292 l EFPD. Cycle 5 will operate in a feed-and-bleed mode for its entire design length of 320 EFPD. Initial cycle 4 operation was in a rodded mode. However, a quad-l' rant power tilt was detected during cycle 4 power escalation, and the mode of l operation was converted to feed-and-bleed to provide a larger margin for cy-c.e 4 operation.2 The shuffle pattern for cycle 5 was designed to minimize the effects of any power tilts present in cycle 4. No control rod interchange is planned during cycle 5. t l 2-1 Babcock & Wilcox
>l2,'io Figure 3-2. Enrichment and Burnup Distribution for Oconee 1, Cycle 5 8 9 10 11 12 13 14 15 3.20 2.75 2.75 3.20 3.02 2.75 2.79 3.02 P 28,923 20,985 16,578 31,581 0 16,428 6,288 0 I 3.02 2.75 2.79 2.75 2.79 2.75 3.02 K 0 l 0 14,746 5,477 ' 19,695-9,080 16,881 2.75 2.79 2.79 2.75 3.02 3.02 L 17,841'. 6,247 8,787 16,404 0 0 l 2.75 2.79 2.75 3.02 M 17,846 5,346 18,853 0 l 2.79 2.79 3.02 N l 6,227 7,549 0 3.02 0 0 P R x.xx Initial Enrichment xxxxx BOC Burnup, %'d/mtU Babcock & Wilcox 3-3
c~rr@ 4.2. Fuel Rod Design 4.2.1. Cladding collapse Creep collapse analyses were performed for three-cycle assembly power histo-ries as well as for batch 4D's four-cycle assembly power histories. For cy-cle 5, the batch 5 fuel is more limiting than all other batches except for 4D because of its previous incore exposure time. The batch 5 and 4D assembly power histories were analyzed, and the most limiting assembly from each batch was determined. The power histories for the most limiting assemblies were used to calculate the fast neutron flux level for the energy range above 1 MeV. The collapse time for the most limiting assembly from each batch was conservatively deter-mined to be more than 30,000 effective full-power hours (EFPH), which is longer than the maximum projected batch 5 residence time of 21,336 EFPH (three l cycles) and the maximum projected batch 4D residence time of 28,349 EFPH (four l cycles). The creep collapse analyses were performed based on the conditions set forth in references 4 and 5. 4.2.2. Cladding Stress The Oconee 1 stress parameters are enveloped by a conservative fuel rod stress analysis. Since worst-case stress conditions are at BOL, the batch 4D fuel is also bounded by the fuel rod stress analysis. For design evaluation, the pri-mary membrane stress must be less than two-thirds of the minimum specified un-irradiated yield strength, and all stresses (primary and secondary) must be less than the minimum specified unirradiated yield strength. The margin is in excess of 30% in all cases. With respect to Oconee 1 fuel, the following con-servatisms were used in the analysis: 1. Low post-densification internal pressure. 2. Low initial pellet density. 3. High system pressure. 4. High thermal gradient across the cladding. The stresses reported in reference 6 for core 1 fuel represent conse rvative values with respect to the cycle 5 core. 4.2.3. Cladding Strain The fuel design criteria specify a limit of 1.0% on cladding circumferential plastic strain. The pellet design is established for plastic cladding strain Babcock & \\Milcox 4-2
m x assedly Cumulative Current net elect. Reactor - cycle Incore Disch. output, mWh TMI-1 3 31,720 25,860 18,430,506 ANO-1 2 28,290 17,650 14,575,320 Rancho Seco 2 22,300 17,170 10,297,637 Crystal River 3 1 10,430 4,936,412 Davia-Besse 1 1 2,490 1,009,741 Table 4-1. Fuel Design Parameters and Dimensions Thrice-Twice-Once-burned burned burned Fresh
- FAs, FAs, FAs.
- FAs, Batch 4D Br.cch 5 Batch 6 Batch 7 FA type Mark-B3 Mark-B4 Mark-B4 Mark-B4 No. of FAs 5
60 56 56 Fuel rod OD, in. 0.430 0.430 0.430 0.430 Fuel rod ID, in. 0.377 0.377 0.377 0.377 Flex. spacers, type Spring Spring Spring Spring Rigid spacers, type Zr-4 Zr-4 Zr-4 Zr-4 Undensif active fuel 142.0 142.6 142.25 142.25 length (nom), in. Fuel pellet initial >94.5 93.5 94.0 94.0 density (nom), % TD Fuel pellet OD (mean 0.3685 0.3700 0.3695 0.3695 specif), in. Initial fuel enrich., 3.20
- 2. 75 2.79 3.02 wt % 235U BOC burnup (avg),
31,049 17,524 6,965 0 mwd /mtU l cladding collapse >30,000 >30,000 >30,000 >30,000 time, EFPH Estimated residence 28,349 21,336 22,320 26,256 time (=ax), EFPH 4_4 Babcock & Wilcox
~ M 4 Table 5-1. Oconee 1, Cycle 5 Physics Parameters OI Cycle 5(d Cycle 4 Cycle length, EFPD 292 320 Cycle burnup, Wd/stU 9,136 10g014 Average core burnup. EOC, Wd/stU 19,034 19(055 Initial core loading, atU 82.1 82.1 Critical boron, BOC (no Xe), ppa HZP, group 8 37.5Z Vd(d) 141$ 1426 RZP, groups 7 and 8 inserted 1335 1293 HFP, group 8 inserted 1145 1242 Critical boron, EOC (eq Xe), ppa HZP, group 8 37.5% wd 373 338 l HFP, group 8 37.5% wd 88 43 Control rod worths HFP, BOC, % ak/k Croup 6 1.07 1, 19 Group 7 0.93 1 44 Croup 8 37.5% vd 0.50 0 4? Control rod worths HFP, EOC, % ak/k Group 7 1.16 1- #2 g Croup 8 37.5% wd 0.47 0.48 Max ejected rod worth, HZP, % ak/k
- BOC (N-12) 0.68 0.57 EOC (N-12) 0.61 0.70 Max stuck rod worth, HZP, I ak/k BOC (N-12) 1.74 2.17 EOC (N-12) 2.02 2.01 Power deficit, HZP to 'iFP, I ak/k BOC 1.49 1.31 EOC 2.07 2.11 l
Doppler coeff,10 5(as/k 'F) BOC, 100% power, to Xe -1.45 -1.45 EOC,100% power, e q Xe -1.55 -1.61 l Moderator coeff, HFP, 10-"(ak/k 'F) BOC (0 Xe, crit pga, gp 8 ins) -1.00 -0,48 EOC (eq Xe, 17 ppa, gp 8 ins) -2.55 -2 63 Boron worth. HFP, pps/ ak/k BOC (1150 ppm) 109 108 l EOC (17 ppm) 101 97 Xenon worth, HFP,
- ak/k BOC (4 EFPD) 2.60 2.62 EOC (equilibrium) 2.61 2 74 l
Eff delayed neutron fraction HFP BOC 0.00593 0.00555 EOC 0.00530 0.00520 l (*Icycle 5 data are for the conditions stated in this report. The cycle 4 core conditions are identified in reference 4. } Based on 292 EFPD at 2568 We, cycle 3. l } (c) Cycle 5 data are based on a " planned" cycle 4 length of 2 50 EFFD; the cycle 4 " design" lifetime is 292 EFFD. (d)HZP denotes hot zero power (532F Tavg), HFP denotes hot full power (579F Tayg).
- I Ejected rod worth for groups 5 through 8 inserted.
5-3 Babcock & Wilcox j
e-Table 5-2. Shutdown Margin Calculation for Oconee 1, Cycle 5 BOC, % Ak/k EOC, % Ak/k Available rod worth Total rod worth, HZP 8.85 8.76 Worth reduction due to burnup -0.36 - 0.41 of poison material Maximum stuck rod, HZP -2.17 -2.01 Net worth 6.32 6.34 Less 10% uncertainty -0.63 -0.63 Total available worth 5.69 5.71 Required rod worth Power deficit, HFP to HZP 1.31 2.11 Max allowable inserted rod 0.38 0.68 worth Flux redistribution 0.59 1.19 i Total required worth 2.28 3.98 Shutdown margin (total available 3.41 1.73 worth minus total required worth) Note: Required shutdown margin is 1.00% Ak/k. e 5-4 Babcock & \\Milcox
Figure 5-1. BOC (4 EFPD), Cycle 5 Two-Dimensional Relative Power Distribution - Full Power, Equilibrium Xenon, Normal Rod Positions (Group 8 Inserted) 8 9 10 11 12 13 14 15 H 0.82 0.93 0.95 0.89 1.37 1.02 1.10 0.89 l 7 K 1.35 1.06 1.20 0.98 1.09 0.94 0.85 l \\ 1.-23 1.02 0.94 1.17 0.69 l 1.03 L M 1.08 1.22 0.89 0.93 N 1.21 0.94 0.62 l 0 0.71 I P R Inserted Rod Group No. x.xx Relative Power Density Babcock & Wilcox 5-5
Table 7-1. Comparison of Key Parameters for Accident Analysis FSAR and Predicted densification cycle 5 Parameter report value value Doppler coeff, Ak/k/*F BOC -1.17 x 10-5 -1.45 x 10-5 EOC -1.33 x 10-5 -1.61 x 10-5 l Moderator coeff, Ak/k/*F BOC +0.5 x 10 4 -0.48 x 10-4 EOC -3.0 x 10 4 -2.63 x 10-4 All-rod group worth, HZP % Ak/k 10 8.85 Initial boren conc'n, HFP, ppm 1400 1242 Boron reactivity worth at 70F, ppm /1% Ak/k 75 76 Max ejected rod worth, HFP, % Ak/k 0.65 0.25 Dropped rod worth (HFP), % Ak/k O.46 0.20 Table 7-2. LOCA '.imits, Oconee 1, Cvele 5 Elevation, LHR limits, ft kW/ft 2 15.5 4 16.6 6 18.0 8 17.0 10 16.0 7-3 Babcock & Wilcox}}