ML20153F895
| ML20153F895 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/31/1988 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Hayes J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8809070534 | |
| Download: ML20153F895 (6) | |
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August 31, 1988 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. J. J. Hayes, Jr.
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specification Change VANTAGE 5 Fuel Gentlemen:
On May 20, 1988, South Carolina Electric & Gas Company (SCE&G) requested a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station in support of refueling and operating with VANTAGE 5 fuel.
This submittal contained a Radiological Impact Assessment.
It concluded that the transition from current fuel to VANTAGE 5, with its extended burnup characteristics, would result in a small increase in thyroid and whole body doses. Since large margins currently exist relative to the dose limits, detailed dose analyses were not deemed necessary.
To supplement the previous Radiological Impact Assessment, SCE&G is performing a detailed evaluation of the environment consequences for the FSAR Chapter 15 accidents impacted by the fuel change.
This letter forwards the revised source terms for the Virgil C. Summer Nuclear Station (with VANTAGE 5 fuel) which will be used as input to the ongoing dose calculations.
Table 1 presents the total core inventory of fission products. These results, expressed as the total inventory of noble gases and 50% of the total halogens, were determined using the ORIGEN code based on expected core loadings with VANTAGE 5 fuel.
l Table 2 lists the computed gap release factors for the iodine and noble gas isotopes. These results were calculated using the same methodology aescribed in Section 15.1.7.2 of the Virgil C. Summer Nuclear Station FSAR and are based on a fuel temperature distribution which is bounding for VANTAGE 5 fuel.
Table 3 presents noble gas and iodine inventories corresponding to the highest power assembly in the core region discharged 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> af ter shutdown. These assembly source terms will be used for the determination of radiological consequencer. of the fuel handling accident. A radial peaking factor of 1.65 has been applied consistent with the guidelines of Regulatory Guide 1.25.
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0009070534 B00031 DR ADOCK 050 5
Document Control Desk August 31, 1988 P.je 2 Lastly, Table 4 lists activities calculated for the reactor coolant corresponding to the assumed release from defective fuel rods generating 1%
of the core power. These reactor coolant equilibrium activities were computed with the FIPCO-V1 code using the ORIGEN results as input.
The VANTAGE 5 source terms described above are forwarded at this time to minimize time required to review the SCE&G previous VANTAGE 5 Technical Specification revision requests. The ongoing do',d evaluations are being pe ' armed on a expedited basis to allow submittal of results as soon as possible.
Should you have any questions, please contact us at your convenience.
Very truly yours, hY v
- 0. S. Bradham ARK /058:1cd Attachments c:
D. A. Nauman/J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams, Jr.
G. O. Percival J. N. Grace R. I. Prevatte J. J. Hayes, Jr.
,,. B. Knotts, Jr.
General Managers H. G. Shealy C. A. Price /R. M. Campbell, Jr.
NSRC R. B. Clary RTS K. E. Nodland NPCF J. C. Snelson File (813.20)
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n-TABLE 1 s
VANTAGE 5 FUEL CORE AVERAGE ACTIVITIES Noble,Gasas Halogens (50%)
Curies Curles Released Released from Fuel from Fuel Nuclide Nuclide Kr-83m 9.1E+06 Br-82 1.4E+05 Kr-85m 2.0E+07 Br-83 4.6E+06 Kr-85 6.4E+05 Br-84 7.7E+06 Kr-87 3.7E+07 Kr-88 5.3E+07 I-130 7.9E+05-Kr-89 6.5E+07 I-131 3.9E+07 I-132 5.6E+07 I-133 7.9E+07 I-134 8.5E+07 Xe-151m 5.4E+05 I-135 7.3E+07 4
Xe-133m 2.3E+07 Xe-133 1.5E+08 Nuclide Kilograms (50%)
Xe-135m 3.1E+07 Xe-135 3.3E+07 I-127 1.4 Xe-138 1.3E+08 I-129 5.6 Note:
The Halogen Curie inventory is 50% of the ORIGEN output value.
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TABLE 2 VANTAGE 5 FUEL GAP RELEASE FACTORS r
Percent l
.[falget of Activity in Gao l
1 1-131 1.4 l
I-132 0.15 I-133 0.46 I
l-134 0.095 l
i l
I-135 9.26 r<
4 Xe-131m 1.7 1
Xe-133 1.1 E
j Xe-133m 0,74 J
Xe-135 0.31 i
- l Xs-135m 0.52 j
Xe-138 0.54 i
l r
i Kr-83m 0.14 I
l Kr-85 21.2 i
l Kr-85m 0.21 1
i Kr-87 0.11 I
Kr-88 0.17 i
i I
Kr-89 0.023 l
l
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TA8LE 3 VANTAGE 5 FUEL ACTIVITIES IN HIGHEST RATED ASSEMBLY FOR USE IN FUEL HANDLING ACCIDENT ANALYSIS l
i.
Gases Iodines s
Curies Curies Released Released from Fuel from Fuel Nuclidg Nuclide Kr-85 6.7E+03 I-130 6.2E+01 I-131 5.8E+05 Xe-131m 5.5E+03 I-132 4.9E+05 Xe-133m 1.0E+05 I-133 6.1E+04 Xe-133 1.2E+06 I-135 4.0E+01 Xe-135m 6.3 Xe-135 2.1E+03 o
Nuclide Grams Released I-127 29 I-129 119 Note: The above values are based on source 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown for a single assembly calculated as follows:
Source = Core average source per assembly x 1.65 radial peaking factor.
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TABLE 4 REACTOR COOLANT EQUILIBRIUM FISSION PRODUCT ACTIVITIES Isotope Fission Products Activity uC1/as Br-84 4.8 x 10-2
'Rb-88 8.9 Sr-89 4.2 x 10-3 Sr-90 1.6 x 10-4 Sr-91 6.1 x 10-3 Sr-92 1.3 x 10-3 Y-90 1.1 x 10-4 Y-91 5.3 x 10-4 Y-92 1.1 x 10-3 Zr-95 6.3 x 10-4 Hb-95 6.3 x 10-4 Mo-99 7.5 x 10-1 1-131 3.9 I-132 2.9 I-133 4.6 I-134 6.7 x 10-1 1-135 2.6 Te-132 2.4 Te-134 3.4 x 10-2 Cs-134 3.1 Cs-136 3.4 Cs-137 1.8 Cs-138 1.1 Ba-140 1.3 x 10-2 La-140 9.6 x 10-3 Ce-144 4.2 x 10-4 Pr-144 4.2 x 10-4 Kr-85 9.1 Kr-85m 2.0 Kr-87 1.2 Kr-88 3.6 Xe-131m 2.2 Xe-133 2.6 x 102 Xe-133m 1.7 x 101 Xe-135 8.0 Xe-135m 5.5 x 10-1 Ke-138 7.2 x 10-1
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