ML20071P473
| ML20071P473 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/28/1994 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9408090337 | |
| Download: ML20071P473 (11) | |
Text
Station support Department 10CFR50.90
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e ERGY ecco t"e'av c -ae"<
Nuclear Group Headquarters 965 Chesterbrook Oculevard Wayne, PA 19087 5691 July 28,1994 Docket Nos. 50-277 50-278 Ucense Nos. DPR-44 DPR-56 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Peach Bottom Atomic Power Station, Units 2 and 3 Response to Request for Additional Information Regarding Power Rerate Program (RAl-7)
Dear Sir:
Attached is our response to your request for additional information (RAl-7) discussed in our telephone conversation on July 25,1994 regarding our planned implementation of the Power Rerate Program at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The Power Rerate Program was the subject of Technical Specifications Change Request (TSCR) No. 93-12 which was forwarded to you by letter dated June 23,1993.
If you have any questions, please contact us.
Very truly yours, h ZE hSlm G. A. Hunger, Jr.
Director - Licensing Attachment cc:
T. T. Martin, Administrator, Region I, USNRC W. L. Schmidt, USNRC Senior Resident inspector, PBAPS R. R. Janati, Commonwealth of Pennsylvania 9408090337 940728 PDR ADOCK 05000277 li l
P PDR i
' COMMONWEALTH OF PENNSYLVANIA :
- ss.
COUNTY OF CHESTER W. H. Smith, lil, being first duly sworn, deposes and says:
That he is Vice President of PECO Energy Company; the Applicant herein; that he has read the enclosed response to the request for additional information concerning Technical Specifications Change Request (Number 93-12) for Peach l
Bottom Facility Operating Licenses DPR-44 and DPR-56, and knows the contents l
thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
i Y
Vice President Subscribed and sworn to before me this day of 1994.
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Notary Public EtaAMEdrUynue w'c2Anfitb
Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 RESPONSE TO REQUEST FOH ADDITIONAL INFORMATION (RAl-7)
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 l
QR91119E Tables 9-3 through 9-7 in Attachment 3 to the licensee's letter dated June 23,1993, titled "GE Proprietary Topical Report NEDC-32183P, Power Rerate Safety Analysis t
Report for Peach Sottom 2 and 3," provided radiological consequences analyses for various design basis accidents at uprated reactor power rating (3528 MWt). Provide the major assumptions and parameters used in these analyses complete with, but not limited to, the following:
(1)
Accident source term used Fission-product release fractions, release timing, and fission-product chemical forms.
BRSR9EDE The radiological consequence analyses in support of the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 power rerate program, as presented in General Electric's Topical Report NEDC-32183P, " Power Rerate Safety Analysis Report for Peach Bottom 2 & 3", dated May,1993, were done using the original design basis source terms as presented in the PBAPS Updated Final Safety Analysis Report (UFSAR), Section 14.9, " Evaluations Using AEC Method." To the greatest extent possible, calculations were prepared using the direct ratio of rerated power to original power. In those cases where the original calculations were not available, calculations j
were reconstituted using the original licensing basis assumptions and original power level, then the values were proportionally increased.
For the Loss-of-Coolant Accident (LOCA), fuel handling and control rod drop accidents, the source terms used for the rerate analyses were obtained by scaling up i
the original licensing basis source term by the ratio of 102% of rerated power (3528 MWt) to the power wed in the original UFSAR analyses (3440 MWt). This scale up was based on the continued applicability of the normalized core source term (Cl/MWt) as shown on Table 1. The scale up ratio is 1.026.
For the Main Steam Une Break (MSLB) and instrument line break analyses, the source terms were adjusted up by 3.2% to reflect the increased mass and energy release associated with the line break at rerated power. There were no changes in specific coolant concentrations since they were based on the maximum allowable coolant concentrations under normal conditions (refer to PBAPS, Units 2 and 3 Technical Specification 3.6.B.1). The concentrations for the MSLB were 0.2 uCi/gm and 4.0 1
Docki,t Nos. 50-277 50-278
)
License Nos. DPR-44 I
DPR-56 uCi/gm of I-131 dose equivalent for normal and spiking conditions, respectively. The total release increased due to increased coolant loss prior to isolation. The MSLB coolant loss for rerate is 190,920 pounds.
The fission product release fractions, release timing and chemical forms used in the l
original analyses were maintained for the power rerate analyses (refer to PBAPS UFSAR Table 14.9.8). The values used for LOCA were:
I fission product available i
l for release:
Core noble gases: 100 %
l Core iodines:
25 %
release timing:
immediate to primary containment chemical forms:
100% elemental Question:
l (2)
Site atmospheric relative concentrations (X/Os) for EAB (0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and LPZ (0 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,1 to 4 days, and 4 to 30 days).
EftspARSE The site atmospheric relative concentrations (X/Os) for design basis accidents were calculated according to the guidelines of Regulatory Guide 1.145, " Atmospheric Dispersion Models For Potential Accident Consequence Assessments at Nuclear Power Plants," using the 8/67 through 7/71 meteorological data base and were not changed by rerate.
The specific X/Os are provided in the attached Table 2.
Question:
(3)
Control Room X/Os and methodology used to determine their values.
Resoonse:
The Control Room X/Os were provided in Attachment O to the letter from S. L. Daltroff (Philadelphia Electric Company) to D. G. Eisenhut (U. S. Nuclear Regulatory Commission), dated January 8,1981, and were not changed by rerate. The methodology used to determine the X/Os was the Halitsky methodology from Section 5-5 of Meteorology and Atomic Energy.1968.
The specific X/Os are provided in the attached Table 2.
i 2
Docket Nos. 50-277 50-278
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License Nos. DPR-44 DPR-56 Questioni (4)
Containment and MSIV leak rates.
Bassonse:
The primary containment leak rate was not changed for the rerate analysis. Main Steam isolation Valve (MSIV) leak rates were not considered in the PBAPS original licensing basis and, therefore, were not used for the rerate analysis. The assumptions are provided in the PBAPS UFSAR, Section 14.9.2.1. The primary containment leak rate is assumed to be 0.635% per day. For comparison, the PBAPS, Units 2 and 3 Technical Specifications limit for containment leakage is 0.5% per day.
Question:
(5)
Pressure suppression pool decontamination factors.
Besponse; The pressure suppression pool decontamination factors were not considered in the PBAPS original licensing basis and, therefore, were not used for the rerate analysis.
The assumptions are provided in the PBAPS UFSAR, Section 14.9.2.1.
Question:
(6)
SGTS charcoal adsorber iodine removal efficiencies.
Response
The Standby Gas Treatment System (SGTS) charcoal adsorber iodine removal efficiencies were not changed for rerate. The values used are provided in the PBAPS UFSAR, Section 14.9.2.1. The SGTS charcoal adsorber removal efficiency is 90% for all iodines.
Question:
(7)
Reactor building pressure drawdown time and air mixing rate.
BA199BRAI The reactor building pressure drawdown time and air mixing rate were not considered in the PBAPS original licensing basis and, therefore, were not used for the rerate analysis. Primary containment leakage is conservatively assumed to flow directly through SGTS without mixing in the secondary containment building. The assumptions used are provided in the PBAPS UFSAR, Section 14.9.2.1.
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Docket Nos. 50-277 50-278
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License Nos. DPR-44 DPR 56 Question:
(8)
Reactor building air exchange rate.
Besannasl The reactor building air exchange rate was not considered in the PBAPS original licensing basis and, therefore, was not used for the rerate analysis. Primary containment leakage is conservatively assumed to flow directly through SGTS without mixing in the secondary containment building. The assumption used is provided in the PBAPS UFSAR, Section 14.9.2.1.
Question:
(9)
Containment and reactor building volumes.
Response
The containment and reactor building volumes were not changed for rerate. The volumes are provided in Attachment O to the letter from S. L. Daltroff (Philadelphia Electric Company) to D. G. Eisenhut (U. S. Nuclear Regulatory Commission), dated January 8,1981. The volumes are:
containment:
2.78E5 ft' reactor building:
2.5E6 ft' Question:.
(10)
Dose conversion factors used; list of associated references.
Response
The dose conversion factors used in the rerate analyses are slightly more conservative than those used in the original PBAPS licensing basis analyses. The licensing basis assumptions are provided in the PBAPS UFSAR, Section 14.9.2.5. The values used for the rerate analyses are provided in the attached Tule 3.
Question:
(11)
SGTS filtration rate.
Response
The SGTS filtration rate was not changed for rerate. Primary containment leakage is not assumed to mix in secondary containment; instead, the leakage is conservatively 4
Docket Nos. 50-277 50-278 Ucense Nos. DPR-44 DPR-56 assumed to flow directly through SGTS. This assumption is provided in the PBAPS UFSAR, Section 14.9.2.1. The actual SGTS maximum filtration rate is 10,500 cfm as provided in the PBAPS UFSAR, Section 5.3.4.
@ 91110D1 l
(12)
Control room volume (effective), emergency air intake rate, air recirculation rate, and charcoal adsorber iodine removal efficiency.
B91990101 i
The control room volume (effective) emergency air intake rate, air recirculation rate and charcoal adsorber iodine removal efficiency were not changed for rerate. The assumptions used are provided in the PBAPS UFSAR, Section 14.9.1.5, and 1
Attachment O to the letter from S. L. Daltroff (Philadelphia Electric Company) to D. G.
Eisenhut (U. S. Nuclear Regulatory Commission), dated January 8,1981. The values used for the rerate analysis are:
control room volume:
1.76E5 ft' emergency air intake rate:
3000 cfm air recirculation rate:
O cfm charcoal adsorber iodine removal efficiency:
90 %
l Question; i
I For LOCA radiological consequence analysis, provide dose contributions from each of the following sources:
(1)
Containment leak 3
(2)
ECCS system leak outside containment (3)
MSIV leak flesponse:
The LOCA radiological consequence analysis was not changed for rerate. In accordance with the original PBAPS licensing basis and the PBAPS UFSAR, Section 14.9.2, only containment leakage is considered in Table 9-3 of NEDC-32183P.
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a
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TABLE 1 1
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Normalized Accident Source Term Isotope Source Term (Ci/MWt)
I-131 2.508E+04 I-132 3.806E+04 I-133 5.622E+04 I-134 6.575E+04 I-135 5.103E+04 Br-83 1.055e+03 Br-84 1.904E+03 Br-85 2.672E+03 Kr-83m 4.152E+03 Kr-85 4.102E+02 l
Kr-85m 1.297E+04 l
Kr-87 2.335E+04 Kr-88 3.200E+04 Kr-89 3.979E+04 Xe-131m 2.595E+02 i
Xe-133m 1.384E+03 Xe-133 5.622E+04 Xe-135m 1.557E+04 Xe-135 5.363E+04 Xe-137 5.103E+04 Re-138 4.775E+04 k
TABLE 2 PBAPS SITE SPECIFIC RELATIVE CONCENTRATIONS X/O (sec/m^3)
ELEVATED GROUND STACK LEVEL RELEASE RELEASE i
EAB 0 - 2 hr 1.360E-05 4.900E-04 LPZ 0 - 8 hr 2.011 E-05 8 - 24 hr 1.308E-05 24 - 96 hr 5.141 E-06 l
96 - 720 hr 1.347E-06 CONTROL ROOM 0-8hr 2.400E-06 1.010E-03
)
8 - 24 hr 9.000E-07 5.950E-04 l
24 - 96 hr 6.600E-08 2.270E 04 96 - 720 hr 2.000E-09 6.680E-05 Note:
Due to terrain corrections, all LPZ doses are calculated assuming a ground level release.
O
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e
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TABLE 3 -- DOSE CONVERSION FACTORS A.
Beta and Gamma Dose Conversion Factors Used in Post-Accident Radiological Consequences Rerate Analyses Semi-Infinite Cloud Gamma Dose Conversion Factors (Rem /hr per Cl/m')
In A Room of Finite Size isotope (Rem /hr per Cl/m )
2 K,
K, K n
~
l-129 48.0 22.5 0.0277 l-131 173.0 338.0 2.84 l-132 349.0 2061.0 17.2 1-133 334.0 572.0 3.53 1134 462.0 2259.0 13.0 1-135 393.0 1314.0 11.5
~
l-136 693.0 2493.0 14.6 Br-83 283.0 3.6 0.052 Br-84 787.0 1656.0 10.15 Br-85 662.0 0.0 0.0 Br-87 1010.0 2160.0 14.7 Kr-83m 28.1 4.5 0.0062 Kr-85m 83.6 140.0 1.15 Kr-85 189.0 1.9 0.016 Kr-87 840.0 770.0 7.87 Kr-88 254.0 1800.0 10.4 Kr-89 828.0 1998.0 6.70 Xe-131m 112.0 19.8 0.025 Xe-133m 158.0 21.6 0.25 Xe-133 104.0 65.7 0.23 Xe-135m 74.5 396.0 3.12 Xe-135 250.0 223.0 1.89 Xe-137 1134.0 173.0 1.11 Xe-138 468.0 839.0 5.74 l
1 of 2
e.
TABLE 3 -- DOSE CONVERSION FACTORS B.
Thyroid Dose Conversion Factors Used in Post-Accident Radiological Consequences Rerate Analyses Isotope K,ny (Rem /hr per Cl/m')
1-131 1.85 x 10' 4
l-132 6.67 x 10 5
l-133 5.00 x 10 l-134 3.13 x 10' 5
l-135 1.55 x 10 i,
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