GNRO-2011/00050, Request for Additional Information Regarding Extended Power Uprate, License No. NPF-29

Request for Additional Information Regarding Extended Power Uprate, License No. NPF-29

ML111730235
Person / Time
Site:	Grand Gulf
Issue date:	06/21/2011
From:	Krupa M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2011/00050
Download: ML111730235 (10)

Text

Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6684 GNRO-2011/00050 June 21, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Request for Additional Information Regarding Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. Email from A. Wang to F. Burford dated June 1, 2011, GGNS EPU Request for Additional Information Related to Accident Dose Branch Review (ME4679) (NRC ADAMS Accession Number ML111520458)

2. License Amendment Request, Extended Power Uprate, dated September 8, 2010 (GNRO-2010/00056, NRC ADAMS Accession Number ML102660403)

Dear Sir or Madam:

The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1) regarding certain aspects of the Grand Gulf Nuclear Station, Unit 1 (GGNS) Extended Power Uprate (EPU) License Amendment Request (LAR) (Reference 2). Attachment 1 provides responses to the additional information requested by the Accident Dose Branch.

No change is needed to the no significant hazards consideration included in the initial LAR (Reference 2) as a result of the additional information provided. There are no new commitments included in this letter.

If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.

GNRO-2011/00050 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on June 21, 2011.

Sincerely, MAK/FGB/dm Attachments:

1. Response to Request for Additional Information, Accident Dose Branch cc: Mr. Elmo E. Collins, Jr.

Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)

ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150

Attachment 1 GNRO-2011/00050 Grand Gulf Nuclear Station Extended Power Uprate Response to Request for Additional Information Accident Dose Branch to GNRO-2011/ 00050 Page 1 of 7 Response to Request for Additional Information Accident Dose Branch By letter dated September 8, 2010, Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) for an Extended Power Uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS). By letter dated April 14, 2011, Entergy submitted responses to the initial request for additional information (RAI) from the Accident Dose Branch (NRC ADAMS Accession No. ML111050134). Subsequently, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information requested by the Accident Dose Branch is needed for the NRC staff to complete their review of the amendment. Entergys response to each item is provided below.

RAI # 1 In Attachment 1 to the letter dated April 14, 2011, it is stated that a weighted dose scaling factor is used to calculate the EPU dose results for the fuel handling accident (FHA), the control rod drop accident (CRDA), and the pressure controller failure event. Please provide additional information describing the methodology used or provide the calculations used to develop the weighted dose scaling factors for the EAB, LPZ, and CR for the FHA, CRDA, and the pressure controller failure event Please provide the basis for the weighted dose scaling factors that were used. Please provide any values that were used to develop the weighted dose scaling factors and describe any models that were used to calculate those values.

Response

As described in Entergys letter to the NRC dated April 14, 2011, the EPU dose is estimated for certain events based on the contribution of each isotope to the calculated dose in the calculation-of-record and the predicted increase in each isotope for EPU. The current licensed thermal power (CLTP) doses are then increased by this weighted scaling factor to develop an accurate estimate of the doses at the EPU power level. The following three tables address the fuel handling accident, control rod drop accident, and the pressure controller failure events.

As shown in each table, the contributions to the calculated doses from each isotope are presented for the CLTP case at each location. To generate the EPU dose, these CLTP doses are then adjusted by the EPU-related increase or decrease for each isotope as reported in Tables 1 and 2 of the April 14, 2011 letter. At each location, the doses from each isotope are then summed for a total dose and the weighted dose scaling factor can be calculated based on the ratio of the total doses.

Attachment 1 to GNRO-2011/ 00050 Page 2 of 7 Table 1: FHA Dose Consequence -

Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU EPU Source EAB TEDE Control Room Change EAB TEDE Control Room (Rem) TEDE (Rem)  % (Rem) TEDE (Rem)

Br-82 7.04E-04 5.67E-04 10.75% 7.80E-04 6.28E-04 Br-83 5.16E-07 7.20E-07 -5.74% 4.77E-07 6.79E-07 I-130 2.79E-03 2.94E-03 7.38% 3.00E-03 3.16E-03 I-131 1.68E+00 2.44E+00 11.73% 1.88E+00 2.73E+00 I-132 6.24E-02 2.60E-02 12.25% 7.00E-02 2.92E-02 I-133 1.94E-01 2.69E-01 9.05% 2.12E-01 2.93E-01 I-135 1.08E-02 9.57E-03 10.09% 1.19E-02 1.05E-02 Kr-83M 6.78E-08 5.65E-09 -5.70% 6.39E-08 5.33E-09 Kr-85 1.76E-04 1.47E-05 92.92% 3.40E-04 2.84E-05 Kr-85M 4.93E-03 4.10E-04 -10.18% 4.43E-03 3.68E-04 Kr-88 2.22E-02 1.85E-03 -12.80% 1.94E-02 1.61E-03 Xe-129M 2.77E-06 2.31E-07 2.52% 2.84E-06 2.37E-07 Xe-131M 3.18E-04 2.65E-05 10.93% 3.53E-04 2.94E-05 Xe-133 2.05E-01 1.70E-02 16.12% 2.38E-01 1.97E-02 Xe-133M 5.23E-03 4.35E-04 18.15% 6.18E-03 5.14E-04 Xe-135 4.15E-01 3.45E-02 53.85% 6.38E-01 5.31E-02 Xe-135M 3.55E-02 2.95E-03 11.19% 3.95E-02 3.28E-03 Total 2.64E+00 2.80E+00 3.12E+00 3.14E+00 Weighted Scaling Factor 1.18 1.12 EAB - Exclusion Area Boundary TEDE - Total Effective Dose Equivalent to GNRO-2011/ 00050 Page 3 of 7 Table 2: CRDA Dose Consequence -

Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU Bundle Source Bundle Source (1.7 peaking Control (1.7 peaking Control factor) EAB 2 hr LPZ TEDE Room TEDE factor) EAB 2 hr LPZ TEDE Room TEDE (Ci/bundle) TEDE (Rem) (Rem) (Rem) (Ci/bundle) TEDE (Rem) (Rem) (Rem)

Br-82 2.717E+03 2.30E-05 2.07E-05 8.97E-05 3.028E+03 2.56E-05 2.30E-05 1.00E-04 Br-83 3.798E+04 7.99E-06 2.83E-06 1.24E-05 3.599E+04 7.58E-06 2.68E-06 1.17E-05 Br-84 7.107E+04 8.05E-05 1.91E-05 3.87E-06 6.460E+04 7.32E-05 1.74E-05 3.52E-06 Kr-83M 3.796E+04 1.31E-07 4.25E-08 9.47E-09 3.599E+04 1.24E-07 4.03E-08 8.97E-09 Kr-85 3.102E+03 1.20E-06 1.46E-06 5.90E-07 4.760E+03 1.85E-06 2.25E-06 9.05E-07 Kr-85M 8.844E+04 1.85E-03 9.16E-04 2.94E-04 7.982E+04 1.67E-03 8.26E-04 2.65E-04 Kr-87 1.786E+05 1.46E-02 4.14E-03 7.23E-04 1.567E+05 1.28E-02 3.63E-03 6.34E-04 Kr-88 2.525E+05 6.64E-02 2.61E-02 7.16E-03 2.213E+05 5.82E-02 2.28E-02 6.28E-03 Kr-89 3.207E+05 4.08E-03 9.33E-04 1.06E-05 2.754E+05 3.50E-03 8.01E-04 9.12E-06 I-128 8.534E+03 6.70E-07 1.56E-07 1.09E-07 9.131E+03 7.17E-07 1.67E-07 1.17E-07 I-130 2.002E+04 2.11E-04 1.44E-04 7.84E-04 2.157E+04 2.27E-04 1.56E-04 8.44E-04 I-131 2.394E+05 2.35E-02 2.05E-02 1.93E-01 2.691E+05 2.64E-02 2.31E-02 2.17E-01 I-132 3.415E+05 1.19E-03 4.22E-04 5.31E-04 3.861E+05 1.35E-03 4.77E-04 6.01E-04 I-133 4.781E+05 8.47E-03 6.22E-03 5.02E-02 5.243E+05 9.28E-03 6.82E-03 5.50E-02 I-134 5.369E+05 1.21E-03 3.10E-04 1.00E-04 5.804E+05 1.30E-03 3.35E-04 1.09E-04 I-135 4.455E+05 2.52E-03 1.40E-03 5.59E-03 4.932E+05 2.78E-03 1.55E-03 6.19E-03 Xe-129M 9.566E+00 3.29E-08 3.89E-08 1.56E-08 9.744E+00 3.36E-08 3.96E-08 1.59E-08 Xe-131M 2.711E+03 3.43E-06 4.08E-06 1.64E-06 3.029E+03 3.83E-06 4.56E-06 1.83E-06 Xe-133 4.502E+05 2.28E-03 2.63E-03 1.05E-03 5.243E+05 2.65E-03 3.07E-03 1.23E-03 Xe-133M 1.490E+04 6.57E-05 7.15E-05 2.84E-05 1.657E+04 7.31E-05 7.95E-05 3.15E-05 Xe-135 1.573E+05 5.66E-03 3.94E-03 1.43E-03 2.028E+05 7.30E-03 5.08E-03 1.85E-03 Xe-135M 9.684E+04 1.20E-03 2.75E-04 1.35E-05 1.083E+05 1.34E-03 3.08E-04 1.51E-05 Xe-137 4.213E+05 3.64E-03 8.32E-04 1.13E-05 4.590E+05 3.97E-03 9.06E-04 1.23E-05 Xe-138 4.380E+05 1.39E-02 3.19E-03 1.44E-04 4.502E+05 1.43E-02 3.28E-03 1.48E-04 Rb-86 1.048E+03 2.44E-07 2.17E-07 6.91E-07 1.203E+03 2.80E-07 2.49E-07 7.94E-07 to GNRO-2011/ 00050 Page 4 of 7 Table 2: CRDA Dose Consequence -

Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU Bundle Source Bundle Source (1.7 peaking Control (1.7 peaking Control factor) EAB 2 hr LPZ TEDE Room TEDE factor) EAB 2 hr LPZ TEDE Room TEDE (Ci/bundle) TEDE (Rem) (Rem) (Rem) (Ci/bundle) TEDE (Rem) (Rem) (Rem)

Rb-88 2.546E+05 8.27E-07 1.90E-07 3.47E-08 2.241E+05 7.28E-07 1.67E-07 3.06E-08 Rb-89 3.323E+05 2.46E-06 5.62E-07 3.62E-08 2.900E+05 2.14E-06 4.91E-07 3.16E-08 Cs-132 1.140E+02 6.26E-09 5.86E-09 1.38E-08 1.280E+02 7.03E-09 6.58E-09 1.55E-08 Cs-134 1.002E+05 1.65E-04 1.48E-04 4.69E-04 1.453E+05 2.39E-04 2.15E-04 6.80E-04 Cs-134M 2.432E+04 3.59E-08 1.38E-08 2.52E-08 2.729E+04 4.03E-08 1.55E-08 2.83E-08 Cs-136 2.653E+04 7.80E-06 7.20E-06 1.94E-05 3.633E+04 1.07E-05 9.87E-06 2.66E-05 Cs-137 3.544E+04 3.98E-05 3.58E-05 1.15E-04 5.948E+04 6.69E-05 6.01E-05 1.92E-04 Cs-138 4.718E+05 8.14E-06 1.93E-06 2.63E-07 4.942E+05 8.52E-06 2.02E-06 2.76E-07 Total 1.51E-01 7.23E-02 2.62E-01 1.48E-01 7.36E-02 2.91E-01 Weighted Scaling Factor 0.98* 1.02 1.11

• Although the isotope-specific weighting factor approach concludes that the CRDA EAB dose decreases with EPU, EPU LAR Attachment 5 Table 2.9-9, CRDA Radiological Consequences, conservatively assumes no change in dose.

EAB - Exclusion Area Boundary LPZ - Low Population Zone to GNRO-2011/ 00050 Page 5 of 7 Table 3: Pressure Controller Failure Dose Consequence Isotope-Weighted EPU Scaling Factor Pre-EPU EPU Isotope-Specific Control Scaling Factor Control EAB 2 hr LPZ TEDE Room TEDE based on core EAB 2 hr LPZ TEDE Room TEDE TEDE (Rem) (Rem) (Rem) source terms TEDE (Rem) (Rem) (Rem)

Br-82 9.88E-05 2.26E-05 5.87E-04 2.79% 1.02E-04 2.32E-05 6.03E-04 Br-83 5.73E-05 1.31E-05 3.84E-04 9.69% 6.28E-05 1.44E-05 4.21E-04 Kr-83m 4.61E-12 1.05E-12 1.70E-09 9.69% 5.06E-12 1.16E-12 1.86E-09 Br-84 1.17E-03 2.67E-04 1.63E-03 8.28% 1.26E-03 2.89E-04 1.76E-03 Kr-85 1.47E-05 3.37E-06 9.41E-06 3.73% 1.53E-05 3.49E-06 9.76E-06 Kr-85m 2.17E-02 4.97E-03 1.05E-02 -10.03% 1.96E-02 4.47E-03 9.46E-03 Rb-86 7.43E-06 1.70E-06 3.63E-05 5.13% 7.81E-06 1.79E-06 3.81E-05 Kr-87 2.18E-01 4.98E-02 6.57E-02 -4.99% 2.07E-01 4.73E-02 6.24E-02 Rb-87 3.40E-18 7.77E-19 1.04E-14 -4.99% 3.23E-18 7.39E-19 9.87E-15 Kr-88 7.28E-01 1.66E-01 3.09E-01 -0.90% 7.21E-01 1.65E-01 3.06E-01 Rb-88 1.01E-03 2.32E-04 3.29E-01 -0.90% 1.00E-03 2.30E-04 3.26E-01 Rb-89 5.10E-04 1.17E-04 7.57E-05 -0.79% 5.06E-04 1.16E-04 7.51E-05 Sr-89 1.30E-08 2.97E-09 1.26E-05 -0.79% 1.29E-08 2.95E-09 1.25E-05 I-131 1.59E-01 3.64E-02 1.76E+00 13.17% 1.80E-01 4.12E-02 1.99E+00 Xe-131m 6.66E-13 1.52E-13 6.97E-10 13.17% 7.54E-13 1.72E-13 7.89E-10 I-132 1.09E-02 2.48E-03 2.15E-02 13.18% 1.23E-02 2.81E-03 2.43E-02 I-133 5.92E-02 1.35E-02 5.90E-01 14.84% 6.80E-02 1.56E-02 6.77E-01 Xe-133 2.70E-02 6.17E-03 1.70E-02 14.84% 3.10E-02 7.09E-03 1.96E-02 Xe-133m 6.67E-11 1.52E-11 6.42E-08 14.84% 7.66E-11 1.75E-11 7.38E-08 Cs-134 5.82E-03 1.33E-03 2.82E-02 -12.43% 5.10E-03 1.16E-03 2.47E-02 I-134 1.59E-02 3.64E-03 9.50E-03 14.56% 1.83E-02 4.18E-03 1.09E-02 Cs-135 1.27E-13 2.91E-14 7.13E-10 15.02% 1.46E-13 3.34E-14 8.20E-10 I-135 1.86E-02 4.26E-03 1.05E-01 15.02% 2.14E-02 4.90E-03 1.21E-01 Xe-135 8.18E-02 1.87E-02 4.58E-02 15.02% 9.41E-02 2.15E-02 5.26E-02 Xe-135m 7.68E-02 1.76E-02 7.82E-03 15.02% 8.84E-02 2.02E-02 8.99E-03 to GNRO-2011/ 00050 Page 6 of 7 Table 3: Pressure Controller Failure Dose Consequence Isotope-Weighted EPU Scaling Factor Pre-EPU EPU Isotope-Specific Control Scaling Factor Control EAB 2 hr LPZ TEDE Room TEDE based on core EAB 2 hr LPZ TEDE Room TEDE TEDE (Rem) (Rem) (Rem) source terms TEDE (Rem) (Rem) (Rem)

Cs-136 3.07E-04 7.01E-05 1.32E-03 -3.66% 2.95E-04 6.75E-05 1.27E-03 Ba-137m 3.66E-07 8.38E-08 4.77E-06 1.55% 3.72E-07 8.51E-08 4.84E-06 Cs-137 2.04E-03 4.67E-04 9.97E-03 1.55% 2.07E-03 4.74E-04 1.01E-02 Cs-138 1.06E-03 2.43E-04 3.38E-04 13.64% 1.21E-03 2.76E-04 3.84E-04 Xe-138 8.49E-01 1.94E-01 7.98E-02 13.04% 9.60E-01 2.19E-01 9.02E-02 Total 2.28E+00 5.21E-01 3.39E+00 2.43E+00 5.56E-01 3.74E+00 Weighted Scaling Factor 1.07 1.07 1.10 to GNRO-2011/ 00050 Page 7 of 7 RAI # 2 It is the NRC staff's understanding that the current GGNS analyses of record for the radiological dose consequences for design basis accidents is evaluated at a power level of 3910 MWt or lower depending on the accident scenario being evaluated. Please describe what the GGNS analyses of record will consist of for the proposed change at the EPU power level, provided a weighted dose scaling factor was used to calculate the EPU dose results instead of a reanalysis of the current radiological dose analyses for DBAs.

Response

The GGNS radiological analyses are maintained in accordance with 10 CFR 50, Appendix B, Part III. The weighted dose scaling factors have been developed via verified, safety-related calculations under Shaws Quality Assurance program. The reported EPU doses developed with these weighted scaling factors represent the predicted post-EPU doses that would be anticipated if full re-analyses of the affected radiological calculations were performed. Thus, full re-analyses are not required to maintain these calculations updated for design control purposes and GGNS plans to rely on the weighted scaling factor results.