ML18201A202

Orano USA - Application for Amendment No. 4 to Certificate of Compliance No. 1029- Revised Rsi 5-1 Response

ML18201A202
Person / Time
Site:	07201029
Issue date:	07/18/2018
From:	Bondre J Orano USA
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
E-52176, EPID L-2017-LLA-0390
Download: ML18201A202 (7)

Text

{{#Wiki_filter:orano Columbia Office 7135 Minstrel Way Columbia, MD 21045 Tel: (410) 910-6900 @Orano_USA U. S. Nuclear Regulatory Commission Attn: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 July 18, 2018 E-52176

Subject:

Application for Amendment No. 4 to Certificate of Compliance No. 1029-Revised RSI 5-1 Response (Docket 72-1029, EPID No. L-2017-LLA-0390)

Reference:

Letter E-50760 from Jayant Bondre (TN Americas LLC) to U.S. NRC Document Control Desk, "Acceptance Review of TN Americas LLC Application for Amendment No. 4 to Certificate of Compliance No. 1029 -Response to Request for Supplemental Information," dated February 22, 2018 (Docket No. 72-1029) Based on recent communications with the NRC staff, this submittal provides a revised response to the Request for Supplemental Information (RSI) for RSI 5-1 provided originally in Enclosure 2 of the reference document. Changes were made solely to the proprietary designation in the response to RSI 5-1 so that this response is now designated as public in its entirety. Enclosure 1 herein provides the revised response to RSI 5-1. For completeness, the UFSAR changed pages associated with this response (unchanged from those provided in the referenced submittal) are also provided as Enclosure

2. Should NRC staff have any questions or require additional information to support the review of this application, please contact Mr. Dennis Williford by telephone at (704) 805-2223, or by email at Dennnis.Williford@orano.group.

Document Control Desk July 18, 2018 Sincerely, Jayant Bondre Chief Technical Officer cc: Siva Lingam (NRC SFM) as follows, all provided in a separate mailing:

• Six paper copies of this cover letter and Enclosures 1 and 2

Enclosures:

1. RSI and Response -RSI 5-1 2. CoC 1029 Amendment 4 Application RSI 5-1 UFSAR Changed Pages E-52176 Page 2 of 2 Enclosure 1 to E-52176 RSI and Response -RSI 5-1 RSI and Response -RSI 5-1 Enclosure 1 to E-52176 RSI 5-1 Provide calculations, computer input files or other information which justify adding the proposed dose rates to the technical specifications.

The applicant proposed dose rate limits of 50 mrem/hr on the AHSM front inlet bird screen and 10 mrem/hr on the AHSM door outside surface. However, the applicant did not provide information justifying that these dose rates limits are adequate. The applicant should provide all calculations and computer input files which substantiate implementing the proposed dose rate limits. This information is necessary for the staff to evaluate compliance with 1 O CFR 72.236(d). RESPONSE TO RSI 5-1 : The proposed dose rate limits on the advanced horizontal storage module (AHSM) front inlet bird screen and on the AHSM door outside surface are based on shielding analysis results presented in Updated Final Safety Analysis Report (UFSAR) Table 5.1-2 for the 24PT1 dry shielded canister (DSC), and UFSAR Table A.5.1-2 for the 24PT4 DSC. The shielding analysis results for the AHSM door outside surface have been added to UFSAR Table 5.1-2 for the 24PT1 DSC, and UFSAR Table A.5.1-2 for the 24PT4 DSC. The dose rate results shown in UFSAR Tables 5.1-2 and A.5.1-2 indicate that the proposed limits are adequate. The proposed dose rate limit of 50 mrem/hr on the AHSM front inlet bird screen is based on a calculated maximum dose rate of 45.81 mrem/hr for the 24PT1 DSC ,and a calculated maximum dose rate of 45.156 mrem/hr for the 24PT 4 DSC. For the 24PT1 DSC, the dose rate reported in Table 5.1-2 of the UFSAR is obtained from Table 8.3 of Calculation SCE-01.0502 Revision 2. For the 24PT 4 DSC, the dose rate reported in Table A.5.1-2 of the UFSAR is obtained from Table 8-4 of Calculation SCE-23.0502 Revision 0. The proposed dose rate limit of 1 O mrem/hr on the AHSM door outside surface is based on a calculated maximum dose rate of 4.04 mrem/hr for the 24PT1 DSC and a calculated maximum dose rate of 4.453 mrem/hr for the 24PT4 DSC. For the 24PT1 DSC, the dose rate added to Table 5.1-2 of the UFSAR is obtained from Table 81 of Calculation SCE-01.0502 Revision 2. For the 24PT4 DSC, the dose rate added to Table A.5.1-2 of the UFSAR is obtained from Table 8-4 of Calculation SCE-23.0502 Revision 0. Calculation 503821-0500 Revision O was prepared to summarize the above information to support the proposed dose rate limits of 50 mrem/hr on the AHSM front inlet bird screen, and 1 O mrem/hr on the AHSM door outside surface. This calculation also references calculations SCE-01.0502 Revision 2 and SCE-23.0502 Revision 0. Calculations 503821-0500 Revision 0, SCE-01.0502 Revision 2 and SCE-23.0502 Revision O are provided in Enclosures 6 through 8 of this submittal. Computer input files associated with these calculations are provided in Enclosure 10, with a summary listing of these files provided in Enclosure

9. Application Impact: UFSAR Table 5.1-2 and Table A.5.1-2 have been revised as described in the response.

Page 1 of 1 Enclosure 2 to E-52176 Coe 1029 Amendment 4 Application RSI 5-1 UFSAR Changed Pages Advanced NUHOMS Sys tem F inal Safety Analy s i s R eport Rev. 0 , 2/03 (1) (2) (3) Surface Rear (1) Front EJ Roof Side (1> Table 5.1-2 Summary AHSM Dose Rates Dose Rate Maximum Dose Minimum Dose Component Rate, mrem/hr Rate, mrem/hr Gamma 0.11 1.06E-04 Neutron 0.01 3.04E-06 Gamma 45.27 1.59E-02 Neutron 0.54 6.99E-04 Gamma 3.57 3.57E-04 Neutron 0.05 2.37E-05 Gamma 1.35 5.13E-06 Neutron 0.03 4.61E-08 Rear and side does rates are on the outer surfaces of the shield walls. Average Surface Dose Rate(2), mrem/hr 4.06E-03 3.70E-04 1.89 0.04 0.03 8.56E-04 0.26 0.01 These dose rate s are bound in g for 1 met e r occupational exposures during transf e r operations. The maximum dose rates on the front surface are based on the results calculated in front of the entrance of the bottom air inlet. Around the door centerline (between 152 cm to 394 cm above the ground) has ma xi mum dose rate 4.04 m re mlhr(gamma dose rate 3.97 mremlhrand neutron dose rate 0.07 mremlhr). February 20 1 8 Revision 1 72-10 29 Amendment No. 4 All indicated changes are in response to RSI 5-1 5.1-3 I Up d a t ed Adva n ced NUHOMS System F in a l Safe t y Ana l ys i s Repo rt Table A.5.1-2 S um mary of AHSM Dose R ates Dose Rate Dose Rate (mrem/hr) Rev. 2, 08/06 Surface Component Maximum Average Gamma 143.88 1 +/- 15.5o/o (a) Rear End of t h e Neutron 0.2 0 7 +/- 4.3% N/A TSBA tbl Total 144.088 +/- 15.5% Gamma 1.1 15 +/- 4.2% 0.085 +/- 3.3% Back of the Rear Neutron 0.008 +/- 1.4% l .05E-3 +/- 1.6% Shield Wa l f bJ Total 1.123 +/- 4.1% 0.086 +/- 3.3% Gamma 44.3 1 8 +/- 5.3% 2.154 +/- 2.9% Front<cl Neutron 0.838 +/- 1.1% 0.138 +/- 7.7% Total 45.1 56 +/- 5.2% 2.292 +/- 2.8% Gamma 149.298 +/- 4.5% 0.011 +/- 2.7% Roof d) Ne u tron 0.279 +/- 1.6% 0.00 1 +/- 7.5% Total 149.577 +/- 4.5% 0.012 +/- 2.6% Gamma 6.657 +/- 6.8% 0.474 +/- 5.6% AHSM Top 1 e J Ne u tron 0.0 1 6 +/- 1.8% 1.56£-3 +/- 1.5% Total 6.673 +/- 6.8% 0.476 +/- 5.6% Gamma 1.790 +/- 3.3% 0.309 +/- 2.0% Side Ne u tron 0.074 +/- 3.6% 1.06E-3 +/- 1.4% Tota l 1.865 +/- 3.1% 0.319 +/- 1.9% (a) Statistica l o n e standard deviation uncerta i nty in the Mo n te Car l o ca l culation. (b) T h e maxi mum gamma dose rates on the r e ar concrete s UJ face (of"top" model) but be l ow the roof elevation are less than 0.2 mrem/hr a n d the maxim u m gamma dose rates on th i s surface above the roof l evel a r e about 1.1 2 mrem/hr; i.e., the dose rate above the roof drops off very rap i dly wit h distance in x from the vent (note the dose rate near t h e edge of the vent i s 144.1 mrem/hr). (c) These max imu m dose rates on the front oft~..cu:l..:ll:t1..J;1J..w..wi::..s.1J...1.LLLWJ;i.J..W.:U.w.;:,...l.-'ll.l,.U~1..1.1.,µ.i.;,.L.JJ.. L-.., front of the e n trance of t h e bottom a i r in l et. Th e ma..,imum dos e rate around th e door i s 4.453 mrem l hr (gamma dose rate 3.909 mr e m!hr and n e utron dos e rate 0.544 mrem!h,)from th e "lop" MC N P mod e l as shown in Figur e A.5.4-3. (d) The dose rates are calc ul ated on top of the AHSM roof. The maxi m um dose rates on t h e roof are based o n the dose rates ju s t at t h e roof ve n t open in g. Knowi n g dose rates just above the roof vent opening is important , since this area must be accessed to c l ean the vent screens , if deb ri s accu m u l ates on t h e screens. For dose rates in front of the Top Shield Block Asse m bl y (TSBA), the " Roof' max i mum dose rate is b e l ow 1.0 mrem/hr. T h e average dose rates are calcu l ated over the roof segment in front of t h e TSBA (before its -x side). (e) The dose rates are calc ul ated on t h e plane enveloping the AHSM from the top. The average dose rate is ca l cu l ated over the ent i re plane enve l oping t h e AHSM from the top. This dose rate is u sed for t h e site dose rate analys i s. The l ocation of t h e maxim um dose rate i s near t h e rear end of the TSBA (its +x s i de , the side facing rear of the AHSM). Note: Gamma res ul ts include t h e dose rates from gammas produced from neutron s in the neutron calcu l at i on. These p artial gamma dose ra t es and t h e n eutron dose rates have bee n m ultiplied by [1 /( l-k)=l/(1-0.45) =1.82] to co n servat i ve l y include neutro n m ul tiplication from i n d u ced fissions in the source region con t aining dama g ed fue l rod s. Note: The averaged d ose rates are calc ul ated over t h e planes envelopi n g the AHSM geometry , whi l e peak dose rates a r e fo r l oca li zed areas. T h e average dose rates are needed for the site dose rate anal y sis. F e bruary 201 8 R e vi s ion 1 72-10 2 9 Am e ndm e nt No. 4 All indicated changes are in response to RSI 5-1 A.5.1-5}}