ML20108E927

NRC-2020-000169 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed. Part 7 of 9

ML20108E927
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Issue date:	04/15/2020
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I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.l MAXIMUM REACTIVITIES WITH REDUCED EXTERNAL WATER DENSITIES Water Density Maximum kerr MPC-37 MPC-89 Internal External (17x17B, 5.0%)

(lOxlOA, 4.8%)

100%

100%

0.9380 0.9435 100%

70%

0.9377 0.9432 100%

50%

0.9399 0.9439 100%

20%

0.9366 0.9428 100%

10%

0.9374 0.9437 100%

5%

0.9376 0.9435 100%

1%

0.9383 0.9435 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-56 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.2 REACTIVITY EFFECTS OF PARTIAL CASK FLOODING MPC-37 (17xl 7B, 5.0% ENRICHMENT)

Flooded Condition Maximum kerr, Maximum kerr,

(% Full)

Vertical Orientation Horizontal Orientation 25 0.9175 0.8306 50 0.9325 0.9093 75 0.9357 0.9349 100 0.9380 0.9380 MPC-89 (lOxlOA, 4.8% ENRICHMENT)

Flooded Condition Maximum kcrr, Maximum kccr,

(% Full)

Vertical Orientation Horizontal Orientation 25 0.9204 0.8345 50 0.9382 0.9128 75 0.9416 0.9392 100 0.9435 0.9435 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6-57 Rev. 5

I IOLTEC PROPRIETARY INFORMATIOl<l TABLE 6.4.3 REACTIVITY EFFECT OF FLOODING THE PELLET-TO-CLAD GAP Pellet-to-Clad Maximum kerr Condition MPC-37 (l 7xl 7B, MPC-89 (l OxlOA, 5.0%

4.8%

ENRICHMENT)

ENRICHMENT) dry 0.9335 0.9391 flooded with unborated water 0.9380 0.9435 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-58 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

AOL I EC PROPRIE I ARV INFORMATION TABLE 6.4.4 REACTIVITY EFFECT OF PREFERENTIAL FLOODING OF THE DFCs Maximum k eff DFC Configuration Preferential Fully Flooded Flooding MPC-37 with 12 DFCs 0.8705 0.9276 (5% Enrichment, Undamaged assembly l5x15F, 20x20 Bare Rod An-ay)

MPC-89 with 16 DFCs 0.8296 0.9464

( 4.8 % Enrichment, Undamaged assembly lOxlOA, 9x9 Bare Rod AtTay)

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-59 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

Internal Water Densityt I

3 mgcm Guide Tubes 1.00 0.99 0.98 0.97 0.96 0.95 0.94 0.93 0.92 0.91 0.90 0.85 0.80 0.70 0.60 0.40 0.20 0.10 HObTEC PROPRIETARY INFORMATION TABLE 6.4.5 MAXIMUM kctr VALUES WITH REDUCED WATER DENSITIES Maximum kerr MPC-89 MPC-37 MPC-37

lOxlOA, (1500ppm)

(2000ppm) 4.8%

17xl 7B, 4.0 %

17xl 7B, 5.0 %

NIA filled void fi lied void 0.9435 0.9181 0.9071 0.9380 0.9292 0.9415 0.91 81 0.9059 0.9367 0.9296 0.9391 0.9162 0.9054 0.9368 0.9279 0.9370 0.9166 0.9035 0.9364 0.9272 0.9345 0.9147 0.9005 0.9360 0.9265 0.9304 0.9148 0.9010 0.9356 0.9243 0.9280 0.9133 0.8995 0.9335 0.9238 0.9259 0.9128 0.8986 0.9355 0.9237 0.9232 0.9120 0.8955 0.9327 0.9203 0.9 183 0.9105 0.8947 0.9335 0.9208 0.9 169 0.9090 0.8934 0.9303 0.9189 0.9013 0.9042 0.8840 0.9272 0.9 109 0.8850 0.8973 0.8733 0.9222 0.9022 0.8462 0.8813 0.8477 0.9068 0.8780 0.7980 0.8565 0.8132 0.8866 0.8478 0.6762 0.7876 0.7195 0.8244 0.7585 0.5268 0.6827 0.5806 0.7284 0.6298 0.4649 0.6206 0.5112 0.6698 0.5639 t External moderator is modeled at I 00%.

t With undamaged and damaged fuel. All other cases with undamaged fuel only MPC-37t (2300ppm) 15x15F and Damaged Fuel 5.0%

filled void 0.9276 0.9265 0.9271 0.9264 0.9271 0.9257 0.9265 0.9242 0.9265 0.9232 0.9253 0.9217 0.9255 0.9225 0.9263 0.9214 0.9237 0.9204 0.9229 0.9194 0.9226 0.9169 0.9190 0.9127 0.9138 0.9040 0.9000 0.8851 0.8806 0.8571 0.8192 0.7735 0.7237 0.6517 0.6669 0.5889 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-60 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.6 MAXIMUM keff' VALUES IN THE MPC-3 7 WITH UNDAMAGED ( l 5x l 5F)

AND DAMAGED FUEL Bare Rod Array inside the DFC Maximum ketT, Maximum kctT, 4.0 wt%

5.0 wt%

8x8 0.8883 0.9122 lOxlO 0.8899 0.9135 12x12 0.8910 0.9152 14x14 0.8945 0.9177 15xl5 0.8966 0.9198 16x16 0.8982 0.9224 17xl7 0.9003 0.9238 18xl8 0.9027 0.9262 20x20 0.9032 0.9276 22x22 0.9023 0.926 24x24 0.9008 0.9239 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-61 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.7 MAXIMUM kerr VALUES IN THE MPC-89 WITH UNDAMAGED ( 1 Ox 1 OA)

AND DAMAGED FUEL Bare Rod Array inside the DFC Maximum keff, 4.8 wt% (planar average) 4x4 0.9389 6x6 0.9411 8x8 0.9432 9x9 0.9464 lOxlO 0.9454 1 lxll 0.9451 12xl2 0.9460 13xl3 0.9453 14xl4 0.9444 16xl6 0.9429 18xl8 0.9423 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-62 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.8 MAXIMUM kcrr VALUES IN THE MPC-89 WITH LOW ENRICHED (3.3 wt% 235U), CHANNELED, BWR FUEL Rod Array inside the Channel Maximum kcrr 4x4 0.4018 6x6 0.7320 8x8 0.8999 9x9 0.9294 lOx lO 0.9325 1 lxll 0.9131 12x12 0.8762 13xl3 0.8237 14x l4 0.7606 16xl6 0.6664 18xl8 0.6334 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-63 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION TABLE 6.4.9 COMPARISON OF MCNP CONVERGENCE PARAMETERS Calculation Maximum kcrr Parameters Particles Skipped MPC-37 (l 7xl 7B, MPC-89 (lOxlOA, per Cycle Cycles 5.0%

4.8%

ENRICHMENT)

ENRICHMENT) 20,000 20 0.9380 0.9435 50,000 20 0.9376 0.9428 20,000 100 0.9387 0.9436 50,000 100 0.9379 0.9434 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-64 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEG PROPRle+,ARY lf)IFORMAJIQN TABLE 6.4.10 COMPARISON OF MAXIMUM kefT VALUES FOR EACH ASSEMBLY CLASS IN THE MPC-37 WITH CONDITIONS OF FILLED AND VOIDED GUIDE AND INSTRUMENT TUBES AT 5 % ENRICHMENT Fuel Assembly Class Maximum kerr, Maximum kerr, Filled Tubes Voided Tubes 14xl4A 0.8983 0.8887 14xl4B 0.9282 0.9148 14xl4C 0.9275 0.9277 15x15B 0.9311 0.9251 I5xl5C 0.9188 0.9134 l5x15D 0.9421 0.9379 15xl5E 0.9410 0.9365 15xl5F 0.9455 0.9404 15xl5H 0.9325 0.9317 l5xl5I 0.9357 0.9362 16xl6A 0.9366 0.9320 16xl6A[DFC]

0.9400 0.9404 16xl6B 0.9334 0.9301 16xl6C 0.9187 0.9015 17xl7A 0.9194 0.9135 17xl7B 0.9380 0.9292 17xl 7C 0.9424 0.9345 l 7xl7D 0.9384 0.9293 l 7xl 7E 0.9392 0.9314 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-65 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

HOLTEC F'ROF'RIETARt' IMFORMATIOl<I Figure 6.4. 1: Calculational Model (planar cross-section) of a DFC in a MPC-37 cell with a 14x14 array of bare fuel rods HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 6-66 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

1 IOLTEC PROPRIETARY INFORMATlmJ 6.5 CRITICALITY BENCHMARK EXPERIMENTS Benchmark calculations have been made on selected critical experiments, chosen, insofar as possible, to bound the range of variable in the cask designs. The most important parameters are (1) the emichment, (2) cell spacing, and (3) the 10B loading of the neutron absorber panels. Other parameters, within the normal range of cask and fuel designs, have a smaller effect, but are also included. No significant trends were evident in the benchmark calculations or the derived bias.

Detailed benchmark calculations are presented in Appendix 6.A.

The benchmark calculations were performed with the same computer codes and cross-section data, described in Section 6.4, that were used to calculate the kcff values for the cask. Further, all calculations were performed on the same computer hardware (personal computers).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-67 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 6.6 REGULATORY COMPLIANCE This section documents the criticality evaluation of the HI-STORM FW system for the storage of spent nuclear fuel. This evaluation demonstrates that the HI-STORM FW system is in full compliance with the criticality requirements of 10CFR72 and NUREG-1536.

Structures, systems, and components important to criticality safety, as well as the limiting fuel characteristics, are described in sufficient detail in this section to enable an evaluation of their effectiveness.

The HJ-STORM FW system is designed to be subcritical under all credible conditions. The criticality design is based on favorable geometry and fixed neutron poisons. An appraisal of the fixed neutron poison has shown that they will remain effective for a storage period greater than 60 years, and there is no credible way to lose it; therefore, there is no need to provide a positive means to verify their continued efficacy as required by 10CFR72.124(b).

The criticality evaluation has demonstrated that the cask will enable the storage of spent fuel for a minimum of 60 years with an adequate margin of safety. Fut1her, the evaluation has demonstrated that the design basis accidents have no adverse effect on the design parameters important to criticality safety, and therefore, the HI-STORM FW system is in full compliance with the double contingency requirements of 1 OCRF72.124. Therefore, it is concluded that the criticality design features for the HI-STORM FW system are in compliance with 10 CFR Part 72 and that the applicable design and acceptance criteria have been satisfied. The criticality evaluation provides reasonable assurance that the HI-STORM FW system will allow safe storage of spent fuel.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-68 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

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i-!OLTEC PROPRIETARY INFORMATION

6.7 REFERENCES

[6.0.l]

HI-STORM 100 FSAR, NRC Docket 72-1014, Holtec Report HI-2002444, Latest rev1s1on

[6.0.2]

[6.1.l]

[6.1.2]

[ 6.1.3]

[6.1.4]

[6.1.5]

[6.1.6]

[6.4.1]

"Criticality Analyses for the HI-STORM FW System", Holtec Report HI-2094432 Rev.6 (proprietary)

NUREG-1536, Standard Review Plan for Dry Cask Storage Systems, USNRC, Washington, D.C., January 1997.

1 OCFR 72.124, "Criteria For Nuclear Criticality Safety."

not used "MCNP - A General Monte Carlo N-Pa11icle Transport Code, Version 5"; Los Alamos National Laboratory, LA-UR-03-1987 (2003).

M.G. Natrella, Experimental Statistics, National Bmeau of Standards, Handbook 91, August 1963.

"CASM0-4 Methodology", Studsvik/SOA-95/2, Rev. 0, 1995.

"CASM0-4 A Fuel Assembly Burnup Program, Users Manual," SSP-01/400, Rev. 1, Studsvik Scandpower, Inc., 2001.

"CASM0-4 Benchmark Against Critical Experiments", Studsvik/SOA-94/13, Studsvik of America, 1995.

J.M. Cano, R. Caro, and J.M Martinez-Val, "Supercriticality Through Optimum Moderation in Nuclear Fuel Storage," Nucl. Technol., 48, 251-260, (1980).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6-69 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEO PROPRIEfAR¥-fNFeRMATION APPENDIX 6.A: BENCHMARK CALCULATIONS (b)(4)

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-1 Rev. 5

(h)(4)

-#ObTI?C PROPRIETARY l~IF9RMMteN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-2 Rev. 5

(b)(4)

I fOLTEG PROPRIETARY INFORMA+IQN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-3 Rev. 5

(b}(4)

-H6LTEO PROPRIE'fAR¥-iNFeRMMteN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-4 Rev. 5

~TEC PROPRlCTARV INFeRMAl'IO~

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-5 Rev. 5

(b)(4)

REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 HOtTEC PROPRIETARY IMFORMATION HOLTEC rNTERNATIONAL COPYRIGHTED MATERIAL 6.A-6 Rev. 5

lb)(4)

REPORT Hl-2 11 4830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 HOLTEC PROPRIETARY ltffORMATlot~

HOLTEC rNTERNATIONAL COPYRIGHTED MATERIAL 6.A-7 Rev. 5

(b)(4)

REPORT HJ-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 HObTEC PROPRIETARY INFORWrrteN HOLTEC rNTERNATIONAL COPYRIGHTED MATERIAL 6.A-8 Rev. 5

(b) !4)

REPORT Hl-2 11 4830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 HOLTEC PROPRIETARY INFORMATION HOLTEC rNTERNATIONAL COPYRIGHTED MATERIAL 6.A-9 Rev. 5

(b)(4)

REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 HOLTEC PROPRIETARY INFORMATIOt4 HOLTEC rNTERNATIONAL COPYRIGHTED MATERIAL 6.A-JO Rev. 5

-HOLTEO PROPRIEfAR¥-tNFeRMMteN-(b}(4) 6 EALF is the energy of the average lethargy causing fission HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-11 Rev. 5

(IJ)(4)

I IOLTEG PROPRIETARY INFORMA+IQN.

7 Arranged in order of increasing reflector fuel spacing.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-12 Rev. 5

I fOLTEG PROPRIEfAR¥-iNFeRMMteN-(b)(4)

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2 114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-13 Rev. 5

(b)(4)

-HObTl?C PROPRIETARY INFeRMMteN-HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-14 Rev. 5

(b)(4)

HObTEC PROPRIETARY INEORMAIION HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.A-15 Rev. 5

1 IOLTEC PROPRIETARY INFORMATlmJ APPENDIX 6.B: MISCELLANEOUS INFORMATION 6.B.1 Sample Input File MPC-37 6.B.2 Sample Input File MPC-89 6.B.3 Analyzed Distributed Enrichment Patterns for Higher Enrichments 6.B.4 Assembly Cross Sections HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 6.B-1 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRleTARY INFORMATION 6.B.1 Sample Input File MPC-37 (b}(4}

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 6.B-2 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

(h)(4)

I fOLTEG PROPRIEfAR¥-fNFeRMMteN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-3 Rev. 5

(b)(4)

HOI TEC PROPRIETARY INFORM,!\\TION-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-4 Rev. 5

(b)(4)

-HObTeC PROPRIETARY l~IFeRMMteN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 6.B-5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

(h)(4)

-H9LTEO PROPRIEfAR¥-iNFeRMMt9N-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT HI-2114830 6.B-6 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HOLTeC PROPRIETARY l~IFeRMMteN-(b)(4)

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-7 I

Rev. 5

(b)(4)

--H6cTEC PROPRIETARY INFORMATION HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 6.B-8 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

1 IOLTEG PROPRIETARY INl=ORMA+IOO-(h)(4)

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 6.B-9 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

(ti)f'1)

I IOLTEG PROPRIETAR¥-iNFeRMMteN-HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 6.B-10 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

(b)(4)

I fOLTEC PROPRli;TARY INFORMAIIQN HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-1 l Rev. 5

(b)(4) 1 IOLTEG PROPRIETAR¥-iNFeRMATteN-HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT Hl-2114830 6.B-12 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

(b)(4)

--1,!0bTeC PROPRIETARY l~lF0RMAft0N-6.B.3 Analyzed Distributed Enrichment Patterns HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-13 Rev. 5

--MOLTEC PROPRICT,';RV INFeRMATIO~

6.B.4 Assemblv Cross Sections (b)(4)

HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-14 Rev. 5

(b)(4)

I IOLTEC PROPRIETARY INFORMATIOt<l HOLTEC INTERNATIONAL COPYRJGHTED MATERIAL REPORT Hl-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 6.B-15 Rev. 5

I IOLTEC PROPRIETARY INFORMATIOl<l CHAPTER 7*: CONFINEMENT

7.0 INTRODUCTION

Confinement of all radioactive materials in the HI-STORM FW system is provided by the MPC.

The design of the HJ-STORM FW MPC assures that there are no credible design basis events that would result in a radiological release to the environment. The HI-STORM FW overpack and HI-TRAC VW transfer cask are designed to provide physical protection to the MPC during nonnal, off-normal, and postulated accident conditions to assure that the integrity of the MPC is maintained. The dry inert atmosphere in the MPC and the passive heat removal capabilities of the HI-STORM FW also assure that the SNF assemblies remain protected from long-term degradation.

A detailed description of the confinement structures, systems, and components important to safety is provided in Chapter 2. The structural adequacy of the MPC is demonstrated by the analyses documented in Chapter 3. The physical protection of the MPC provided by the overpack and the HI-TRAC Transfer Cask is demonstrated by the structural analyses documented in Chapter 3 for off-normal and postulated accident conditions that are considered in Chapter 11. The heat removal capabilities of the HI-STORM FW system are demonstrated by the thermal analyses documented in Chapter 4. Materials evaluation in Chapter 8 demonstrates the compatibility and durability of the MPC materials for long term spent fuel storage.

This chapter describes the HI-STORM FW confinement design and describes how the design satisfies the confinement requirements of 10CFR72 [7.0.1]. It also provides an evaluation of the MPC confinement boundary as it relates to the criteria contained in Interim Staff Guidance (ISG)- 18 [7.0.2] and applicable po1tions of ANSI N 14.5-1997 [7.0.3] as justification for reaching the determination that leakage from the confinement boundary is not credible and, therefore, a quantification of the consequence of leakage from the MPC is not required. This chapter is in general compliance with NUREG-1536 [7.0.4] as noted in Chapter 1.

It should be observed that the configuration of the confinement boundary of the MPCs covered by this FSAR is identical to that used in the MPCs in Docket No. 72-1014 (HI-STORM 100 system), including weld joint details and weld types and weld sizes. Therefore, it is reasonable to conclude that the safety evaluation conducted to establis.h confinement integrity in Docket No.

72-1014 is also applicable herein.

• This chapter has been prepared in the format and section organization set forth in Regulatory Guide 3.6 l. However, the material content of this chapter also fulfil Is the requirements ofNUREG-1536.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-1 Rev. 4

lelObTi;C PROPRIETARY INFORMATION 7.1 CONFINEMENT DESIGN CHARACTERISTICS The confinement against the release of radioactive contents is the all welded MPC. There are no bolted closures or mechanical seals in the MPC confinement boundary.

The confinement boundary of the MPC consists of the following parts:

MPC shell MPC base plate MPC lid MPC vent and drain port covers MPC closure ring associated welds The combination of the welded MPC lid and the welded closure ring form the redundant closure of the MPC and satisfies the requirements of 10 CFR 72.236( e) [7.0.1]. The confinement boundary is shown in the licensing drawing package in Section 1.5. Chapter 2 provides design criteria for the confinement boundary. All components of the confinement boundary are important-to-safety, as specified on the licensing drawings. The MPC confinement boundary is designed, fabricated, inspected and tested in accordance with the applicable requirements of ASME Code,Section III, Subsection NB [7.1.1], with alternatives given in Chapter 2.

7.1.1 Confinement Vessel The HI-STORM FW system confinement vessel is the MPC. The MPC is designed to provide confinement of all radionuclides under nonnal, off-normal and accident conditions. The three major components of the MPC vessel are the shell, baseplate, and lid. The shell welds and the shell to baseplate weld are performed at the fabrication facility. The remaining confinement boundary welds are performed in the field (Table 7.1.1 ).

The MPC lid consists of two sections (referred to as upper and lower) welded together. Only the upper portion of the lid is credited in the confinement boundary. The lid is made intentionally thick by the addition of the lower portion of the lid to minimize radiation exposure to workers during MPC closure operations. The MPC lid has a stepped recess around the perimeter for accommodating the closure ring. The MPC closure ring is welded to the MPC lid on the inner diameter of the ring and to the MPC shell on the outer diameter.

Following fuel loading and MPC lid welding, the MPC lid-to-shell weld is examined by progressive liquid penetrant examinations (a multi-layer liquid penetrant examination), and a pressure test is performed. The MPC lid-to shell weld is not helium leakage tested since the weld meets the guidance of NRC Interim Staff Guidance (ISG)-15 [7.1.2] and criteria of ISG-18

[7.0.2], therefore leakage from the MPC lid-to-shell weld is not considered credible. Table 7.1.2 provides the matrix of ISG-18 criteria and how the Holtec MPC design and associated inspection, testing, and QA requirements meet each one.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 4 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-2

HObTEC PROPRIETARY INEORMATIQN After the MPC lid weld is ensured to be acceptable the vent and drain port cover plates are welded in place, examined by the liquid penetrant method and a helium leakage test of each of the vent and drain port cover plate welds is performed. These welds are tested in accordance to the leakage test methods and procedures of ANSI N 14.5 [7.0.3] to the "leaktight" criterion of the standard. Finally, the MPC closure ring which also covers the vent and drain cover plates is installed, welded, and inspected by the liquid penetrant method. Chapters 9, 10, and 13 provide procedural guidance, acceptance criteria, and operating controls, respectively, for perfom1ance and acceptance of non-destructive examination of all welds made in the field.

After moisture removal and prior to sealing the MPC vent and drain ports, the MPC cavity is backfilled with helium. The helium backfill provides an inert, non-reactive atmosphere within the MPC cavity that precludes oxidation and hydride attack on the SNF cladding. Use of a helium atmosphere within the MPC contributes to the long-term integrity of the fuel cladding, reducing the potential for release of fission gas or other radioactive products to the MPC cavity.

Heliwn also aids in heat transfer within the MPC and helps reduce the fuel cladding temperatures. The inert atmosphere in the MPC, in conjunction with the thermal design features of the MPC and storage cask, assures that the fuel assemblies are sufficiently protected against degradation, which might otherwise lead to gross cladding ruptures during long-term storage.

The confinement boundary welds completed at the fabrication facility (i.e., the MPC longitudinal and circumferential shell welds and the MPC shell to baseplate weld) are referred to as the shop welds. After visual and liquid penetrant examinations, the shop welds are volumetrically inspected by radiography. The MPC shop welds are multiple-pass (6 to 8 passes) austenitic stainless steel welds. Helium leakage testing of the shop welds is performed as described in Table 10.1.1.

7.1.2 Confinement Penetrations Two penetrations (the MPC vent and drain ports) are provided in the MPC lid for MPC draining, moisture removal and backfilling during MPC loading operations, and also for MPC re-flooding during unloading operations. No other confinement penetrations exist in the MPC.

The MPC vent and drain ports are sealed by cover plates that are integrally welded to the MPC lid. No credit is taken for the sealing action provided by the vent and drain port cap joints. The MPC closure ring covers the vent and drain port cover plate welds and the MPC lid-to-shell weld, providing the redundant closure of these penetrations. The redundant closure of the MPC satisfies the requirements of 10CFR72.236(e) [7.0.1].

7.1.3 Seals and Welds Section 7.1. l describes the design of the confinement boundary welds. The welds forming the confinement boundary is summarized in Table 7.1.1.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-3 Rev. 4

I IOLTEC PROPRIETARY INFORMATION The use of multi-pass welds with surface liquid penetrant inspection of root, intermediate, and final passes renders the potential of a leak path through the weld between the MPC lid and the shell to be non-credible. The vent and drain port cover plate welds are helium leak tested in the field, providing added assurance of weld integrity. Additionally after fuel loading, a Code pressure test is performed on the MPC lid-to-shell weld to confirm the structural integrity of the weld.

The ductile stainless steel material used for the MPC confinement boundary is not susceptible to delamination or other failure modes such as hydrogen-induced weld degradation. The closure weld redundancy assures that failure of any single MPC confinement boundary closure weld will not result in release of radioactive material to the environment. Section 10.1 provides a summary of the closure weld examinations and tests.

7.1.4 Closure The MPC is an integrally welded pressure vessel without any unique or special closure devices.

All closure welds are examined using the liquid penetrant technique to ensure their integrity.

Additionally, the vent and drain port cover plate welds are each helium leakage tested to be "leaktight" in accordance with the leakage test methods and procedures of ANSI N14.5-l997

[7.0.3]. Since the MPC uses an entirely welded redundant closure system with no credible leakage, no direct monitoring of the closure is required.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-4 Rev. 4

I IOLTEC PROPRIETARY INFORMATION Table 7.1.1 MPC CONFINEMENT BOUNDARY WELDS ASMECode MPC Weld Location Weld Typet Category (Section III, Subsection NB)

Shell longitudinal seam Full Penetration Groove A

(shop weld)

Shell circumferential seam Full Penetration Groove B

(shop weld)

Baseplate to shell Full Penetration Groove C

(shop weld)

MPC lid to shell Partial Penetration Groove C

(field weld)

MPC closure ring to shell Fillet n

(field weld)

Vent and drain port covers to Partial Penetration Groove D

MPC lid (field weld)

MPC closure ring to MPC lid Partial Penetration Groove C

(field weld)

MPC closure ring to closure ring Partial Penetration Groove tt radial weld (field weld) tt The tests and inspections for the Confinement Boundary welds are listed in Section I 0. 1 This joint is governed by NB-5271 (liquid penetrant examination).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-5 Rev. 4

lelObTi;C PROPRIETARY INFORMATION Table 7. l.2 COMPARISON OF HOLTEC MPC DESIGN WITH ISG-18 GUIDANCE DESIGN/QUALIFICATION GUIDANCE HOL TEC MPC DESIGN The canister is constrncted from austenitic The MPC enclosure vessel is constructed entirely stainless steel.

from austenitic stainless steel (Alloy X). Alloy X is defined as Type 304, 304LN, 316, or 3 I 6LN material.

The canister closure welds meet the guidance of The MPC lid-to-shell closure weld meets ISG-15, ISG-J 5 ( or approved alternative),Section X.5.2.3.

Section X.5.2.3 for austenitic stainless steels. UT examination is permitted and NB-5332 acceptance criteria are required. An optional multi-layer PT examination is also permitted. The multi-layer PT is performed at each approximately 3/8" of weld depth, which corresponds to the critical flaw size.

The canister maintains its confinement integrity The MPC is shown by analysis to maintain during normal conditions, anticipated confinement integrity for all normal, off-normal, occurrences, and credible accidents and natural and accident conditions, including natural phenomena as required in IOCFR72.

phenomena. The MPC is designed to ensure that the Confinement Boundary will not leak during any credible accident event and under the non-mechanistic tip-over scenario.

Records documenting the fabrication and closure Records documenting the fabrication and closure welding of canisters shall comply with the welding of MPCs meet the requirements of ISG-provisions 10CFR72. l 74 and lSG-15. Record 15 via controls required by the FSAR and Hl-storage shall comply with ANSI N45.2.9.

STORM FW CoC. Compliance with 10CFR72.l 74 and ANSI N.45.2.9 is achieved via Holtec QA program and implementing procedures.

Activities related to inspection, evaluation, The NRC has approved Holtec's Quality documentation of fabrication, and closure welding Assurance program under I OCFR 71. That same of canisters shall be performed in accordance with QA program has been adopted for activities an NRC-approved quality assurance program.

governed by 10CFR72 as permitted by IO CFR 72.140(d)

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 4 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-6

HOLTEC f9RO~RIETARY lt~FORMATION 7.2 REQUIREMENTS FOR NORMAL AND OFF-NORMAL CONDITIONS OF STORAGE Once sealed and transferred into the HI-STORM FW overpack there is no mechanism under no1mal and off-normal conditions of storage for the confinement boundary to be breached.

Chapter 3 shows that all confinement boundary components are maintained within their Code-allowable stress limits during normal and off-normal storage conditions. Chapter 4 shows that the peak confinement boundary component temperatures and pressures are within the design basis limits for all normal and off-normal conditions of storage. Since the MPC confinement vessel remains intact, the design temperatures and pressure are not exceeded, and leakage from the MPC confinement boundary as discussed in Section 7.1 is not credible, there can be no release of radioactive material during normal and off-normal conditions of storage.

The MPC is dried and helium backfilled prior to sealing and no significant moisture or other gases remain inside the MPC. Therefore, a credible mechanism for any radiolytic decomposition that could cause an increase in the MPC internal pressure is absent. The potential for an explosive level of gases due to the radiological decomposition in the MPC is eliminated by excluding foreign materials in the MPC or by evaluating foreign material to demonstrate the effect on the MPC internal pressure is negligible.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-7 Rev. 4

AOL I EC PROPRIETARY ll~FORMATION 7.3 CONFINEMENT REQUIREMENTS FOR HYPOTHETICAL ACCIDENT CONDITIONS The analysis in Chapter 3 and results discussed in Chapter 12 demonstrates that the MPC remains intact dtu-ing and after all postulated accident conditions; therefore there can be no release of radioactive material causing any additional dose contribution to the site boundary during these events.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-8 Rev. 4

I IOLTEC PROPRIETARY INFORMATION

7.4 REFERENCES

[7.0.1]

10CFR72, Code of Federal Regulations, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor Related Greater than Class C Waste," USNRC, Washington, DC.

[7.0.2]

Interim Staff Guidance-18, "The Design/Qualification of Final Closure Welds on Austenitic Stainless Steel Canisters as Confinement Boundary for Spent Fuel Storage and Containment Boundary for Spent Fuel Transportation," USNRC, Washington, DC, May 2003.

[7.0.3]

ANSI Nl4.5-1997, "American National Standard for Radioactive Materials -

Leakage Tests on Packages for Shipment," American National Standards Institute, Washington, DC, 1997.

[7.0.4]

NUREG-1536, "Standard Review Plan for Dry Cask Storage Systems", USNRC, Washington, DC, January, 1997.

[7.1.1]

ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, Class 1 Components, American Society of Mechanical Engineers, New York, NY, 2007 Edition.

[7.1.2]

Interim Staff Gui.dance-15, "Materials Evaluation", USNRC, Washington, DC, January 2001.

[7.1.3]

Holtec Proprietary Report HI-2022850, Revision 0, "Summary Report on MPC Leak Tightness Test", April 2002.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 7-9 Rev. 4

HOLTEC PRO~RIETARY lt~FORMATION CHAPTER 8: MATERIAL EVALUATION

8.1 INTRODUCTION

This chapter presents an assessment of the materials selected for use in the HI-STORM FW System components identified in the licensing drawings in Section 1.5. In this chapter and Chapter 3 of this FSAR, the significant mechanical, thermal, radiological and metallurgical properties of materials identified for use in the components of the HI-STORM FW System are presented. This chapter focuses on the HI-STORM FW material properties to assess compliance with the ISG-15 [8.1.1] and ISG-11 [8.1.2] requirements. The principal purpose ofISG-15 is to evaluate the dry cask storage system to ensure adequate material pe1formance of the independent spent fuel storage installation (ISFSI) components designated as important to safety under normal, off-normal and accident conditions. Some areas of review applicable to the suitability assessment of the materials have been addressed elsewhere in this FSAR and are referenced from this chapter as necessary. Areas that require further details are reviewed within this chapter as necessary to satisfy the requirements of ISG-15. Guidance on performing the review is adopted directly from ISG-15 and ISG-11.

ISG-15 sets down the following general acceptance criteria for material evaluation.

The safety analysis report should describe all materials used for dry spent fuel storage components designated as important to safety, and should consider the suitability of those materials for their intended functions in sufficient detail to evaluate their effectiveness in relation to all safety functions.

The dry spent fuel storage system should employ materials that are compatible with wet and dry spent fuel loading and unloading operations and facilities. These materials should not degrade to the extent that a safety concern is created.

The information compiled in this chapter addresses the above acceptance criteria. To perform the material suitability evaluation, it is necessary to characterize the following for each component:

(i) the applicable environment, (ii) the potential degradation modes and (iii) the potential hazards to continued effectiveness of the selected material.

The operating environments. of the different components of the cask system are not the same.

Likewise, the potential degradation modes and hazards are different for each component. Tables 8.1.1, 8.1.2, and 8.1.3 provide a summary of the environmental states, potential degradation modes and hazards applicable to the MPC, the HI-STORM FW overpack and the HI-TRAC VW cask, respectively. The above referenced tables serve to guide the material suitability evaluation for the HI-STORM FW System.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-1 Rev. 5

lelOLTEC PROPRIETARY l~FORMA I ION To provide a proper context for the subsequent evaluations, the potential degradation mechanisms applicable to the ventilated systems are summarized in Table 8.1.4. The degradation mechanisms listed in Table 8.1.4 are considered in the suitability evaluation presented later in this chapter.

The material evaluation presented in this chapter is intended to be complete, even though a conclusion of the adequacy of the materials can be made on the strength of the following facts:

1.

The materials used in HI-STORM FW are, with the sole exception of Metamic-HT, identical to those used in the widely deployed HI-STORM 100 System (Docket No. 72-1014).

11. The thermal environment in the HI-STORM FW system emulates the HI-STORM 100 system in all respects..

iii. The fuel loading and short-tenn operations are essentially identical to those that have been practiced in the HI-STORM I 00 system throughout the industry.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-2 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Table 8.1.1 CONSIDERATIONS GERMANE TO THE MPC MATERIAL PERFORMANCE Consideration Short-Term Operations Long-Term Storage Environment Aqueous (with Boric acid in MPC's internal environment is PWR plants), characterized by hot (~752°F), inertized and moderately hot (<212°F) water dry. Temperature of the MPC during fuel loading, rapid cycles very gradually due to evaporation during welding changes in the environmental and drying operations temperature.

Potential degradation modes Hydrogen generation from Corrosion of the external oxidation of aluminum and surfaces of the MPC (stress, aluminum alloy internals. Risk corrosion, cracking, pitting, to the integrity of fuel etc.)

cladding from thermal transients caused by vacuum drying.

Potential hazards to effective Inadequate drying of Blockage of ventilation ducts performance waterlogged fuel rods.

under an extreme environmental phenomenon leading to a rapid heat-up of the MPC internals.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-3

I IOLTEC PROPRIETARY INFORMATIOl<l Table 8.1.2 CONSIDERATIONS GERMANE TO THE HI-STORM FW OVERPACK MATERIAL PERFORMANCE*

Consideration Performance Data Environment Cool ambient air progressively heated as it rises in the overpack/MPC annulus heating the inside surface of the cask. The heated air has reduced relative humidity. Direct heating of the overpack inner shell by radiation can be prevented using the optional "heat shields" described in Chapter 1, on a site specific basis.

External surface of the overpack including the top lid is heated and in contact with ambient air, rain, and snow, as applicable.

Potential degradation modes Peeling or perforation of surface preservatives and corrosion of any exposed steel surfaces.

Potential hazards to effective perfonnance Blockage of ducts by debris leading to overheating of the concrete in the overpack, scorching of the cask by proximate fire, lightning.

• Short-term operations are not applicable to the HI-STORM FW overpack.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-4 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATIOl<l Table 8.1.3 CONSIDERATIONS GERMANE TO THE OF HI-TRAC VW MATERIAL PERFORMANCE" Consideration Performance Data Environment Heated fuel pool water on the outside and demineralized water in contact with the inside surface, heated water in the "water jacket".

Temperature ramps on the inside surface during the drying and "backfill" operation.

Potential degradation modes Peeling or perforation of surface coatings, loss of effectiveness of bottom lid gasket.

Potential hazards to effective perfonnance Lead slump due to sudden inertial loading; contamination of the inside surface of the cask by pool water, partial loss of heat rejection resulting in boiling of water in the water jacket, impact from tornado missile during transfer to the ISFSI.

• Long-term storage conditions are not applicable to the transfer cask.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-5 Rev. 5

HObTEC PROPRIETARY INFORMATION Table 8.1.4 FAIL URE AND DEGRADATION MECHANISMS APPLICABLE TO VENTILATED SYSTEMS§ Mechanism Area of Performance Vulnerable Parts Affected

1.

General Corrosion Sh*uctural capacity All carbon steel parts

2.

Hydrogen Generation Personnel safety during short-Coatings, parts made term operations of aluminum or aluminum alloys

3.

Stress Corrosion Cracking Structural Austenitic Stainless Steel

4.

Creep Criticality control Fuel Basket

5.

Galling Equipment handling and Threaded Fasteners deployment

6.

Hysteresis During fuel loading in the pool HT-TRACVW Bottom Lid Gaskets

7.

Fatigue Structural Integrity Fuel Cladding &

Bolting

8.

Brittle Fracture Structural Capacjty Thick Steel Parts

9.

Boron Depletion Criticality Control Neutron Absorber

§ This table lists all potential (generic) mechanisms, whether they are credible for the HI-STORM FW System or not. The viability of each failure mechanism is discussed later in this chapter.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-6 Rev. 5

HOLTEC F'RO~RIETARY lt~FORMATION 8.2 MATERIAL SELECTION The following acceptance criteria are applicable for material selection per ISG-15.

a.

The material properties of a dry spent fuel storage component should meet its service requirements in the proposed cask system for the duration of the licensing period.

b.

The materials that comprise the dry spent fuel storage should maintain their physical and mechanical properties during all conditions of operations. The spent fuel should be readily retrievable without posing operational safety problems.

c.

Over the range of temperatures expected prior to and during the storage period, any ductile-to-brittle transition of the dry spent fuel storage materials, used for structural and nonstructural components, should be evaluated for its effects on safety.

d.

Dry spent fuel storage gamma shielding materials (e.g. lead) should not experience slumping or loss of shielding effectiveness to an extent that compromises safety. The shield should perfotm its intended function throughout the licensed service period.

e.

Dry spent fuel storage materials used for neutron absorption should be designed to perform their safety function.

f.

Dry spent fuel storage protective coatings should remain intact and adherent during all loading and unloading operations within wet or dry spent fuel faci lities, and during long-term storage.

The above criteria have been utilized in selecting the material types for the HI-STORM FW system. The selected materials provide the required heat transfer, confinement, shielding and the criticality control of the stored spent fuel and are capable of withstanding loadings including seismic, temperature cycles due to internal heat and ambient temperature variation, extreme temperature conditions, loads due to natural phenomena like tornado missiles, flooding and other credible hypothetical accident scenarios. The HI-STORM FW components must withstand the environmental conditions experienced during normal operation, off-normal conditions and accident conditions for the entire service life.

The selection of materials is guided by the applicable loadings and potential failure modes. An emphasis has been placed on utilizing proven materials that have established properties and characteristics and are of proven reliability. Where a relatively new material ( e.g., Metamic-HT) is used, comprehensive tests have been conducted to ensure reliability.

The major structural materials used in HI-STORM FW System are discussed in this section. The mechanical and thern1al properties of these materials are presented in Section 8.4. The materials for welds are discussed in Section 8.5. The structural materials for bolts and fasteners are discussed in Section 8.6. Coatings and paints are discussed in Section 8.7. Gamma and neutron HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-7 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

lelObTi;C PROPRIETARY INFORMATION shielding materials are treated in Section 8.8. The neutron absorbing materials are discussed in Section 8.9.

Chapter 1 provides a general description of the HI-STORM FW System including information on materials of construction. All materials of construction are identified in the drawing package provided in Section 1.5 and the ITS categories of the sub-components are identified in Table 2.0.1 through 2.0.8.

8.2.1 Structural Materials 8.2.1. 1 Cask Components and Their Constituent Materials The major structural materials that are used in the HI-STORM FW System are Alloy X, Metamic-HT, carbon steel, and aluminum. They are further discussed below in light of the ISG-15 requirements.

MPC All structural components in an MPC Enclosure Vessel are made of Alloy X (stainless steel).

Appendix l.A provides discussions on Alloy X materials. The fuel basket is made of Metamic-HT neutron absorber described in Chapter 1, Section 1.2.1.4. The confinement boundary is made of stainless steel material for its superior strength, ductility, and resistance to corrosion and brittle fracture for long tenn storage. The basket shims used to suppo1t the basket are made of a creep resistant aluminum alloy. The two-piece MPC lid is either made entirely of Alloy X or the bottom portion of the lid is made of carbon steel with stainless steel veneer. The principal materials used in the fabrication of the MPC are listed in Section 1.2.

ID-STORM The main structw-al function of the overpack is provided by carbon steel and the main shielding function is provided by plain concrete. Chapter 1 presents discussions on these materials. The materials used in the fabrication of the overpack are listed in Section 1.2.

HI-TRAC As discussed in Chapter 1, the HI-TRAC VW transfer cask is principally made of carbon steel and lead. The HI-TRAC VW is equipped with a water jacket. The materials used in the fabrication of the transfer cask are listed in Section 1.2.

8.2. 1.2 Synopsis of Structural Materials

1.

Alloy X The MPC enclosure vessel design allows use of any one of the four Alloy X materials: Types 304, 304LN, 316 and 316LN. Qualification of structures made of Alloy X is accomplished by HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-8 Rev. 5

I IOLTEC PROPRIETARY INFORMATION using the least favorable mechanical and thennal properties of the entire group for all MPC mechanical, structural, neutronic, radiological, and thermal conditions. Each of these material properties are provided in the ASME Code Section 11 [8.3.1].

As discussed in Appendix l.A, the Alloy X approach is conservative because, no matter which material is ultimately utilized, the Alloy X guarantees that the performance of the MPC will meet or exceed the analytical predictions. The material properties are provided at various temperatures.

All structural analyses utilize conservatively established material properties such as design stress intensity, tensile strength, yield strength, and coefficient of thermal expansion for the range of temperature conditions that would be experienced by the cask components.

Chapter 3 provides the structural evaluation for the MPC Enclosure Vessel which is made of Alloy X. It is demonstrated that Alloy X provides adequate structural integrity for the MPC enclosure vessel under normal, off normal, and accident conditions. As shown in Chapter 4, the maximum metal temperature for Alloy X for the Confinement Boundary remains the design temperatures in Table 2.2.3 under all service modes. As shown in ASME Code Case N-47-33 (Class 1 Components in Elevated Temperature Service, 1995 Code Cases, Nuclear Components),

the strength properties of austenitic stainless steels do not change due to exposure to 1000°F temperature for up to I 0,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

Since stainless steel materials do not undergo a ductile-to-brittle transition in the m1111mum pennissible service temperature range of the HI-STORM FW System, brittle fracture is not a concern for the MPC components. Subsection 8.4.3 presents further discussions on brittle fracture.

In Section 8.12, the potential for chemical and galvanic reaction of Alloy X in short-tem1 and long-term operating conditions is evaluated. Alloy X is also used in the Confinement Boundary of all HI-STORM 100 MPCs.

11.

Metamic-HT Criticality control in the HI-STORM FW System is provided by the coplanar grid work of the Fuel Basket honeycomb, made entirely of the Metamic-HT extruded metal matrix composite plates. The boron in Metamic-HT provides criticality control in the Hl-STORM FW System. The Metamic-HT neutron absorber is a successor to the Metamic (classic) product widely used in dry storage fuel baskets and spent fuel storage racks (the "HT" designation in Metamic-HT stands for high !emperature and is derived from this characteristic). Metamic-HT has been Licensed in the HI-STAR 180 transport cask (Docket No. 71-9325).

Metamic-HT is also engineered to possess the necessary mechanical characteristics for structural application. The mechanical properties of Metamic-HT are derived from the strengthening of its aluminum matrix with ultra fine-grained (nano-particle size) alumina (Ah03) particles that anchor the grain boundaries for high temperature strength and creep resistance.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-9 Rev. 5

HOLTEC f"ROl"RIETARY lt~FORMATION Critical properties of Metamic-HT have been established as minimum guaranteed values by conducting tests using ASTM sanctioned procedures (Metamic-HT Sourcebook [8.9.7]). The critical structural properties include yield strength, tensile strength, Young's modulus, and area reduction, (See Chapter 1, Section 1.2.1.4 ).

The neutron absorbing properties of Metamic-HT are addressed m Section 8.9 and also m Chapter 1, Section 1.2.1.4.

Chapter 3 presents structural evaluation of spent fuel basket made of Metamic-HT wherein it is concluded that the Metamic-HT plates possess adequate stmctural strength to meet the loadings postulated for the fuel basket. Section 8.12 presents potential for chemical and galvanic reaction in Metamic-HT under short-term and long-term operating conditions.

All Metamic-HT material procured for use in the Holtec casks is qualified as important-to-safety (ITS). Accordingly, material and manufacturing control processes are established to eliminate the incidence of errors, and inspection steps are implemented to serve as an independent set of barriers to ensure that all critical characteristics defined for the material by the cask designer are met in the manufactured product. Additional discussions on the manufacturing of Metamic-HT are provided in Chapter 1, Section 1.2.1.4 and also in Chapter 10.

111.

Carbon Steel, Low-Alloy, and Nickel Alloy Steel Materials for HI-STORM FW overpack and HI-TRAC VW transfer cask including the parts used to lift the overpack and the transfer cask, which may also be referred to as "significant-to-handling" or "STH" parts, are selected to preclude any concern of brittle fracture. Details of discussions are provided in Subsection 8.4.3.

Steel forging materials for low temperature applications have been selected for the STH components that have thicknesses greater than 2" so that acceptable fracture toughness at low temperatures can be assured. All other major steel structural materials in the HI-STORM FW overpack and HI-TRAC VW cask are made of fine grain low carbon steel (see drawings in Section 1.5).

The mechanical properties of these materials are provided in Section 3.3. Section 3.1 provides allowable stresses under different loading conditions and impact testing requirements for these materials.

Chapter 3 provides structural evaluations of the HI-STORM FW System components. It is demonstrated that the structural steel components of the HI-STORM FW overpack meet the allowable stress limits for normal, off-normal and accident loading conditions.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-10 Rev. 5

lelOLTEC PROPRIETARY l~FORMA i lCJJ'r 8.2.2 Nonstructural Materials

1.

Aluminum Alloy The space between the fuel basket and the inside surface of the Confinement Boundary is occupied by specially shaped precision extruded or machined basket shims made of a high strength and creep resistant aluminum alloy. The basket shims establish a conformal contact interface with the fuel basket and the MPC shell, and thus prevent significant movement of the basket. The basket shims are extruded and/or machined to a precise shape with a high degree of accuracy.

The clearance between the basket shims and the interfacing machined surface of the MPC cavity is set to be sufficiently small such that the thermal expansion of the parts inside the MPC under Design Basis heat load conditions will minimize any macro-gaps at the interface and thus minimize any resistance to the outward flow of heat, while ensuring that there is no restraint of free thermal expansion.

To further enhance thermal performance, the aluminum alloy basket shims are hard anodized.

This provides for added corrosion protection and to achieve the emissivity value specified in Section 4.2. Mechanical properties of the shim material are provided in Section 3.3.

The basket shim material utilized in the HI-STORM FW system has also been used in other casks (viz. HI-STAR 180).

11.

Concrete The plain concrete between the overpack inner and outer steel shells and in the overpack lid is specified to provide the necessary shielding properties and compressive strength. Appendix l.D of the HI-STORM 100 FSAR which provides technical and placement requirements on plain concrete is also invoked for HI-STORM FW concrete.

The HI-STORM FW overpack concrete is enclosed in steel inner and outer shells connected to each other by radial ribs, and top and bottom plates and does not require rebar. As the HI-STORM FW overpack concrete is not reinforced, the structural analysis of the overpack only credits the compressive strength of the concrete.

The technical requirements on testing and qualification of the HI-STORM FW plain concrete are identical to those used in the HI-STORM 100 program. Accordingly, the testing and placement guidelines in Appendix l.D of the HI-STORM 100 FSAR (Docket No. 72-1014), is incorporated in this SAR by reference.

ACI 318 is the reference code for the plain concrete in the HI-STORM FW overpack. ACI 318.1-85(05) is the applicable code utilized to determine the allowable compressive strength of the plain concrete credited in structural analysis.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-11 Rev. 5

I IOLTEC PROPRIETARY INFORMATION The gamma shielding characteristics of concrete is considered in Section 8.8.

111.

Lead HI-TRAC VW contains lead between its inner and the middle shell for gamma shielding. The load carrying capacity of lead is neglected in all structural analysis. However, in the analysis of a tornado missile strike the elasto-plastic properties of lead are considered in characterizing the penetration action of the missile.

Applicable mechanical properties of lead are provided in Section 3.3. Shielding properties of lead are provided in Section 8.8.

8.2.3 Critical Characteristics and Equivalent Materials As defined in the Glossary, the critical characteristics of a material are those attributes that have been identified, in the associated material specification, as necessary to render the material's intended function. However, material designations adopted by the International Standards Organization (ISO) also affect the type of steels and steel alloys available from suppliers around the world. Therefore, it is necessary to provide for the ability in this FSAR to substitute materials with equivalent materials in the manufactw-e of the equipment governed by this FSAR.

As defined in the Glossary, equivalent materials are those materials with critical characteristics that meet or exceed those specified for the designated material. Substitution by an equivalent material can be made after the equivalence in accordance with the provisions of this FSAR has been established.

The concept of equivalent materials explained above has been previously used in this FSAR to qualify four different austenitic stainless steel alloys (ASME SA240 Types 304, 304LN, 316, and 316LN) to serve as candidate MPC materials.

The equivalence of materials is directly tied to the notion of critical characteristics. A critical characteristic of a material is a material prope1ty whose value must be specified and controlled to ensure an SSC will render its intended function. The numerical value of the critical characteristic invariably enters in the safety evaluation of an SSC and therefore its range must be guaranteed.

To ensure that the safety calculation is not adversely affected properties such as Yield Strength, Ultimate Strength and Elongation must be specified as minimum guaranteed values. However, there are certain properties where both minimum and maximum acceptable values are required (in this category lies specific gravity and thermal expansion coefficient).

Table 8.2.1 lists the array of properties typically required in safety evaluation of an SSC in dry storage and transpo1t applications. The required value of each applicable property, guided by the safety evaluation needs defines the critical characteristics of the material. The subset of applicable properties for a material depends on the role played by the material. The role of a material in the SSC is divided into three categories:

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-12 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY l~JFORMATION Type Technical Area of Applicability s

Those needed to ensure ~tructural compliance T

Those needed to ensure thermal compliance (temperature limits)

R Those needed to ensure radiation compliance (criticality and shielding)

The properties listed in Table 8.2.1 are the ones that may apply in a dry storage or transport application.

The fo llowing procedure shall be used to establish acceptable equivalent materials for a particular application.

Criterion i:

Functional Adequacy:

Evaluate the guaranteed critical characteristics of the equivalent material against the values required to be used in safety evaluations. The required values of each critical characteristic must be met by the minimum ( or maximum) guaranteed values (MGVs of the selected material).

Criterion ii:

Chemical and Environmental Compliance:

Perform the necessary evaluations and analyses to ensure the candidate material will not excessively corrode or otherwise degrade in the operating environment.

A material from another designation regime that meets Criteria (i) and (ii) above is deemed to be an acceptable material, and hence, equivalent to the candidate material.

Equivalent materials as an alternative to the U.S. national standards materials (e.g., ASME, ASTM, or ANSI) shall not be used for the Confinement Boundary materials. Equivalent materials as alternative to Holtec's specialty engineered Metamic-HT material shall not be used for the MPC fuel basket. For other ITS materials, recourse to equivalent materials shall be made only in the extenuating circumstances where the designated material in this FSAR is not readily available.

As can be ascertained from its definition in the glossary, the critical characteristics of the material used in a subcomponent depend on its function. The overpack lid, for example, serves as a shielding device and as a physical barrier to protect the MPC against loadings under all service conditions, including extreme environmental phenomena. Therefore, the critical characteristics of steel used in the lid are its strength (yield and ultimate), ductility, and fracture resistance.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-13 Rev. 5

I IOLTEG PROPRIET.ARY INFORMATION The appropriate critical characteristics for structural components of the HI-STORM FW System, therefore, are:

1.

Material yield strength, cry

11.

Material ultimate strength, <Ju 111.

Elongation, s iv.

Charpy impact strength at the lowest service temperature for the part, Ci Thus, the carbon steel specified in the drawing package can be substituted with different steel so long as each of the four above properties in the replacement material is equal to or greater than their minimum values used in the qualifying analyses used in this FSAR. The above critical characteristics apply to all materials used in the primary and secondary structural parts of the steel weldment in the overpack.

In the event that one or more of the critical characteristics of the replacement material is slightly lower than the original material, then the use of the § 72.48 process shall be necessary to ensure that all regulatory predicates for the material substitution are fully satisfied.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-14 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Table 8.2.1 Critical Characteristics of Materials Required for Safety Evaluation of Storage and Transport Systems Property Type Purpose Bounding Acceptable Value

1.

Minimum Yield s

To ensure adequate elastic Min.

Strength strength for normal service conditions

2.

Minimum Tensile s

To ensure material integrity Min.

Strength under accident conditions

3.

Young's Modulus s

For input in structural Min.

analysis model

4.

Minimum elongation s

To ensure adequate material Min.

ofomin.' %

ductility

5.

Impact Resistance at s

To ensure protection against Min.

ambient conditions crack propagation

6.

Maximum allowable s

To prevent excessive Max.

creep rate deformation under steady state loading at elevated temperatures

7.

Thermal conductivity T

To ensure that the basket will Min.

(minimum averaged conduct heat at the rate value in the range of assumed in its thermal model ambient to maximum service temperature, tmax)

8.

Minimum Emissivity T

To ensure that the thermal Min.

calculations are perfom1ed conservatively

9.

Specific Gravity S (and R)

To compute weight of the Max. (and Min.)

component (and shielding effectiveness)

10. Thermal Expansion T (and S)

To compute the change in Min. (and Max.)

Coefficient basket dimension due to temperature (and thermal stresses)

11. Boron-! 0 Content R

To control reactivity Min.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 Rev. 5 8-15 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION 8.3 APPLICABLE CODES AND STANDARDS The principle codes and standards applied to the HI-STORM FW System components are the ASME Boiler and Pressure Vessel Code [8.3.1], the ACI code [8.3.2], the ASTM Standards and the ANSI standards. Chapter I provides details of the specific applications of these codes and standards along with the other codes and standards that are applicable.

Section 1.0 of this FSAR provides a tabulation of this FSAR's compliance with NUREG-1536.

This section also provides a list of clarifications and alternatives to NUREG-1536. This list of clarifications and alternatives discusses Holtec lntemational's approach for compliance with the underlying intent of the guidance and also provides the justification for the alternative method for compliance adopted in this FSAR. Section 1.2 identifies the ASME code paragraphs applicable for the design of the HI-STORM FW overpack primary load bearing parts, summarizes the code requirements for the fabrication of the HI-STORM FW components, and refers to the national standards (e.g., ASTM, AWS, ANSI, etc.) used for the material procurement and welding.

Chapter 2 discusses factored load combinations for ISFSI pad design per NUREG-1536 [8.3.3],

which is consistent with ACI-349-85. Codes ACI 360R-92, "Design of Slabs on Grade"; ACI 302.lR, "Guide for Concrete Floor and Slab Construction"; and ACI 224R-90, "Control of Cracking in Concrete Strnctures" are also used in the design and constrnction of the concrete pad. Section 2.2 elaborates on the specific applications of ASME Boiler and Pressure Vessel code and provides a list of ASME code alternatives for the HI-STORM FW System.

Section 3.1 provides allowable stresses and stress intensities for various materials extracted from applicable ASME code sections for various service conditions. This section also provides discussions on fracture toughness test requirements per ASME code sections. Mechanical prope1ties of materials are extracted from applicable ASME sections and are tabulated for various materials used in HI-STORM FW System. Concrete propetties are from ACI 318-89 code. Section 3.7 presents discussions on compliance on NUREG-1536 and stipulations of J OCFR72 requirements to provide reasonable assurance with respect to the adequacy of the HI-STORM FW System.

In order to meet the requirements of the codes and standards the materials must conform to the minimum acceptable physical strengths and chemical compositions and the fabrication procedures must satisfy the prescribed requirements of the applicable codes.

Additional codes and standards applicable to welding are discussed in Section 8.5 and those for the bolts and fasteners are discussed in Section 8.6.

Review of the above shows that the identified codes and standards are appropriate for the material control of major components. Additional material control is identified in material specifications. Material selections are appropriate for environmental conditions to be encountered during loading, unloading, transfer and storage operations. The materials and fabrication of major components are suitable based on the applicable codes of record.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-16 Rev. 5

I IOLTEC PROPRIETARY INFORMATIOl<l 8.4 MATERIALPROPERTIES This section provides discussions on material prope1ties that mainly include mechanical and thennal properties. The material properties used in the design and analysis of the HJ-STORM FW System are obtained from established industry codes such as ASME Boiler and Pressure Vessel Code [8.4.1 ], ASTM publications, handbooks, textbooks, other NRC-reviewed SARs, and government publications, as appropriate.

8.4.1 Mechanical Properties Section 3.3 presents mechanical prope1ties of materials used in the HI-STORM FW System. The sttuctural materials include Alloy X, Metamic-HT, carbon steel, low-alloy and nickel-alloy steel, bolting materials and weld materials. The properties include yield stress, mean coefficient of thermal expansion, ultimate stress and the Young's modulus of these materials and their variations with temperature. Certain mechanical properties are also provided for nonstructural materials such as concrete and lead used for shielding. Additional properties of the neutron absorbing material Metamic-HT are discussed in Section 8.9.

The discussion on mechanical properties of materials in Chapter 3 provides reasonable assurance that the class and grade of the structural materials are acceptable under the applicable construction code of record. Selected parameters such as the temperature dependent values of stress allowables, modulus of elasticity, Poisson's ratio, density, thermal conductivity and thennal expansion have been appropriately defined in conjunction with other disciplines. The material properties of all code materials are guaranteed by procuring materials from Holtec approved vendors through material dedication*, process if necessary.

8.4.2 Thermal Properties Section 4.2 presents thermal properties of materials used in the MPC such as Alloy X, Metamic-HT, aluminum shims and helium gas; materials present in ID-STORM FW such as carbon steel and concrete; and materials present in HI-TRAC VW transfer cask that include carbon steel, lead and demineralized water. The prope1ties include density, thermal conductivity, heat capacity, viscosity, and surface emissivity/absorptivity. Variations of these properties with temperature are also provided in tabular fo1ms.

The thermal properties of fuel (U02) and fuel cladding are also reported in Section 4.2.

Thermal properties are often obtained from standard handbooks and established text books (see Table 4.2.1). When variations of thermal properties are observed the most conservative values are established as input for the design of the components of the HI-STORM FW System.

• A term of art in nuclear quality assurance.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-17 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 8.4.3 Low Temperature Ductility of Ferritic Steels*

The risk of brittle fracture in the HI-STORM FW components is eliminated by utilizing materials that maintain high fracture toughness under extremely cold conditions.

The MPC canister is constructed from a menu of stainless steels termed Alloy X. These stainless steel materials do not undergo a ductile-to-brittle transition in the minimum service temperature range of the HI-STORM FW System. Therefore, brittle fracture is not a concern for the MPC components.

Such an assertion cannot be made a' priori for the HI-STORM FW storage overpack and HI-TRAC VW transfer cask that contain fen-itic steel parts. In general, the impact testing requirement for the HI-STORM FW overpack and the HI-TRAC VW transfer cask is a function of two parameters: the Lowest Service Temperature (LST) t and the nonnal stress level. The significance of these two parameters, as they relate to impact testing of the overpack and the transfer cask, is discussed below.

In nonnal storage mode, the LST of the HI-STORM FW storage overpack structural members may reach -40°F in the limiting condition wherein the spent nuclear fuel (SNF) in the contained MPCs emits no (or negligible) heat and the ambient temperature is at -40°F (design minimum per Chapter 2: Principal Design Criteria). However, during the HI-STORM FW overpack transport operations, the applicable lowest service temperature is per 0°F (per the Technical Specifications). Therefore, two distinct LSTs are applicable to load bearing metal parts within the HI-STORM FW System; namely, LST = 0°F for the HI-STORM FW overpack during transport operations and for the HI-TRAC VW transfer cask during all nonnal operating conditions.

LST = -40°F for the HI-STORM FW overpack during storage operations.

SA350-LF2 and SA350-LF3 have been selected as the material for the STH parts due to their capability to maintain acceptable fracture toughness at low temperatures (see Table 5 in SA350 of ASME Section IIA). For the HI-TRAC VW Version P, the lifting trunnions are fabricated from SB-637 Grade N07718. SB-637 Grade N07718 is a high strength nickel alloy material, which has high resistance to fracture at low temperatures. Therefore, brittle fracture is not a concern for the lifting trunnions.

Table 3.1.9 provides a summary of impact testing requirements for the materials used in the HI-STORM FW System to ensure prevention of brittle fracture.

• This subsection has been copied from the HI-STORM I 00 FSAR (Section 3. l) without any substantive change.

t LST (Lowest Service Temperature) is defined as the daily average for the host ISFSI site when the outdoors portions of the "short-term operations" are carried out.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-18 Rev. 5

HOLTEC F'RO~RIETARY INFORMATION 8.4.4 Creep Properties of Materials Creep, a visco-elastic and visco-plastic effect in metals, manifests itself as a monotonically increasing deformation if the metal part is subjected to stress under elevated temperature. Since ce1tain parts of the HI-STORM FW System, notably the fuel basket, operate at relatively high temperatures, creep resistance of the fuel basket is an important property. Creep is not a concern in the MPC enclosure vessel, the HI-STORM FW overpack, or the HI-TRAC VW steel weldment because of the operating metal temperatures, stress levels and material prope1ties.

Steels used in ASME Code pressure vessels have a high threshold temperature at which creep becomes a factor in the equipment design. The ASME Code Section II material properties provide the acceptable upper temperature limit for metals and alloys acceptable for pressure vessel service. In the selection of steels for the HI-STORM FW System, a critical criterion is to ensure that the sustained metal temperature of the part made of the patticular steel type shall be less than the Code allowable temperature for pressure vessel service (ASME Section III Subsection ND). This criterion guarantees that excessive creep deformation will not occur in the steels used in the HI-STORM FW System.

As discussed below, the incidence of creep in the fuel basket is a not a trivial matter because lateral creep defonnation can alter the reactivity control characteristics of the basket.

8.4.4.1 Metamic-HT Metamic-HT is the sole constituent material in the HI-STORM FW fuel basket. The suitability of Metamic-HT for the conditions listed in Table 8.1.1 are considered in the "Metamic-HT Qualification Sourcebook" [8.9.7].

The Metamic Sourcebook contains data on the testing to determine the creep characteristics of the Metamic-HT under both unirradiated and irradiated conditions. A creep equation to estimate a bounding estimate of total creep as a function of stress and temperature is also provided. The creep equation developed from this test provides a conservative prediction of accumulated creep strain by direct comparison to measured creep in unitndiated and irradiated coupons.

The creep equation for Metamic-HT that bounds all measured data (tests run for 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) is of the classical exponential form in stress and temperature (see Table 1.2.8) stated symbolically e

= f(cr,T).

Creep in the fuel basket will not affect reactivity because the basket is oriented vertically during all operations ( except as described in Subsection 4.5.] which requires a site-specific stress evaluation per Subsection 3.1.2.2). The lateral loading of the fuel basket walls is insignificant and hence there is no mechanistic means for the basket panels to undergo lateral deformation from creep.

The creep effect would tend to shorten the fuel basket under the self-weight of the basket. An illustrative calculation of the cumulative reduction of the basket length is presented below to demonstrate the insignificant role of creep in the fuel basket.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-19 Rev. 5

I IOLTEG PROPRIET.ARY lf)IFORMAJIQN The in-plane compressive stress, cr, at height x in the basket panel is given by cr = p(H-x)

Where p = density of Metamic-HT H = height of the fuel basket Using the above stress equation, the total creep shrinkage, 8, is given by (8.1)

(8.2)

Where T = panel's metal temperature, initial value conservatively assumed to be 350°C (from Section 4.6) and dropping linearly to 150°C at 60 years.

t* = 60 years H = height of the basket (approximately 200 inches)

Using the creep equation [l.2.6] and performing the above double integration numerically with Mathcad yields 8 = 0.044 inch. In other words, the computed shrinkage of the basket is less than 0.022% of its original length.

It is concluded that for vertical configuration of storage the creep effects of the MPC basket are insignificant due to absence of any meaningful loads on the panels. Therefore, creep in the Metamic-HT fuel basket is not a matter of safety concern.

8.4.4.2 Aluminum Alloy The basket shims are not subject to any significant loading during storage. Similar to the fuel basket, the stress levels from self-weight in long-term storage eliminates creep as a viable concern for the basket shims.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-20 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HObTEC PROPRIETARY INFORMATION 8.5 WELDING MATERIAL AND WELDING SPECIFICATION Welds in the HI-STORM FW System are divided into two broad categories:

1.

Structural welds

11. Non-structural welds Structural welds are those that are essential to withstand mechanical and inertial loads exerted on the component under normal storage and handling.

Non-stmctural welds are those that are subject to minor stress levels and are not critical to the safety function of the part. Non-stmctural welds are typically located in the redundant parts of the structure. The guidance in the ASME Code Section NF-1215 for secondary members may be used to determine whether the stress level in a weld qualifies it to be categorized as non-stmctural.

Both structural and non-structural welds must satisfy the material considerations listed in Tables 8.1.1, 8.1.2, and 8.1.3, for the MPC, the HI-STORM FW overpack and the HI-TRAC VW transfer cask, respectively. In addition, the welds must not be susceptible to any of the applicable failure modes in Table 8.1.4.

To ensure that all welds in the HI-STORM FW System shall render their intended function, the following requirements are observed:

1.

The weld joint configuration is selected to accord with the function of the joint (Holtec Position Paper DS-329 [8.5.1] provided to the USNRC in Docket No. 72-1 014).

LL The welding procedure specifications comply with ASME Section IX for every Code material used in the system.

iii. The quality assurance requirements applied to the welding process correspond to the highest ITS classification of the parts being joined.

1v. The non-destructive examination of every code weld is carried out using quality procedures that comply with ASME Section V.

v. Metamic-HT welding and welder qualifications, requirements, and examinations will be in accordance with Paragraphs 10.1.6.2, 10.1.1.4, and the drawing package in Section 1.5.

The welding operations are performed in accordance with the requirements of codes and standards depending on the design and functional requirements of the components.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-21 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION The selection of the weld wire, welding process, range of essential and non-essential variables,*

and the configuration of the weld geometry has been carried out to ensure that each weld will have:

1.

Greater mechanical strength than the parent metal.

ii. Acceptable ductility, toughness, and fracture resistance.

iii. Corrosion resistance properties comparable to the parent metal.

iv. No risk of crack propagation under the applicable stress levels.

The welding procedures implemented in the manufacturing of HI-STORM FW System components are intended to fulfill the above performance expectations.

Additional information on the welding for HI-STORM FW System components is provided in Section 1.2. Lists of codes and standards applicable for the manufacturing of HI-STORM FW System are also provided therein.

A list of ASME code alternatives for the MPC fabrication including welding is presented in Section 2.2. The structural strength requirements of welds including fracture toughness test requirements of weld materials are provided in Section 3.1. The confinement boundary welds and their testing requirements are discussed in Section 7.1. The inspection and testing requirements of the HI-STORM FW System component welds are provided in Section 10.1.

The weld filler material shall comply with requirements set forth in the applicable Welding Procedure Specifications qualified to ASME Section IX at the manufacturer's facility. Only those welding procedures that have been qualified to the Code are permitted in the manufacturing of HI-STORM FW components.

Review of the above shows that except for the MPC lid welds, all welds of the Enclosure Vessel are full penetration weld with volumetric NDE. All weld fi ller metals are specified by ASME Section II, Part C and associated A WS classification in applicable weld procedures.

The weld procedure qualification record specifies the requirements for fracture control (e.g. post weld heat treatment). The HI-STORM FW overpack and HI-TRAC VW transfer cask do not require any post weld heat treatment due to the material combinations and provisions in the applicable codes and standards. With respect to the MPC Lid-to-Shell weld, the progressive P.T.

requirements on the shell/lid weld are identical to those in Docket No. 72-1014 ( which are derived from the analysis summarized in Holtec Position Paper DS-213 [8.5.2], provided to the USNRC on Docket No. 72-1014.

• Please refer to Section IX of the ASME Code for the definition and delineation of essential and non-essential variables.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-22 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

AOL I EC PROPRIETARY lf~FORMATION Non-structural welds shall meet the following requirements:

1. The welding procedure shall comply with Section IX of the ASME Code or A WS D 1.1.

2. The welder shall be qualified, at minimum, to the commercial code such as ASME Section VIII, Div.I, or AWS Dl.l.

3. The weld shall be visually examined by the weld operator or a Q.C. inspector qualified to Level 1 ( or above) per ASNT designation.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-23 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 8.6 BOLTS AND FASTENERS Chapter 3 provides information on the structmal evaluation of the bolts and fasteners. Section 3.1 discusses fracture toughness requirements for bolting materials. Section 3.3 provides the bolting materials used in the HI-STORM FW System. Section 3.3 (Table 3.3.4) provides mechanical properties of bolting materials.

Chapter 9 provides pre-tensioning requirements for HI-STORM FW System bolts to ensure that the bolts shall not be overstressed under any condition of loading applicable to the system.

Bolts and fasteners made of low alloy steel are not expected to experience any significant corrosion in the operating environment. The ISFSI operation and maintenance program shall call for coating of bolts and fasteners if the ambient environment is aggressive.

A review of the above shows that the materials for the bolts and the fasteners have been selected to possess the required tensile strengths, resistance to corrosion and brittle fractme. To prevent a change in the bolt pre-stress during operating conditions, the coefficient of thennal expansion of each bolt material has been closely matched to that of the parts being fastened together.

Preventing galling of interfacing surfaces is another critical consideration in selecting bolt materials. Use of austenitic stainless bolts on interfacing austenitic stainless steel surfaces is not permitted. All threaded surfaces are treated with a preservative to prevent corrosion. The O&M program for the storage system calls for all bolts to be monitored for corrosion damage and replaced, as necessary.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-24 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 8.7 COATINGS AND CORROSION MITIGATION Protective coatings are used primarily as a corrosion barrier and/or as a means to facilitate decontamination. Coating materials for the HI-STORM FW system components are guided by the successful experience in similar service applications of the HI-STORM 100 and HI-STAR 100 components and parts. The main considerations in the selection of coatings are the ruggedness and physical integrity in the specific service environment, ease of decontamination as applicable to immersion service, thermal and radiation stability, and ease of application to facilitate touch-up activities for preventive maintenance. Surface preparation and repair are performed in accordance with manufacturer recommendations.

The coatings applied on specific HI-STORM FW System components are selected to be compatible with their respective conditions of service. For example, equipment used in the fuel pool environment must be conducive to convenient decontamination. Protective coatings are applied to surfaces vulnerable to corrosion such as exposed carbon steel surfaces on the HI-STORM FW overpack and HI-TRAC VW transfer cask. The MPC surfaces are not coated but may be subjected to certain optional surface treatments discussed in Section 8.7.4.

8.7.1 Environmental Conditions Applicable to Coating Selection and Evaluation Criteria:

8.7. l.1 Environmental Conditions The environmental conditions that warrant consideration in the selection of coatings are:

i. Temperature, humidity, and insolation ii. Radiation field iii. Immersion service Temperature, humidity, and insolation conditions may vary at different ISFSI sites. The coating selected for the HI-STORM FW overpack, which is subject to long-term exposure, must be stable under the entire range of psychometric conditions that prevail in the territorial United States. The coating selected for HI-TRAC VW must withstand the thermal exposure during fuel drying operations and during immersion in the spent fuel pool.

Stable performance under radiation is important for coatings applied on the inside surfaces of the HJ-STORM FW overpack and the HI-TRAC VW transfer cask, which are proximate to the lateral surfaces of the MPC.

Immersion in the pool implies three major challenges to the coating on the HI-TRAC VW:

a. Risk of penetration of tiny contaminant pa11iculates in the pores of the coating.

b. Chemical attack (by boric acid in PWR pools and demineralized water in BWR pools).

c. Temperature change as the transfer cask is immersed in or withdrawn from water.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-25 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Coatings that have been determined to be unsuitable for the immersion service shall not be used in the HI-TRAC VW transfer cask.

8.7.1.2 Coating Evaluation Criteria The evaluation criteria for selecting coatings are summarized below. These criteria shall be used if a pre-approved coating listed in Subsection 8.7.2, for any reason, is no longer available for use.

Coatin2 Acceptance Criteria

1.

Non-reactive to the surrounding environment

2.

Structural performance (bendability, ductility, resistance to cracking, and resistance to abrasion)

3.

Adherence to base material

4.

Chemical immersion resistance, if applicable

5.

Emissivity and absorptivity consistent with thermal analysis

6.

Temperature resistance for analyzed temperature conditions with humidity and insolation, as applicable

7.

Radiation resistance for analyzed conditions The paint suppliers may certify the properties by perfonnance of applicable ASTM tests. In the absence of ASTM test data for a required characteristic in the above table, the coating supplier will provide evidentiary information to justify acceptance. Alternatively, Holtec International will perform its own independent tests to establish compliance with the required criteria.

8.7.2 Acceptable Coatings Proven (previously used on HI-STORM 100 System components and other cask designs) coatings and paints that adequately satisfy the requirements are presented below and pre-approved for use on HI-STORM FW System components.

Carboguard 890 (Cycloaliphatic Amine Epoxy) of Carboline Company which demonstrates acceptable performance for short-te1m exposure in mild borated pool water may be used for coating the HI-TRAC VW transfer cask exterior su1faces as well as HI-STORM FW overpack surfaces.

This coating is certified for immersion services and provides excellent chemical resistance and abrasion resistance. It provides a smooth surface with no porosity and thereby, excellent decontamination characteristics. No adverse interaction has been experienced in many years of use.

Thermaline 450 (Amine-Cured Novolac Epoxy) of Carboline Company may be used for coating HI-TRAC VW transfer cask internal surfaces which are exposed only to demineralized water during in-pool operations (the annu lus is fi lled prior to placement in the spent fuel pool and the inflatable seal prevents fuel pool water in-leakage) and higher service temperatures. This coating provides excellent resistance to co1rnsion, abrasion, and permeation. No adverse interaction has been experienced in many years of use.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-26 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Carbozinc 11 (also known as CZ-11) may be used for coating HI-STORM FW overpack internal cavity and external surfaces (including lid surfaces). This solvent based coating material has excellent cotTosion resistant properties in harsh environments and provides inorganic zinc (galvanic) protection to steel surfaces. As an alternative to the Carbozinc 11, Sherwin Williams Zinc Clad II HS, Sherwin Williams Zinc Clad II Plus may also be used.

Product information for the above coatings is provided in Appendix 8.A.

Coatings that are specified in this section shall not be substituted with another coating unless the substitute meets or exceeds the performance of the coating listed above under all the applicable coating evaluation criteria set forth in the previous subsection.

8.7.3 Coating Application Holtec utilizes Q.A.-validated written procedures (HSP-318 [8.7.1] and HSP-319 [8.7.2]) to achieve the desired performance for the coating. These procedures provide requirements for the preparation and painting of the HI-STORM FW overpack, HI-TRAC VW transfer cask and associated components. These procedures are based on paint manufacturers' applicable specifications, instructions and recommendations.

The procedures provide details for the preparation prior to blasting, surface preparation, mixing and application, painting in the field, and touch up steps or repairs. The procedures also provide details of the dry film thickness testing and the acceptance criteria. Painting documentation is maintained for the record of the completion of various painting steps and the environmental conditions including the ambient temperature, humidity and the component surface temperature.

8.7.4 Optional MPC Surface Treatment (Peening)

To further enhance the confinement boundary resistance to stress corrosion cracking (SCC),

selected areas of the MPC can be treated using a peening process as an optional operation during manufacture of MPCs. The peening process induces a beneficial compressive stress in the surface layer of the material, hence reducing or eliminating the possibility of crack formation on the surface from potential degradation corrosion mechanisms such as CISCC (Chloride Induced Stress Corrosion Cracking).

Holtec utilizes Q.A.-validated written procedures to achieve the desired performance for the surface treatment and to ensure that the integrity of the MPC Confinement Boundary is maintained. The qualification of the procedures is discussed in Section 10.1.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-27 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PRO~RIETARY INFORMATIOl<l 8.8 GAMMA AND NEUTRON SHIELDING MATERIALS Gamma and neutron shield materials in the HI-STORM FW System are discussed in Section 1.2.

The primary shielding materials used in the HI-STORM FW system, like the HI-STORM 100 system, are plain concrete, steel, lead, and water.

The plain concrete enclosed by cylindrical steel shells, a thick steel baseplate, and a top annular plate provides the main shielding function in the HI-STORM FW overpack. The overpack lid has appropriate concrete shielding to provide neutron and gamma attenuation to minimize skyshine.

The transfer cask in the HI-STORM FW system (HI-TRAC VW) is provided with steel and lead shielding to ensure that the radiation and exposure objectives of l OCFR 72.104 and 1 OCFR 72. l 06 are met. The space between the inner shell and the middle shell is occupied by lead, conforming to ASTM B29, which provides the bulk of the cask's (gamma) radiation shielding capability. The water jacket between the middle shell and the outermost shell (filled with demineralized water or ethylene glycol fortified water, depending on the site environmental constraints) provides most of the neutron shielding capability to the cask. The water in the water jacket serves as the neutron shield on demand: When the cask is in the pool and the MPC is full of water, the water jacket is kept empty (or partially empty as necessary) to minimize the cask's weight, the neutron shielding function being provided by the water in the MPC cavity. However, when the MPC is emptied of water at the Decontamination and Assembly Station (DAS), then the neutron shielding capacity of the cask is replenished by filling the water jacket. The HI-TRAC VW bottom lid is extra thick steel to provide an additional measure of gamma shielding to supplement the gamma shielding at the bottom of the MPC.

8.8.1 Concrete Appendix l.D of HI-STORM 100 FSAR provides details of the concrete properties and the testing requirements. The critical characteristics of concrete are its density and compressive strength.

The density of plain concrete within the HI-STORM FW overpack is subject to a minor decrease due to long-term exposure to elevated temperatures. The reduction in density occurs primarily due to liberation of unbonded water by evaporation.

The density of concrete has been classified into three states in the published literature [8.8.1).

a) fresh density: the density of freshly mixed concrete b) air-dry density: drying in air under ambient conditions, where moisture is lost until a quasi-equilibrium is reached c) oven-dry density: concrete dried in an oven at 105°C (221°F)

Because the bulk temperature of concrete in HI-STORM FW is spatially variable, the oven-dry density is conservatively used as the reference density for shielding analysis.

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I IOLTEC PROPRIETARY INFORMATION Density loss during the initial drying process is considered in the fabrication of the HI-STORM FW overpack by providing wet concrete densities above the minimum required dry (hardened paste) density. Density loss during drying is on the order of 1 % and conservatively imposes a larger delta between wet density and the minimum dry density. The data in the literature, viz.,

Neville [8.8.1] indicates that the density difference between the air-dry condition and oven-dry condition is about one fourth of the density difference experienced during the drying process.

Therefore, the loss in density would be expected to be on the order of 0.25%. This density loss is very low and is considered too small to have a significant impact on the shielding performance of the overpack. Thus, the minimum "fresh density" during concrete placement is set equal to the reference density (Table 1.2.5) plus 1.25%.

Section 5.3 considers the minimum density requirements of concrete for effective shielding. The density requirement is confirmed per Appendix l.D of the HI-STORM 100 FSAR.

8.8.2 Steel Section 5.3 provides a discussion on steel as a shielding material and its composition used in the evaluation of its shielding characteristics.

8.8.3 Lead Section 1.2 provides a discussion on lead used in HI-TRAC VW for gamma shielding. In the HI-TRAC VW transfer cask radial direction, gamma and neutron shielding consists of steel-lead-steel and water, respectively. In the HI-TRAC VW bottom lid, layers of steel-lead-steel provide an additional measure of gamma shielding to supplement the gamma shielding at the bottom of the MPC.

Mechanical properties of lead are provided in Section 3.3. Section 5.3 provides the minimum density and composition (mass fraction of trace elements) of lead.

8.8.4 Water Water is used as a neutron shield in the HI-TRAC VW transfer cask. Section 5.3 provides the minimum density requirements of water for transfer cask water jacket and inside MPC. The shielding effectiveness is calculated based on the minimum water density at the highest operating temperature. Calculations show that additives for freeze protection (at low temperature operation) such as ethylene glycol do not have any adverse effect on effectiveness of the neutron shielding function of water in the water jacket.

As discussed in Section 5.1, there is only one accident that has any significant impact on the shielding configuration. This accident is the postulated loss of the neutron shield (water) in the HI-TRAC VW. The change in the neutron shield was conservatively analyzed by assuming that the entire volume of the liquid neutron shield was replaced by air.

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I IOLTEC PRO~RIETARY INFORMATIOl<l 8.9 NEUTRON ABSORBING MATERIALS Inside the MPC enclosure vessel is a structure referred to as the fuel basket. The fuel basket is an egg-crate assemblage of Metamic-HT plates which creates prismatic cells with square cross sectional openings for fuel storage. Metamic-HT is the neutron absorber and structural material of the MPC fuel basket. Metamic-HT is a composite material of nano-particles of aluminum oxide (alumina) and finely ground boron carbide particles dispersed in a metal matrix of pure aluminum [8.9.7].

8.9.1 Qualification and Properties of Metamic-HT The qualification and properties of Metamic-HT are presented in Chapter 1, Section 1.2.1.4 where its key characteristics necessary for insuring nuclear reactivity control, thermal, and structural performance are discussed. A test program configured to address the Metamic-HT properties was conducted by Holtec International and the minimum guaranteed values (MGVs) of the critical characteristics of Metamic-HT were determined [8.9.7] and summarized in Chapter l, Section l.2.1.4. All testing was conducted in accordance with the applicable ASTM test standards. The role in the fuel basket safety function of each of the critical characteristics is provided in Chapter 1, Section 1.2.1.4.

A rigorous quality control regimen and Holtec QA procedures ensure that all extruded Metamic-HT plates meet the requirements for the quality genre of the casks.

To ensure that the manufactured Metamic material will render its intended function with reasonable assurance, a sampling plan based on Mil Standard 105E [8.9.8] has been specified and made a pa11 of the Metamic-HT Manufacturing Manual [8.9.6]. The Sampling plan shall provide a reasonable level of confidence that the Minimum Guaranteed Values of all critical mechanical properties will be met in the production lots. Additional information regarding manufacturing ofMetamic-HT is provided in Chapter 1, Section 1.2.l.4.

Chapter 2 provides discussions on criticality parameters for design basis SNF, and the controls and methods utilized for prevention of criticality.

Criticality evaluation is presented in Chapter 6. The material heterogeneity parameters are adequately characterized and controlled and the criticality calculations employ appropriate corrections when modeling the heterogeneous material as an idealized homogeneous mixture. It is demonstrated that the MPC provides criticality control for all design basis normal, off-normal, and postulated accident conditions, as discussed in Section 6. l. The effective neutron multiplication factor is limited to k eff < 0.95 for fresh unirradiated fuel with optimum water moderation and close reflection, including all biases, w1certainties, and MPC manufacturing tolerances. Additional neutronic prope1ties of Metamic-HT are provided in Chapter l, Section 1.2. l.4.

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1 IOLTEC PROPRll:.TARY INFORMAi ION 8.9.2 Consideration of Boron Depletion The effectiveness of the borated neutron absorbing material used in the MPC fuel basket design requires that sufficient concentrations of boron be present to assure criticality safety during worst case design basis conditions over the design life of the MPC. Analysis discussed in Section 6.3 demonstrates that the boron depletion in the neutron absorber material is negligible over the expected service life of the HI-STORM FW System. This is due to the fact that the borated material is subjected to a relatively low neutron flux. Analyses show that the depletion of boron is a small fraction of the quantity present. Therefore, sufficient levels of boron will remain in the fuel basket neutron absorbing material to maintain criticality safety functions over the design life of the MPC. Fmthermore, the boron content of Metamic-HT used in the criticality safety analysis is conservatively based on the minimum specified boron areal density (rather than the nominal),

which is further reduced by 10% (see Chapter 6) for conservatism in the analysis.

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HOLTEC PROPRIETARY INFORMA I IU'ff" 8.10 CONCRETE AND REINFORCING STEEL The HI-STORM FW System does not utilize concrete with rebar. The plain concrete used in the HI-STORM FW overpack serves as the neutron shieldling. The absence of rebar in the HI-STORM FW overpack concrete ensures that radiation streaming paths due to the development of cracks and discontinuities at the rebar/concrete interfaces will not develop. Concrete in the overpack is not considered as a structural member, except to withstand compressive, bearing, and penetrant loads. Therefore the mechanical behavior of concrete must be quantified to determine the stresses in the structural members (steel shells surrounding it) under accident conditions.

Section 3.3 provides the concrete mechanical properties. Allowable, bearing strength in concrete for normal loading conditions is calculated in accordance with ACI 318-05 [8.3.2]. The procedure specified in ASTM C-39 is utilized to verify that the assumed compressive strength will be realized in the actual in-situ pours. Appendix l.D in the HI-STORM 100 FSAR provides additional information on the requirements on plain concrete for use in HI-STORM FW storage overpack.

To enhance the shielding performance of the HI-STORM FW storage overpack, high density concrete can be used during fabrication. The permissible range of concrete densities is specified in Table 1.2.5.

Review of the above shows that the HI-STORM FW System concrete components are acceptable. All concrete is either encased in steel or covered underneath the overpack lid, therefore; it is not subject to weathering or other atmospheric degradation, even in marine environments. To ensure that the concrete performs its primary function (shielding integrity/effectiveness) tests are performed as required by Chapter 10.

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--t'lOLTEC PROPRIETARY INFORMATION 8.11 SEALS The HI-STORM FW System does not rely upon mechanical seals for maintaining the integrity of the Confinement Boundary. The MPC Vent/Drain caps washers are made of a soft and malleable metal such as aluminum 1100.

The HI-TRAC VW transfer cask bottom lid utilizes a gasket to prevent ingress of pool water when the cask is staged in the fuel pool and leakage during MPC processing operations. Gaskets used may be silicone, neoprene, and a similar elastomeric material that is inert in the pool's aqueous environment.

In selecting the gasket material, it is necessary to ensure that none of the following materials will leach out in the pool water in measurable quantities.

Viton Saran Silastic L8-53 Teflon Nylon Carbon steel Neoprene or similar materials made of halogen containing elastomers Rubber bonded asbestos Polyethelene film colored with pigments over 50 ppm fluorine, measurable amount of mercury or halogens, or more than 0.05% lead Materials containing lead, mercury, sulfur, phosphorus, zinc, copper and copper alloys, cadmium, tin, antimony, bismuth, mischmetal, magnesium oxide, and halogens exceeding 75 ppm (including cleaning compound).

The gaskets used in the HI-TRAC VW shall be the same or equivalent to those that have proven to be satisfactory in prior service (such as in other Holtec transfer casks).

The mechanical design details of the gasketed joint in the transfer cask follow the guidelines in Chapter 3 of [8.11.1 ], which recommend joints subjected to cyclic loadings to be made of the "controlled compression" genre. The "controlled compression" joint minimizes cyclic damage to the gasket.

The O&M program for the storage system calls for HI-TRAC VW transfer cask elastomeric seals to be inspected for damage and replaced on an appropriate schedule as recommended by the manufacturer.

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I IOLTEC PROPRIETARY INFORMATION 8.12 CHEMICAL AND GALVANIC REACTIONS The materials used in the HI-STORM FW System are examined to establish that these materials do not participate in any chemical or galvanic reactions when exposed to the various environments during all normal operating conditions and off-normal and accident events.

The following acceptance criteria for chemical and galvanic reactions are extracted from ISG-15

[8.1.1] for use in HI-STORM FW components.

a.

The DCSS should prevent the spread of radioactive material and maintain safety control functions using, as appropriate, noncombustible and heat resistant materials.

b.

A review of the DCSS, its components, and operating environments (wet or dry) should confirm that no operation (e.g., sho1t term loading/unloading or long-term storage) will produce adverse chemical and/or galvanic reactions, which could impact the safe use of the storage cask.

c.

Components of the DCSS should not react with one another, or with the cover gas or spent fuel, in a manner that may adversely affect safety. Additionally, corrosion of components inside the containment vessel should be effectively prevented.

d.

The operating procedures should ensure that no ignition of hydrogen gas should occur during cask loading or unloading.

e.

Potential problems from general cotTosion, pitting, stress corrosion cracking, or other types of corrosion, should be evaluated for the environmental conditions and dynamic loading effects that are specific to the component.

The materials and their ITS pedigree are listed in the drawing package provided in Section 1.5.

The compatibility of the selected materials with the operating environment and to each other for potential galvanic reactions is discussed in this section.

8.12.1 Operating Environments During fuel loading, handling or storage the components of the HI-STORM FW System experience the following environments (see Tables 8.1.1, 8.1.2, and 8.1.3).

Spent Fuel Pool Water - During the fuel loading steps, the MPC confinement space is flooded with water (borated water in PWRs and demineralized water in BWRs). As water is withdrawn from the MPC space, the temperature of its contents rises, facilitating an AlThenius-like acceleration of any chemical reaction that may occur in the presence of water and water vapor or boric acid (in PWRs). These same conditions would exist in the event an MPC needs to be unloaded and the MPC is reflooded prior to lid removal.

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I IOLTEC PROPRIETARY INFORMATION Helium - During loading operations, all water is removed from the interior of the MPC and an inert gas is injected. Internal MPC components get exposed to dry helium under pressure during storage.

External atmosphere - During long term storage the casks are exposed to outside atmosphere, air with temperature variations, solar radiation, rain, snow, ice, etc.

As discussed below, the components of the HI-STORM FW System has been engineered to ensure that the environmental conditions expected to exist at nuclear power plant installations do not prevent the cask components from rendering their respective intended functions.

8.12.2 8.12.2.1 Compatibility of MPC Materials MPC Confinement Boundary Materials Austenitic Stainless Steels The MPC confinement boundary is composed entirely of corrosion-resistant austenitic stainless steel. The corrosion-resistant characteristics of such materials for dry SNF storage canister applications, as well as the protection offered by these materials against other material degradation effects, are well established in the nuclear industry. The available austenitic stainless steels are AISI Types 304, 304LN, 316 and 316LN containing a minimum of 16% chromium and 8% nickel, and at least traces of molybdenum. The passive films (formed due to atmospheric exposure) of stainless steels range between 10 to 50 angstroms (lxl0-6 to 5x10-6 mm) thick

[8.12.4). Of all types of stainless steels (i.e., austenitic, ferritic, martensitic, precipitation hardenable and two-phase), "the austenitic stainless alloys are considered the most resistant to industrial atmospheres and acid media" [8.12.4].

The MPC contains no gasketed, threaded, or packed joints for maintaining confinement. The all-welded construction of the MPC confinement boundary and the inert backfill gas within ensures that the interior surfaces and the MPC internals (Metamic-HT baskets, shims, etc.) are not subject to corrosion. Exterior MPC surfaces would be exposed to the ambient environment while inside of a HI-STORM FW storage overpack or a HI-TRAC VW transfer cask.

Austenitic Stainless Steels in Demineralized and Borated Water Environments The average MPC may be in contact with borated and/or demineralized water at temperatures below boiling and at pressures of up to three atmospheres (not including hydrotest) for approximately 2 to 3 days. For PWRs, the soluble boron levels are typically maintained at or below 2,500 ppm (0.25% boric acid solution). Experimental corrosion data for AISI Type 304 and 316 stainless steels (Swedish Designations SIS-14-2333 and SIS-14-2343, respectively) are available from the Swedish Avesta Jemverk laboratory [8. 12.4). Corrosive media evaluated in these tests include 4% (40,000 ppm) and 20% (200,000 ppm) boric acid solutions and water, all at boiling. Under the evaluated conditions, the tested steels are identified as "fully resistant",

with corrosion rates of less than 0.1 mm per year. Even more extensive experimental corrosion HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-35 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION data is available from ASM International [8.12.1]. For test conditions without rapid agitation, similar to conditions that would exist during MPC fuel loading in a spent fuel pool, all austenitic stainless steels available for MPC fabrication (i.e., AISI Types 304, 304LN, 316 and 316LN) are extremely resistant to corrosion in boric acid and water. More specifically, one set of data (UNS No. S30400) for 2.5% boric acid solution and water at 90.6°C (195°F), under no aeration and rapid agitation yielded a maximum corrosion rate of 0.003 mm per year [ 8.12. l].

No structural effects from any potential corrosion from demineralized and borated water environments are expected. Loading of a dry storage cask with reasonable delays can take up to two weeks. Adjusting the worst-case data for a 0.25% boric acid concentration the maximum thinning of any structural member in an MPC is only 4.80 x 10-6 mm (1.89 microinches). This is a negligibly small fraction (0.0006%) of the thickness of the thinnest structural member 7.9 mm (0.3125 in.) and a negligibly small fraction (0.004%) of the tolerance on the material thickness (0.045 in.) pennitted by the governing ASME Code [8.12.2].

Austenitic Stainless Steels and Crud Corrosion products cause "crud" deposits on fuel assemblies. Industry experience shows that crud, which is stable in oxygenated solutions, has not been found to contain materials that can react with stainless steel and cause significant degradation. Crnd may leave a slight film of rust on the interior surfaces of the MPC during fuel loading and closure activities.

Austenitic Stainless Steels and Boron Crystals Dry boron or boric acid crystals that remain in the MPC after drying and helium backfill are expected to have negligible co1rnsive effects on stainless steel due to the absence of the necessary reagents ( oxygen and moisture).

Austenitic Stainless Steels and Marine Environments The MPC is designed to be loaded with spent fuel assemblies from most light water reactor (L WR) nuclear power plants. L WR nuclear power plants, in general, are located near large bodies of water to ensure an adequate supply of cooling water. As a result many nuclear power plants and, subsequently, many potential ISFSI sites are located in coastal areas where dissolved salts may be present in atmospheric moisture. Casks deployed at coastal ISFSI sites that would be exposed to the harsh marine environment for prolonged periods must not suffer corrosion that will impair their functionality.

Extensive data show corrosion rates (pitting) to 0.0018 (mm/yr) for 304, 304LN, 316 and 316LN in marine environments at ambient temperatures after 26 years [8.12.1]. Using this bounding corrosion rate data, a Holtec Position Paper [8.12.3] estimates the total corrosion of the external surface of the MPC in I 00 years of service is about half a millimeter which is significantly smaller than the available design margins in the material thickness. It is to be noted that this upper-bound is estimated for an extreme hypothetical marine environment. As discussed earlier for inland applications the corrosion rates are insignificant.

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I IOLTEC PROPRIETARY INFORMATION Therefore, corrosion of the MPC in long-term storage is not a credible safety concern.

Austenitic Stainless Steels and Hydrogen Damage Traces of hydrogen may be present under the MPC Lid during welding operations. The hydrogen content is limited due to a low hydrogen generation rate and the (required) purging of the underside of the lid with helium. Hydrogen damage is classified into four distinct types (1) hydrogen blistering, (2) hydrogen embrittlement, (3) decarburization, (4) hydrogen attack.

Decarburization and hydrogen attack are high temperature processes and therefore may be of concern during cooling of the weld puddle. Austenitic stainless steels are one of the few metals that perform satisfactorily at all temperatures and pressures in the presence of hydrogen [8.12.6).

Considering the limited hydrogen concentration, limited time (2-3 days) for fuel loading and limited pressures and temperatures (with the exception of high temperatures at the lid to shell weld), hydrogen damage is not an applicable corrosion mechanism during fuel loading. With respect to the lid to shell weld, the weld design, use of a continuous inert gas purge, the weld method and NDE inspections provide assurance that the weld has no credible damage and is of high integrity.

8.12.2.2 Materials of MPC Internals The internals of the MPC consists of Metamic-HT fuel baskets and aluminum alloy shims for basket support. Besides these internals, SNF, possible failed fuel and/or damaged fuel with containers, and non-fuel hardware, a sealed MPC may also contain boric acid crystals (in PWRs) and crnds. The cleanliness requirements and inspections during fabrication and fuel loading operations ensure that the MPC has minimal surface debris and impurities.

Tests on Metamic-HT Extensive tests [8.9.7] have been conducted to establish material properties of Metamic-HT including its corrosion-resistance characteristics. The Metamic-HT specimens were used for corrosion testing in demineralized water and in 2000 ppm boric acid solution. The tests concluded that the Metamic-HT panels will sustain no discernible degradation due to corrosion when subjected to the severe thermal and aqueous environment that exists around a fuel basket during fuel loading or unloading conditions.

Aluminum Alloy Aluminum alloy used in the fuel basket shims are hard anodized. The anodizing is an electrolytic passivation process used to increase the thickness of the natural oxide layer on the su1face of metal parts. Anodizing increases corrosion resistance and wear resistance of the material surface.

There is no mechanistic process for the basket shims with hard anodized surface to react with borated water or demineralized water during fuel loading operation. Under the long-term storage condition, the basket shims are exposed to dry and inert helium with no potential for reaction.

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I IOLTEG PROPRIET.ARY INFORM4IION Effect of Forced Helium Dehydration (FHD) Process The operation of the FHD consists of flowing hot dry helium through the MPC at pressures and temperature limited by the MPC design pressure and temperature of the MPC. Due to the purity of the helium stream and the relatively short duration (normally 10 to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />), no significant corrosion mechanisms are identified.

Maintenance of Helium Atmosphere The inert helium atmosphere in the MPC provides a non-oxidizing environment for the SNF cladding to assure its integrity during long-tenn storage. The preservation of the helium atmosphere in the MPC is assured by the robust design of the MPC Confinement Boundary (see Section 7. l). Maintaining an ine1t environment in the MPC mitigates conditions that might otherwise lead to SNF cladding failures. The required mass quantity of helium backfilled into the canister at the time of closure and the associated fabrication and closure requirements for the canister are specifically set down to assure that an inert helium atmosphere is maintained in the canister throughout the MPC's service life.

Allowable Fuel Cladding Temperatures The helium atmosphere in the MPC promotes heat removal and thus reduces SNF cladding temperatures during dry storage. In addition, the SNF decay heat will substantially attenuate over the dry storage period. Maintaining the fuel cladding temperatures below allowable levels during long-term dry storage mitigates the damage mechanism that might otherwise lead to SNF cladding failures. The allowable long-term SNF cladding temperatures used for thermal acceptance of the MPC design are conservatively determined, as discussed in Section 4.3.

8.12.2.3 Galvanic Co1TOsion The MPC is principally constructed of stainless steel shell and Metamic-HT. Borated aluminum and stainless steel have been used in close proximity in wet storage for over 30 years. Many spent fuel pools at nuclear plants contain fuel racks, which are fabricated from Metamic (classic) and stainless steel materials. Not one case of chemical or galvanic degradation has been found in such fuel racks. This experience provides a sound basis to conclude that corrosion will not occur in these materials. For further protection, both Metamic-HT and aluminum basket shims are installed in the anodized state in the MPC.

Furthermore, galvanic corrosion is not an applicable mechanism since the interior of the MPC during normal operation is essentially devoid of any moisture and the MPC shell surfaces are expected to be practically free from condensation. Finally, the interior of the carbon steel HI-STORM FW overpack is painted to inhibit corrosion.

During long-term storage in the HI-STORM FW overpack, the MPC operates at elevated temperatures under normal conditions while inside the HI-STORM. The external ambient environment normally consists of atmospheric conditions, which include humidity and perhaps airborne contaminants such as sulfur dioxide, chlorine gas, sulfur gas and ozone. The interior is HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-38 Rev. 5

HOLTEC f!IRO~RIETARY lt~FORMATION backfilled with highly pure helium. The spent fuel irradiates the MPC but at much lower levels than those experienced in an operating reactor. It is recognized that in general the higher the temperature the higher the rate of chemical reaction. It is also recognized that moistme will not exist on the MPC exterior surfaces for many years since moisture will not condense on hot surfaces and the protection afforded by the HI-STORM FW overpack. It is estimated that it would take decades for the hottest MPC to approach ambient temperatures and once at ambient temperature, any MPC surfaces will be highly corrosion resistance even when wet.

8.12.2.4 Cyclic Fatigue As discussed in Section 3.1, passive non-cyclic nature of dry storage conditions does not subject the MPC to conditions that might lead to structural fatigue failure. Ambient temperature and insolation cycling during normal dry storage conditions and the resulting fluctuations in MPC thermal gradients and internal pressure is the only mechanism for fatigue. These low-stress, high-cycle conditions cannot lead to a fatigue failure of the MPC that is made from stainless alloy stock ( endurance limit well in excess of 20,000 psi). All other off-nonnal or postulated accident conditions are infrequent or one-time occurrences, which cannot produce fatigue failures.

8.12.3 Compatibility of HI-STORM FW Overpack Materials The principal operational considerations that bear on the adequacy of the storage overpack for the service life are addressed as follows:

Exposure to Environmental Effects All exposed surfaces of the HI-STORM FW overpack are made from ferritic steels that are readily painted. Concrete, which serves strictly as a shielding material, is encased in steel.

Therefore, the potential of environmental vagaries such as spalling of concrete, are ruled out for HI-STORM FW overpack. Under normal storage conditions, the bulk temperature of the HI-STORM FW overpack will change very gradually with time because of its large thermal inertia.

Therefore, material degradation from rapid thermal ramping conditions is not credible for the HI-STORM FW overpack. Similarly, corrosion of structural steel embedded in the concrete strnctures due to salinity in the environment at coastal sites is not a concern for HI-STORM FW because HI-STORM FW does not rely on rebars (indeed, it contains no rebars). As discussed in Appendix l.D of the HI-STORM 100 FSAR, the aggregates, cement and water used in the storage cask concrete are adequately controlled to provide high durability and resistance to temperature effects. The configuration of the storage overpack assures resistance to freeze-thaw degradation. In addition, the storage overpack is specifically designed for a full range of enveloping design basis natural phenomena that could occur over the service life of the storage overpack as catalogued in Section 2.2 and evaluated in Chapter 11.

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lelObTi;C PROPRIETARY INFORMATION Material Degradation The relatively low neutron flux to which the storage overpack is subjected cannot produce measurable degradation of the cask's material properties and impair its intended safety function.

Exposed carbon steel components are coated to prevent corrosion. The ambient environment of the ISFSI storage pad mitigates damage due to exposure to corrosive and aggressive chemicals that may be produced at other industrial plants in the surrounding area.

Maintenance and Inspection Provisions The requirements for periodic inspection and maintenance of the storage overpack throughout its service life are defined in Section 10.2. These requirements include provisions for routine inspection of the storage overpack exterior and periodic visual verification that the ventilation flow paths of the storage overpack are free and clear of debris. TSFSis located in areas subject to atmospheric conditions that may degrade the storage cask or canister should be evaluated by the licensee on a site-specific basis to determine the frequency for such inspections to assure long-term performance. In addition, the HI-STORM FW system is designed for easy retrieval of the MPC from the storage overpack should it become necessary to perform more detailed inspections and repairs on the storage overpack.

The above findings are consistent with those of the NRC's Waste Confidence Decision Review

[8.12.5], which concluded that dry storage systems designed, fabricated, inspected, and operate in accordance with such requirements are adequate for a 100-year service life while satisfying the requirements of 1 OCFR72.

8.12.4 Compatibility of HI-TRAC VW Transfer Cask Materials The principal design considerations that bear on the adequacy of the HT-TRAC VW Transfer Cask for the service life are addressed as follows:

Exposure to Environmental Effects All transfer cask materials that come in contact with the spent fuel pool are coated to facilitate decontamination. The HI-TRAC VW is designed for repeated normal condition handling operations with a high factor of safety to assure structural integrity. The resulting cyclic loading produces stresses that are well below the endurance limit of the cask's materials, and therefore, will not lead to a fatigue failure in the transfer cask. All other off-normal or postulated accident conditions are infrequent or one-time occurrences that do not contribute significantly to fatigue.

In addition, the transfer cask utilizes materials that are not susceptible to brittle fracture during the lowest temperature permitted for loading, as discussed in Section 8.4 in the foregoing.

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HOLTEC PROPRIETARY INFORMATIOl<l Material Degradation All transfer cask materials that are susceptible to corrosion are coated. The controlled environment in which the HI-TRAC VW is used mitigates damage due to direct exposure to co1rnsive chemicals that may be present in other industrial applications. The infrequent use and relatively low neutron flux to which the HI-TRAC VW materials are subjected do not result in radiation embrittlement or degradation of the shielding materials in the HI-TRAC VW that could impair the intended safety function. The HI-TRAC VW transfer cask materials have been selected for durability and wear resistance for their deployment.

Maintenance and Inspection Provisions The requirements for periodic inspection and maintenance of the HI-TRAC VW transfer cask throughout its service life are defined in Section 10.2. These requirements include provisions for routine inspection of the HI-TRAC VW transfer cask for damage prior to each use. Precautions are taken during bottom lid handling operations to protect the sealing surfaces of the bottom lid.

The leak tightness of the liquid neutron shield is verified periodically. The water jacket pressure relief devices and connections for water injection/removal have been engineered for convenient removal and replacement.

8.12.5 Potential Combustible Gas Generation To ensure safe fuel loading operation the operating procedure described in Chapter 9 provides for the monitoring of hydrogen gas in the area around the MPC lid prior to and during welding or cutting activities. Although the aluminum surfaces (Metamic-HT basket and aluminum basket shims) are anodized, there is still a potential for generation of hydrogen in minute amounts when immersed in spent fuel pool water for an extended period. Accordingly, as a defense-in-depth measure, the lid welding procedure requires purging the space below the MPC lid prior to and during welding or cutting operation to eliminate any potential for formation of any combustible mixture of hydrogen and oxygen. Following the completion of the MPC lid welding and hydrostatic testing the MPC is drained and dried. As discussed earlier, after the completion of the drying operation there is no credible mechanism for any combustible gases to be generated within the MPC.

8.12.6 Oxidation of Fuel During Loading/Unloading Operations During the loading and unloading operations in a spent fuel pool, the fuel cladding is surrounded by water. During fuel drying operation the water is displaced with a non-oxidizing gas environment. Therefore, there is no credible mechanism for oxidation of fuel.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-41 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

MOLTEC PROPRIETARY INFORMA I ION 8.12.7 Conclusion The above discussion leads to the conclusion that the materials selected for the HI-STORM FW System components are compatible with the environment for all operating conditions. There is no potential for significant corrosion, chemical reaction or galvanic reaction to shorten the intended service life of the equipment. In other words, the acceptance criteria set forth in ISG-15 are completely satisfied.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-42 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HOL'fEC PROPRIETARY INFORMATION 8.13 FUEL CLADDING INTEGRITY 8.13.1 Regulatory Guidance The acceptance criteria from ISG-1 1 that apply to the fuel cladding are:

a.

For all fuel burnups (low and high), the maximum calculated fuel cladding temperature should not exceed 400°C (752°F) for normal conditions of storage and short-term loading operations ( e.g., drying, backfilling with inert gas, and transfer of the cask to the storage pad).

However, for low burnup fuel, a higher short-term temperature limit may be used, if it can be shown by calculation that the best estimate cladding hoop stress is equal to or less than 90 MPa (13.053 psi) for the temperature limit proposed.

b.

During loading operations, for high burnup fuel, repeated thermal cycling (repeated heatup/cooldown cycles) may occur but should be limited to less than 10 cycles, with cladding temperature variations that are less than 65°C (149°F) each.

c.

For off-normal and accident conditions, the maximum cladding temperature should not exceed 570°C (1058°F).

The ISG-15 guidance on cladding integrity in its entirety provides the following supplemental requirements:

a. The cladding temperature should be maintained below maximum allowable limits, and an inert environment should be maintained inside the cask cavity to maintain reasonable assurance that the spent fuel cladding will be protected against degradation that may lead to gross rupture, loss of retrievability, or severe degradation.

b. Cladding should not rupture during re-flood operations.

8.13.2Measures to Meet Regulatory Guidance The HI-STORM FW System features and processes minimize the potential for any spent fuel cladding degradation during transfer and storage conditions by limiting the fuel cladding temperature and the environment around the fuel rod to within ISG-1 1 limits (Table 4.3.1 ).

The highly pure helium under positive pressure in the canister limits the amount of oxidants and controls the cladding temperature. The MPC drying and helium backfilling operations result in the creation of an inert environment around the fuel. As prescribed by NUREG-1536 [8.3.3), if the classical vacuum drying method is used, the partial pressure of water vapor is brought down to below 3 torr to minimize [8.13.1] residual oxidizing gas concentration.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-43 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

lelOLTEC PROPRIETARY l~FORMA I ICJJ'r An alternative method (preferred) for drying the MPC internals utilizes Holtec's patented Forced Helium Dehydration technology [8.13.1, 8.13.2] described in the HI-STORM 100 FSAR (Appendix 2.B). The Forced Helium Dehydrator has been successfully used at numerous nuclear plants since its regulatory approval in 2001. The efficacy of the Forced Gas Dehydrator (FGD) has been tested in a full-scale demonstration [8.13.4] for demoisturizing simulated water-logged RBMK fuel [8.13.3].

The FHD uses helium as the working substance. The use of the FHD prevents the elevation of the fuel cladding temperature during drying, which is a chief demerit of the vacuum drying method. The use of the FHD method of drying is compulsory for high burnup fuel to protect its (relatively) ductility challenged cladding from severe thermal transients.

Chapter 2 provides the allowable fuel cladding temperature limits along with other design conditions. Chapter 4 presents performance evaluation of the HI-STORM FW System under normal conditions of storage, MPC temperatures during moisture removal operations and HI-STORM FW System long term storage maximum temperature conditions. Chapter 4 provides MPC temperatures under various accident conditions. It is demonstrated that the maximum calculated fuel cladding temperature is within 400°C (752°F) with substantial margins for normal conditions of storage and short-term loading operations. For off-normal and accident conditions, the maximum cladding temperature does not exceed 570°C (1058°F).

The short-term operations described in Chapter 9 are specifically configured to prevent severe thermal stresses in the fuel cladding due to rapid thermal transients.

The thermal stresses from MPC reflood analysis during fuel unloading operations shall be lower than typical MPCs because the HI-STORM FW fuel assemblies operate at considerably lower temperatures at Design Basis heat loads (see Chapter 4) than is permitted by ISG-11.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-44 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 8.14 EXAMINATION AND TESTING Examination and testing are integral parts of manufacturing of the HI-STORM FW System components. A comprehensive discussion on the examinations and testing that are conducted during the manufacturing process is provided in Section 10.1. The applicable codes and standards used are also referred and the acceptance criteria are listed.

8.14.1 Helium Leak Testing of Canister &Welds Helium leakage testing of the MPC base metals (shell, baseplate, and MPC lid) and MPC shell to baseplate and shell to shell welds shall be performed in accordance with the leakage test methods and procedures of ANSI N14.5 [8.14.1]. Acceptance criterion is specified in Chapter 10. Testing shall be performed in accordance with written and approved procedures.

Leak testing results for the MPC shall be documented and shall become part of the quality record documentation package.

The helium leakage test of the vent and drain port cover plate welds shall be performed using a helium mass spectrometer leak detector (MSLD). If a leakage rate exceeding the acceptance criterion is detected, then the area of leakage shall be determined and the area repaired per ASME Code Section III, Subsection NB, Article NB-4450 requirements. Re-testing shall be perfotmed until the leakage rate acceptance criteria are met.

Leakage testing of the field welded MPC lid-to-shell weld and closure ring welds are not required.

Leakage testing of the vent and drain port cover plate welds shall be performed after welding of the cover plates and subsequent NDE. The description and procedures for these field leakage tests are provided in Chapter 9 of this SAR and the acceptance criteria are defined in the Technical Specifications for the HI-STORM FW System.

8.14.2 Periodic Inspections Post-fabrication inspections are discussed in Section 10.2 as part of the HI-STORM FW System maintenance program. Inspections are conducted prior to fuel loading or prior to each fuel handling campaign. Other periodic inspections are conducted during storage.

The HI-STORM FW overpack is a passive device with no moving parts. Overpack vent screens are inspected monthly for damage, holes, etc. The overpack external smface including identification markings is visually examined annually. The temperature monitoring system, if used, is inspected per licensee's QA program and manufacturer's recommendations. HI-TRAC VW transfer cask visual inspection is performed annually for compliance with the licensing drawings.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-45 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

AOL I EC PROPRIE I ARV INFORMATION 8.15 CONCLUSION The preceding sections describe the materials used in important to safety SSCs and the suitability of those materials for their intended functions in the HI-STORM FW System.

The requirements of 10CFR72.122(a) are met: The material properties of SSCs important to safety conform to quality standards commensurate with their safety functions.

The requirements of 10CFR72.104(a), 106(b), 124, and 128(a)(2) are met: Materials used for criticality control and shielding are adequately designed and specified to perform their intended function.

The requirements of 10CFR72.122(h)(l) and 236(h) are met: The design of the DCSS and the selection of materials adequately protect the spent fuel cladding against degradation that might otherwise lead to gross rupture of the cladding.

The requirements of 10CFR72.236(h) and 236(m) are met: The material properties of SSCs impo1tant to safety will be maintained during normal, off-normal, and accident conditions of operation as well as short-term operations so the spent fuel or MPC, as appropriate, can be readily retrieved without posing operational safety problems.

The requirements of 1 OCFR 72.236(g) are met: The material prope1ties of SSCs important to safety will be maintained during all conditions of operation so the spent fuel can be safely stored for the specified service life and maintenance can be conducted as required.

The requirements of 10CFR72.236(h) are met: The HI-STORM FW System employs materials that are compatible with wet and dry spent fuel loading and unloading operations and facilities.

These materials should not degrade over time or react with one another during long-term storage.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-46 Rev. 5

HOLTEC PROPRIETARY INFORMA I luff""

8.16 REFERENCES

[8.1.1] ISG-15, "Materials Evaluation," U.S. Nuclear Regulatory Commission, Washington, DC, Revision 0, January 2001.

[8.1.2] ISG-11, "Cladding Considerations for the Transportation and Storage of Spent Fuel,"

U.S. Regulatory Commission, Washington, DC, November 2003.

[8.3.1] ASME Boiler and Pressure Vessel Code, American Society of Mechanical Engineers, New York, NY, (2007).

[8.3.2] ACI 318-2005, "Building Code Requirements for Structural Concrete," American Concrete Institute, Ann Arbor, Ml.

[8.3.3] NUREG-1536, "Standard Review Plan for Dry Cask Storage Systems," U.S. Nuclear Regulatory Commission, Washington, DC, January 1997.

[8.4.l] ASME Boiler & Pressure Vessel Code,Section III, Part D, 2007 Edition.

[8.5.1] Holtec Position Paper DS-329, "Stress Limits, Weld Categories, and Service Conditions",

(Holtec Proprietary).

[8.5.2] Holtec Position Paper DS-213, "Acceptable Flaw Size in MPC Lid-to-Shell Welds" (Holtec Proprietary)

[8.7.1] Holtec Standard Procedure HSP-318, "Procedure for Blasting and Painting HI-TRAC Overpacks and Associated Components." (Holtec Proprietary)

[8.7.2] Holtec Standard Procedure HSP-319, "Procedure for Surface Preparation and Painting of HI-STORM 100 and lOOS Overpacks." (Holtec Proprietary)

[8.8. l] A.M. Neville, "Properties of Concrete," Fourth Edition, Addison Wesley Longman, 1996.

[8.9.1] Turner, S.E., "Reactivity Effects of Streaming Between Discrete Boron Carbide Particles in Neutron Absorber Panels for Storage or Transpo11 of Spent Nuclear Fuel," Nuclear Science and Engineering, Vol. 151, Nov. 2005, pp. 344-347.

[8.9.2] "HI-STORM 100 Final Safety Analysis Report", Holtec Report HI-2002444, latest revision, Docket No. 72-1014.

[8.9.3] USNRC Docket No. 72-1004 SER on NUHOMS 61BT (2002).

[8.9.4] "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Holtec International Report HI-2022871 Regarding Use of Metamic in Fuel Pool Applications,"

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-47 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATIOl<l Facility Operating License Nos. DPR-51 and NPF-6, Entergy Operations, Inc., docket No. 50-313 and 50-368, USNRC, June 2003.

[8.9.5] Natrella, M.G., "Experimental Statistics, "National Bureau of Standards Handbook 91, National Bureau of Standards, Washington, DC, 1963.

[8.9.6] "Metamic-HT Manufacturing Manual", Nanotec Metals Division, Holtec International, Latest Revision (Holtec Proprietary).

[8.9.7] "Metamic-HT Qualification Sourcebook",

Holtec Repott No. HI-2084122, Latest Revision (Holtec Proprietary).

[8.9.8] "Sampling Procedures and Tables for Inspection by Attributes", Military Standard MIL-STD-105E, ( l 0/5/1989).

[8.11.1] "Mechanical Design of Heat Exchangers and Pressure Vessel Components", K.P.

Singh and A.I. Soler, Arcturus Publishers, 1984.

[8.12.1] Craig and Anderson, "Handbook of Co1rnsion Data," A.SM International, First Ed.,

1995.

[8.12.2] ASME Boiler and Pressure Vessel Code,Section II, Part A - Ferrous Material Specifications," American Society of Mechanical Engineers, New York, NY, 2007 Edition.

[8.12.3) Holtec Position Paper DS-330, "Estimating an Upper Bound on the Cumulative Corrosion in Stainless Steel MPCs in Highly Corrosive Environments." (Holtec Proprietary)

[8.12.4) Peckner and Bernstein, "Handbook of Stainless Steels," First Ed., 1977.

[8.12.5] 10CFR, Waste Confidence Design Review, USNRC, September 11,1990.

[8. 12.6) Fontana G. Mars, "Corrosion Engineering," Third Edition, 1986.

[8.13.1) PNL-6365, "Evaluation of Cover Gas lnpurities and their Effects on the Dry Storage of L WR Spent Fuel," Pacific Northwest Laboratory, Richland, WA, November 1987.

[8.13.2] Holtec Patent No. 7,096,600B2, "Forced Gas Flow Canister Dehydration)), August 29, 2006.

[8.13.3] Holtec Patent No. 7,210,24 7B2, "Forced Gas Flow Canister Dehydration", May I, 2007

[8.13.4) Holtec Report No. HI-2084060, "FGD Performance Test Program for ISF-2 Project for Chernobyl Nuclear Plant," 2008.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8-48 Rev. 5

HOLTEC PROPRIETARY INFORMATION

[8.14. l] American National Standards Institute, Institute for Nuclear Materials Management, "American National Standard for Radioactive Materials Leakage Tests on Packages for Shipment", ANSI Nl4.5, January 1997.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8-49 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

1 IOLTEC PROPRIETARY INFORMATION APPENDIX 8.A Datasheets for Coatings and Paints§

§ The materials in this Appendix can also be found in the suppliers' website.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8.A-1 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HO! IEC PROPRIETARY INFORMATION Selection & Specification Data Generic Type Description Features Color Finish Primers Topcoats Dry FIim Thickness Solids Content Theoretical Coverage Rate voe Values Dry Temp.

Resistance Cycloaliphalic Amine EP""Y Highly chemical resistant epoxy masUc coating with exceptionaly...,,satile uses in all industrial markets.

Sedf-primltig and suitable for application """' most existing coatings, and tightly adherent to rusl Carboguard 890 serves as stand-alone system for a vartety of chemical environments. Carboguard 8&0 is also d!'signed for various: immersion conffltlons.

Excellent chem1cal resistance Surfac$ tolerant charactenstJcs Conventtonal and low-temp~ture versions Selfwpriming and pnmerffinish capab4Uties Very good abrasion resistance voe compliant to current AIM regulations SU<abte for use In USDA inspected fac:iNtles Refer to CarboNne Color Guide. Certain colors may reQIJh muklple coats for hiding. Note: The low temperalure formulation will cause most colors to yellow a discolor more than normal in a short period of time. (Epoxies lose gloss, discolor and chalk in sunlight exposure.)

Gloss Self* priming. May be apptied over inorganic zinc primers and other tightly adhering ooatings. A mist coat may be required to minimize bubbling O\\/Or inorganic zinc primers.

AcryNc,i, Epoxies, Polyurethanes 4.0-6.0 mils (100-150 microns) per coat 6.0-8.0 mils (150-200 microns) <Nor light rust and for uniform gloss over Inorganic zincs.

Donl exceed 10 mils (250 microns) in a single coat Excessive film thickness over Inorganic zinc,, may increase damage during shipping Of erection.

By Volume (890):

75% +/- 2%

(890L T):

80% +/- 2%

890:

1203 mil ft2(30.0 m'n at 25 microns) 241 n' al 5 mils (6.0 m'n at 125 microns) 890LT:

1283 mil ft2(31.0 m'n at 25 microns) 257 ft2 at 5 mils (6,3 m'n at 125 microns)

Allow for loss in mixing and application As supplied Thinned wllf2':

ll2

1. 71bs/gal (214 gn) 7ozlgal=2.0lbs/gal (250g/l) 13oz/gal=2.21bs/gal

<211gm

.mJ.I 1.Slbs/gal (180gn) 15oz/gat=2.0lbs/gal (2S0g!)

Thinned 7ozlgal=2.0lbslgal 14oz/gal=2.0 wllfJ3':

(250g/l) lbs/gal (2509! )

16oz/gal=2.31bs/gal 16oz/gal=2.11bs/gal

<28Sgn)

(258g!)

'Use Thinner #76 up to 8 o,/gal for 8&0 and 16 oz/gal for 890 LT 'Where non*photoc:hemically reacUve sol=ts are requ~ed.

Continuous:

250'F (121'C)

Non-Continuous:

300*F (148"C)

Discoloration and loss of gloss Is observed above 200°F (93'C).

Limllatlons Do not apply owr latex coatings. Fa-immersion April 2007 replaces February 2007 CarboguarcP 890

& 890 LT projecls use only factory made material lh special colors. Consult Technical SeeAoe tor specific,,.

Carboguard 890 LT should net ba used for lmmer!;lon and should only be used as a primer or lntermedlale

coat, Di,coloro!on m1y be objectionable If used as a topcoat, Substrates & Surface Preparation Gener al Steel Galvanized Steel Concrete orCMU Drywall &

Plaster Prevtously Painted Surfaces Surfilces musl be clean emd dry, Em~oy eide~a.te mttlio<a to ftmove dirt, tllst.. oil and all oth9r contaminants that could kiterfere with aclieslon of lhe

coating, l'"'""r~on SSPC-SP10 Non*mmarsion; SSPC.SP6 1.s.s.o ml* (38-75 mlcr..,,J SSPC*SP2 or SP3 are suitable cleaning methods for mild environments.

Prim* whh specific C1rb0Un1 primers as recommended by your Carboline Sales Representative. Refer to the specific primer's Product Data Sheet for substrate prepar e.tlon requirement,.

Concrete must be cured 28 days 111 75°F (24°C) and 50%

relative humidity or equivalant. Prepare surfaces in eccordatlCe with ASTM 04258 Su1face Cleaning or Coner<<* and ASTM 04259 Abrading Concrete. Voids in concrete may require surfacing. Mortar Joints should be cured

• min of 16 days. Prime with ltselt, Carboguard' 1340, or $Uitable lller/sHler.

Joint compcxind and pt111er should be lllty cured prk>r to coating applacation. Prime wieh Carbocryicci 120 or Carbog.iard 1340.

Lightly sand or abrade to roughen surface a nd degloss the surface. Existing paint musl attain a minimum 38 rating in 11.ccordance with ASTM 03359 ~x-Saibe' 1<1iesJon t11t.

Performance Data Test Method System Results Report#

ASTM D33611 81,otodStool 5A 0270 Adhesion 1 ct. 890 ASTM D4060 Blasted Steel 85 mg. loss after 1000 Abrasion 1 ct. Epoxy Pr.

cydo~ CS17 whool.

02411 1 ct. 890 1000 gm. load No effect on plan.. rust ASTM 6117 Blasted Steel In scribe. 1/16" 02594 Salt Fog 2 cts. 890 undercutting at scribe after 2000 hou~

Bl, otedStoel No effect on p41n1, no ASrM B\\17 1 ct.lOZ rust in s.eribe and no L40-Salt Fog 1 ct. 890 undercutting after 42.45,95 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> ASTM 01735 Blasted Steel No blistering, rusting or Water Fog 1 cl Epoxy Pr.

delamination after 2800 08564 1 ct. 890 hours0.0103 days <br />0.247 hours <br />0.00147 weeks <br />3.38645e-4 months <br /> ASTM D3363 Blc1sted Steel Greater than 8H 02775 Ptncit Herdntu 2 cts. 890 ASTM D2496 Blasted Steal 83% gloss,etaintd liter Scrub 1 ct. 890 10,000 cycles w/ liq.,id 03142 Resistance saubmedium ASTM E84 5 Flame Flame and 2 ct. 890 5 Smoke 03110 Smoke Ctan A Test reports and additional data available upon wntten request.

09-83 HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 Rev. 5 8.A-2 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

---

i-!OLTEC PROPRIETARY INFORMATION Carboguar~ 890 & 890 LT Ap lication E ui ment Llsled below are general equipment guldellnn for the appllcatlon oflhls product. Job site conditions may require modlftcallons to thtst guk:ltllnts lo actiltw lht desired rnuh. Otnwal Ould1Hnn :

Spray Application This is a high solids: coating and may re(I.Jire (General) adjustment, In spray techniques. WfA film thickness is H~ly i nd quickly aci-.eved. Thi following sproy equipment has been found suitable and is available tom manufacturers such as Binks, OeVilbiss and Guco.

Convention al Spray AirleH Spray Brush & Roller (GeneraQ BruSh Roller Pressure pot equipped with dial regulators, 318* 1.0.

minimum mat11MII hos-..010~ I 0. nuid tip l.fld appropriate elr cap.

Pump Ratio:

GPM Output:

Material Hose:

Tip Size:

Output PSI:

FIiter Size:

30:1 (rrin.)'

3.0(mln.)

318" I.D. (min.)

.017'*.021' 210().2300 60 mesh

' Teffon packings are recommended and available from tht pump manufaclUttr.

Mutl:lple coat'!. may be r~uired to o~aln des.Ired appearance, recommended dry film thickness and 1dequ1tt hldng. Avoid txcnslve r*bru1hlng or rt-rolling. For best rewlts, tl&-11'11 within 1 O minutes at 75"F (24"C).

Use a medium brls.tle brush.

Use I shorl*n1p synthetic roller cover with phenolic core.

Mixing & Thinnin Mixing Rado PotLtre Powtr mbc separattly, then combine and power mix.

DO NOT MIX PARTIAL KITS.

890 end 890 LT 1:1 Rollo (Ato B)

Spn,y:

Up to 13 oz/g*I (1 0%) w/ #2 Bru,h:

Up to 16 oz/g*I (1 2%) w/ #33 Rohr:

Up to 16 oz/gal (12%) w/#33 Thinner #33 can be used for spray in hotwindy condiiions. Use of thinners other than those supplied or recommended by Carbotine may 11dver1tly affect product p*formance and void product warranty, whether expressed or imp+ied.

• s.. voe values for thinning limits.

890 3 Hours at 75°F (24°C) 890 LT 2 Hours et 75°F (24'C)

Pot Wfe tnds when coating losts boaj and b~lns to s.a.g, Pot life ~mes w~I be less at higher temperatures.

Cleanu & Safety Cleanup sore ty Ct1UtJoo Use Thlriner #2 or Acetone. In cas. of splltge, absorb and dspost of In 1ccordllnc1 wilh locel 1ppllc1ble regulations.

R11d and follow 111 caution st1t1m1nts on this product data sheet and on the MSDS for this product. Employ normal workmanlike safety precautiom.. Hypersensitive persons should wHr protectiw dod'ling, gkwes and uu protective crHm on face, harads and all exposed artas.

vVhen osed 1s

• link lin1mg Of in enc)Hed *reas-,

lho,ough air cl,cuhltlon mu1i be ui.d during and -d*r eppUcation onti1 the coatlng1 Is cllfed. n,. v.ntilarion

,yst.m should be capflble o( prttVttflting Ute sotveot vapor concentration from,e1chlng lh1 low~ 1w:plo.1ion 1,~ for the solvents: used. User shoufd teit end mM~Ot

• xi>osur* levels to insure

• 11 pltfsonnlN are b.-ow gu1dt41n11. If l'lol sure or If not able to mo.nltor ltvtb, uu MSHAJNK>SH apprcwtd suppOwd 1ir r1sp1r.to,,

Th11 prodi.lct conta!n:s h mmeble $CJV8nts. Knp sway ftom.sp1r1', and opan bm*** All electJlc1I 11qulpm9nl illnd 1n~Wllations Vlou~ bo mode a,id grounde.d m accoutance with the N.iiona1 Ele~ric Coe* Jn,,..,

wh1r1 e,cplo-s:lon hanrck *Kist. workmen -ahould be rsqulred to Use flookr.rrou~ tools al'Ki ~ea, conduetlv*

1nd non*~parkfng -Vloe.-a, A

lication Conditions Condition Malerlal S...-face Ambient Humldltv Nom,11 eo*.0s*F 60"*85°F 60"*90°F 0.80%

116' -29'CI 116'-29"CI 118'-32'CI Mintmum so*F 50°F 50<>F 0%

(IO'C) 11o*c1 (10'C)

Maximum 0o*F 125°F 110°F 80%

/32'CI 1s2*c1

/43"Cl HO LT Normat 60~85°F 6().95' F 6().9QOF 10.80%

(16-29'CI

/16-29°Cl 116-32"Cl Minimum 40°F 35°F 35"f 0%

(4'Cl (2'C)

(2"C)

Maximum 90°F 125°F 110°F 80%

/32'CI 152' Cl

/43"C)

This product smply requires the S-ubsb'ate temperature to be above the dew point. Condensation due to substrate temperatures bekffl the dew point can cause ftuh rusting on prepared sttel and lnttrfwt with proper adhaslon to tht substrate. Special application techniques may be required above or below normal application conditions.

Curing Schedule 880 (Based on 4-8 mils. 100-200 microns drv lllm thickness.)

Surface Temp.

Dry lo Dry to Topcoat P'lnal Cure

& 50% Relative w/Other Humldltv Recoat Finishes General Immersion 51l"F IIO'C 12 Hours 24 H04.H 3 01ys N/R 61l"F /16"C B Hours 16 Hours 2 Days 10 Day~

75°F (24'C 4 Hours 8 Hours 1 Dav 5 DI VS 91l"F 132'C 2 Hours 4 Hours 18Hours 3 Days 890LT Based on 5 mils., 125 microns d~ film thickness.)

Surface Dry to l'lnal Cure Temp. &

Dry to Ory to Recoal &

General 50% Reladve Touch Handle Topcoat w/

Service HLmldJIV Others 35'F <2"CI SHouu 18 Hours 20 Hours 7 DIVS 4QClF 4°0\\

4.5 Hours 15.5 Hours 16 Hours 5 Oavs 50°F 1o*c1 3.5Hours 6.5Hours 12Hours 3 Dovo 60'F 19*c 1 2 Hours 5 Hours 8 Hours 2 Deyo 75°F 24°Cl 1.5Hours 2 Hours 4Hours 24 Hours 90' F 32*c1 1 Hour l.5Hours 2 Hours 16 Hours Higher film thickness, r,suflcient vent1latlon or cooler temperatures W1N reqiulre longer cure times Bnd could result in solvent entrapm11t1t and prenlilture failure.

Exc,nive humidity or condensation on the surface during curing cen lnttt'"9rt with the cure, can cause discoloration and may result k'I I wrface haze. Ally haze or blush must be removed by water washing before recoating. During high humidity conditions, It Is recommended that tht application be done wtillt temperatufls are incrHslng. Maximum recoat/topcoat limes are 30 days for epoxtes and 90 days for polyurethanes at 750f (24-C). If the maximum rec.oat times have been exceeded, the surface ft'WJSt be ab,aded by sweep blasting Of sanding prio, to the applicaUon of additional coals. 890 LT applied below 60°F (10°C) may temporarify soften as temperatures rise lo 60°F (18°C). This is a normal concfltlon end win not affect performance.

Packaging, Handling & Storage Shipping Weight (Approxlma1e) flasn Point (Selaflash) s1orage Tempemure

&H001ldlty 6h*II Ure:

890 & 890LT

' Shelf Llfa: (actual stated shelf Ille I when kept at recommended storage conditions and In original unopened containers.

~ ~

29 1bs(13kg) 1451bs(66 kg) 89'F (32"C) for Port A: 890 & 890 LT 73* F (23"C) ~r Part B: 890 & 890 LT 40 - t11l"F(4' -4ll"C) &oro,ndoo,.

0.10014 ~elotlv* Humidity Patt A: Min. 36 months at 75-'F (24"C) 890 P*t B: Min. 15 month& I I 75*F (24-"C) 890 LT Pwt 8: Min. t!, monthsal 75' f (24'C) lSOTllllkyl~Oowr,,8\\.1..ai'Y, MOfill.U.1.ff;t l l~1000 >1~"7(fb)tll'ww.cwWIIIILami HOLTEC INTERNATIONAL COPYRIGHTED INFORMATfON REPORT Hl-2114830 8.A-3 HI-STORM FW SYSTEM FSAR Revision 5. June 20, 2017 Rev. 5

HOU:EC PROPRIETARY INFORMATION Selection & Specification Data Gener1o. Type Ducrtpllon featurew CZ 11FQ Color Fln1Sh Primers Topcoals Dry FIim TI'llckness Solids Cortent Zinc Content In drylllm Theoretical c overage Rate voe Valuos Carbozinc 11 voe Values Carbozlnc 11 FG Ory Temp.

Resistance Solvenl Based Inorganic Zinc Tlm*test1d co,roslon resis1ao~ p,imer th1t prot.cts

<Steel galvanicafy In the harshest environments. For over four decade*, Clllr'bozmc: t 1 (CZ 11) has been the k,duslry stendard for high,performanct 1'10,ganlc.zinc PfOl~tJOl"t on ~teu!1I strudures wo1dwlde, CZ 11 e.nd CZ 11 FG meet Class 8 slip co-efficient and cre,p testlng criteria for U$t on ray,ng surfaces RapPd curt. Or)' to handle W1 45 rrinutH,t 600F (16*C) and 60%,.satlv" 11untklily low temperature cure dov.,i to C>9F (-19"C)

High zinc loedng.

MHtt FDA rtquiremtntt 11, gray color.

Available in ASTM D520, Type II zinc version.

Very good reslsteince 10 $alting.

May be appNed with standMd 1itless °' convtntl04"tal s.pray equipment.

VOC compliant Wl certain areas lower zinc loadng for economics.

voe compliant for shop/fabricator use ont,;.

Groon (0300); Gray (0700)

Flat Self Priming Not raquir*d for c:artain exposuras. Can be topcoated with

EpoxlH, Potyu1tthen11, Acr~c,.

H1"1*HHt Silicones and others as recommended by yoor C11rbollne ules

,epresentative.

Under certain conditions, 1 mist coat ls tM1ulrtd to minimize topcoat bubbling.

2.0-3.0 mils (60-75 mk:ron1). Ory film lhicl<n,u In exctss of 6.0 mtls (160 microns) per coet Is not recommended.

~!tZ...ll...Ell.

ByWelg,t:

79% t 2%

74%+/-2"4 By W~~t:

85% t 2%

CZ 11: 1000 mil ft~ (22.8 m111 at 25 microns) 333 ft' ot 3.0 m,ls (8.2 m'~ ot 75 micron,)

CZ 11 FG: 850 mil 11:1(19.4 m2A at 25 microns) 283 ft2 at 3.0 mils (7.0 m211 et 75 micr0f1S)

Allow for loss In mixing and application EPA Method 24:

4.0 lbs./gal (479 g/1)

Thinned:

7 oz/gal w/#2t:

4.1 lbsJgol(492 g/1) 5 oz/gal w/#26:

4.1 lbsJgal (492 g/1) 5 oz/gal w/#33:

4.1 lbsJgol (492 g/1)

These e,e nominal valuH.

EPA Method 24:

4.3 lbs./gal (515 g/1)

Thinned: For ust In fabrication shops only to temaln In VOC compliance i n accordance with EPA Slandards.

7 oz/gal w/#21:

4.5 lbs./gal ( 539 ~

5 oz/gal w/#28:

4.5 lb1.lgol ( 539 wl) 5 oz/gal w/#33:

4.5 lbsJgol ( 539 ~

These are nominal values.

Untopcoeted:

Continuous; 7SO°f (399'>C)

Non-Contiooous:

800°F (427°C)

With rtcomm,ndtd silicone toccoats:

Continuous*

1000°F (1538°C)

Non*Continuous:

t2004'F (649°C)

October 2006 replaces September 2006 Carbozinc 11 Substrates & Surface Pre aration General Steel Surfaces must be clean and dry. Employ ildequ~le method't to r1mov1 di,t, ck.lst1 oM and 111 ether c:orrt1mlnants that could lnterfer* wltt, 1cheslor1 of the coating.

NPSHIDOOlf!ioo*

SSPC*SP61nd obto.ln a 1.0..3.0 mil (2S-75 microo) angult1r blas.t profile.

Performance Data CZ 11 TH tMf!fhnd awtem Re1utts-Report It ASTMA-325 Blasted steel 0.868; Slip Co-aflld9nt 1 <I. CZ ti meet, requtements foJ 02722 Class 8 r1tina 1 ct.CZ 11 al No rusting or blistering, ASTM 8117 2misdry film cracking or delamination after 43000 hrs.

SR 408 Satt Spray lhlc:kntu Oitr Moderate salting ofth*

blasted steel i-urface ontv.

ASTM 0~3 1 ct CZ 11 PencU Harck'less ~2H" 03278 Pencil Hardiess No blistering or rusting of AASHTOM300 coating or rusting of b1r1 Bullet Hole t ct.CZ 11 steal lfH 1fttr 650 hrs.

Immersion over Abrasilo'e Immersion in 5% sodium 02514 Porog<oph 4.6.9 blosttd st*~

chloride solution: 1,6*

round bare 1,11 In coatina.

Test reports and additional datl 1v1l11ble upon written request.

Ap lication E uipment Listed below are generaJ eq..iiprmmt guidelinH for the 11pplication of this product.

Job site conditions may require modiflc1tlon to thts* gukttlinas to achiwt lht desired results.

General Guidelines:

Spray AppllcaUon The following sproy equipment hu bttn found,uitoble (General) and Is available ft'om manufacturers such as Binks, D1Vtlbiss and Greco.

KHp material under mild agitation during applicatlon. If spraying stops r<< mo,,

than 10 minutes,,eclrCtJla.le the mal eriat remaining fn the spray line. Do not leave mixed primar in the hoses during wo,k stoppages.

Conventlonal Ag~ated pressure pot equipped with dua l regulators, Spray 3.19* 1.0. minimum material host, with a maximum length or 50',.070" I.O. nuld tip and app<oprlote olr cop.

Airless Spray Pump Ratio:

30:1 (min.)

GPM Output:

3.0 (min.)

Material Hose:

319~ 1.0. (min.)

Tip SiZe:

.019-.023" Output PSI:

16-0().2000 FIiter Slzt:

80 mesh Teflon peckings are recommended and available from the pump manufactu,er.

Brush For touch-up of areas less than one sq.iare foot ont,;.

Use medium bristle brush and avoid rebrushifig.

Roller Not recommendad 0214)

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 Rev. 5 8.A-4 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

AOL I EC PROPRIETAR ( ll~FORMATION Carbozinc 11 Mixing & Thinning MIXlng Ratio Thinning Potltfe Power mix base, then combine and power mix as follows. Pour zinc Iller 1Jery $lowly lnto premOced base with continuous agit1ijon. Mbc unt~ ht or lumps. Pour mixture through a 30 mest, screen. DO NOT MIX PARTIAL KITS.

Tip: Sll\\lng zinc through

• wlr,dow screw, will *~ In the mixing process by breaking up or catching dly zinc lumps.

g_ii

~

CZ 11 FG 1 Gal Kit 5 Gallon Kit 4.6 Gallon Kit Part A:

.75 gel.

3.75 gaNons 3.75 gaNons Zinc Flllor: 14.6 lbs.

73 lbs.

50 lbs.

May be thinned up to 5 oz/gal (4%) with #26 for ambient and warm surfllcH. FOf *xtremely warm or windy conditions, may be thinned up to 5 oz/gal (4%) with #33.

In cool weather (below 40DF (4°C)), thin up to 7 oz/gal (61'Ai) with #21. Utt of thinner& oth* than thou supplied or recommended by Cerbol lne may actven.ely affect product perk>rmance and void product warranty, whtthtr exprnstd << lmphd.

8 Hours at 7511F (24oC) and less at higher temperatures.

Pot life ends when coating b1oeomes too viscous to use.

Cleanu & Safety Cleanup sarety Vend lad on cautloo Use Thinn* #21 04' lsopropyl.AJcohol. In case of spila_ge, absorb and dispose of in accordance wiet'l locaJ applicable regulations.

Read and ~ low all cautlon statements on thts product datll sheet and on the MSDS for this product. Employ nQfmal workmanlike safety P'f*cautions. H)'Ptrttnsitive persons should wear protective clothing, gloves and use protective cream on face, harwds and all exposed areas.

WMn utad H a tank IH'llng or In enclosed arHt.

thorough air circulation must: be used lining and after application until the coating is cured. The ventilation 1y1tem should be capable of preventlr)Q the sotv,nt vapor concentration from reaching It!* lower explosion limit for the solvent, used, In addition to ensuring proper vantWation, appropriate rtspiratort must be us.d by ell application personnel.

This product cont.ains flammable solvents. KH p ftWay from sparks and open tam*** All electrical equipment and installations should be made and grounded in accordance with the Natlonel Electtlc Code. In areas whtrt 1xptoslon hua,ds -.xlst. workmen should bt required to use nai-1"rrous t oots and wear conductive and non-sparking shoes.

A lication Conditions Condition Normal 40-90%

Minimum O' F O'F O'F 30%

-18*c

• 18'C

• 18'C MaMlmum 130' F 200' F l30' F 95%

@4*C 93'C 54'C This p,oduct sJTiply req1.o.res th* ubstnit* temperature ta be *bove tli* dew point Condenr.:ation du* to substrate tempt returet below the dciw point c*an cause ftlsh,u:rJK'lg on prepitred steel and jntetflke With proper eche.slori lO the substrate. Speda.l appltC-ation techo!q1,.1es may be,11qulred aboiv, or below normal appllcation cooditJOhs.

Curing Schedule Surface Ten-.,. &

Dryto Han<lo Dry to 50% Relative Humidity TopcoatJRecoat O'F (*18'C) 4 Hours 7 Days -

40'F WC) 1 Hour 48 Hour, 60°F/16"C\\

% Hour 24 Hours 80' f (27°Cl

%Hour 18 Hours -

100'F 13B'CI

)'4 Hour 16 Hours These times are based on a 3.0-4.0 mil (75-100 micron) dry llm thtekness.

HIW,e, film thkknen. lnsuflclent vtnll1, tlon or cooltr lt mperatur" wlN requlrt longer cure times and could re.suit in solvent entrapment and p,emature failure.

Humidty levels below 50°-" will require longer cure times. Notes: Any n hing that appHrs on the zinc surface as e result of ptolonged WHthering exposure mYSt be removed prior to the a.pplication of additlonal coatings. Also, loose zinc must be removed t om the cured film by rubbing wilt! lberglass screen wire if: 1) The Carbo.zinc 11 I* to be used without I topcoat In Immersion service and *z:inc p ick up* could be detrimental, or 2) Wien *ct,y spray/overspray" is evident on the cured film and a topcoat will be applied. For accelerated curing m where 'the relative hi.rnldh'Y It btlow 40%, allow en lniti*I 2-ho1.1r embitnt cure. Follow 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> cure with wate, misting or steam to keep the coated surface wet for e minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and until the coated surface achieves a "2W pencil hardness por ASTM 03363.

Packaging, Handling & Storage CZ 11 Shipping Weight (Approximate)

CZ 11 FG Shippong Weight (Approximate)

Flash Point (Setaflash]

Storage (Genera l)

Storage TemperatU"e

& Humidity 1 Gallon Kit 6 Gllllon Kit 23 lbs (10 kg) 113 lbs (51 kg) 4.6 Gallon Kit 104 lbs. (47 kg)

Part A:

55°F (13°C)

Zinc Aller: NA Store Indoors.

40' *100'F (4-38'C).

0-90% Relatiw Humid~y Shelf life: 11 & 11FG Part A: 12 monthsat 75' F(24' C)

Part B: 24 months al 75°F (24°C)

' Shelr life: (actual stated shelf Ille) When k ept al recommended storage conditions and In original unopened containers.

lSOl...,lc,ladooOWC..,,,9t.t..o.,1110ttl1'4-U99

)14/f44.1000,,_,1 (lb)www, __..,.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT Hl-2114830 8.A-5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HOLTl:C PROPRIETARY INFORMATION-Selection & S ecification Data Generic Type, Description Futures Color Finish Primers Topcoats Dry FIim Thickness Solids Content Theoretical Coverage Rate voe Values Dry Temp.

Resistance Limitations Amine-Cured Novolac Epoxy Highly cross-linked, glass flake-filled polymer lhat offers exceptional barrier protection and resistance to wel/dry cycling al elevated temperalures, Suitable for insulaled and non-Insulated pipes, slacks and equipment operating up to 450°F (232' C). Th s coaling provides excellent resistance to corrosion, abrasion and permeation, and Its novolac-modification resists severe ctiemical etleck.

• Temperature resistance up to 450' F (232' C)

• High-build single-coat capablllties Excellent resistance to thermal shock

• Superior abrasion and chemical resistance through intemal reinforcement Ambient-temperature cure voe compliant to current AIM regulations Red (0500); Gray (5742)

Eggshell Self-prming, May be applied over epoxies and phenolics.

Epoxies, Polyurethanes 8,0-10,0 mils (200-250 microns)

Do nol exceed 15 mils (375 microns) per coat.

By Volume:

70%+/- 2'%

1117 mll <<' (27.9 m'n al 25 microns)

Allow for loss in mixing and application As supplied:

2.08 lbs/gal (250 g/1)

Thinned:

13 oz/gal w/ #213: 2.58 lbs/gal (308 g/1) 13 oz/gal w/#2 2,54 lbs/gaJ (305 gn)

These are nominal values, Continuous:

425' F (218' C)

Non-Continuous:

450' F (232' C)

Discoloration and loss of gloss may be observed above 200' F (9:3"C),

Epoxies lose gloss, discolor and eventually chalk In sunlight exposure.

January 2009 replaces June 2006 Thermaline 450 Novolac Substrates & Surface Pre aration General Steel Surfaces must be clean and dry. Employ adequate methods lo remove din, dust, ell and all ether cootaminants that could interfere wllh adhesion of the coating.

Non-Insulated*

~

Surface Proffle*

SSPC-SP6 SSPC-SP10 2.0-3.0 mils (50-75 microns)

Performance Data Test Method system RM Ults Report #

ASTM D3359 Blasted Steel

• A 08460 Adhesion 2 els, 450 ASTM 04060 Blasted Steel 171 mg loss after 1000 Abrasion 2 cts, 450 cycles; CS17 whHI, 02910 1000 gram load ASTM D2794 Blasted Steel

.375 tn. from damaged 02675 lmoact 1 ct 460 arH. 10().inftbs No cr,ckl'lg, bNsttrlng or delamination of film arter HHICycing Bluttd Sttll 425' F for 1 hr/ambient/

• 100F for24 hrs/*mbient/

SR342 THt 1 ct.450 425af for 24 hrs/ambient/

. 1o* F lo, 24 hrs/1mbl1nV 425°F for 200 hr/ambient Modified No effect to coettng film NACE Std.

Bluttd Stttl t)(Ctpt clscoforeHon after 02651 TM-01* 740 2 cts. 450 6 month e,)(posure, Immersion Deionized water R.slstent to l'umts of commons add$, alkalis, solvents and hy<<ocarbon compounds.

SR 359 C~emical Bluted Steel Resistant to splash and 02735 Reslstance 1 ct 450 spihage of alkaJis, 03133 1otv1nl1 and 02794 hydrocarbons. Acid cootact may cause dlseol0f1tlon of coating, Test reports and additional data avahlble upon written reeJJest.

1039 HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8.A-6

HOL'fEC PROPRIETARY l~IFORMATION Thermaline 450 Novolac A

lication E ui ment listed below are general equipment guidelines for the application of this product.

Job sit* condition$ may rt(IJirt modifieationi to these guidelines to achieve tht dnlrtd results.

General Guidelines:

Spray Appllcaclon The followlng spray equipment hes b11n round suitable (General) and is available ftom manufactu,ers such as Binks.

Conventional Spray Airless spray Sn.Jill Roller D*Vilbiss and Graco.

Pres.sure pot equipped with dual reSJllatcn, Yl 1.0.

minimum materiiil hose,. 110* I.D. fluid tip and epproprlat, elr cop.

Pump Ratio:

45:1 (min.)'

GPM Outp!A:

S.O (min.)

Material Hose:

1h~ 1.0. (min.)

Tip Size:

.035-.041 ~

Output PSI:

2200-2500

' Tenon packings art recommended and ava~ablt from the pump ma_nufacturer.

For Slriplng al walds and toLJch-up of ~m*I lrHS only.

Use a medium natural bristle brush and avoid rebrushing.

Not rticommtinded.

Mixing & Thinning tllxlng Ratio Thinning Pot Lire Pow* mhc 1tp1rately, then combine 1nd pow.- mix.

00 NOT MIX PARTIAL KITS.

4:1 Reoo (A to 8)

May be thinned up to 13 oz/gal (1 0%) with Thinner

1. 2t3. For 1pplic:ation oo hOfizontal surfaces, may be thinned up to 13 oz/gel (10)% "4th Thinner #2. Agitate Thinner #21 3 before use. Thirlner 1213 v-;a have a thick viscous appeeranc, which is normal, Use of thinners other than those supplied by C1rboline may ectverstly atrec-t product performance Md void prod.let warranty, whett, erexpresYd or implied.

3 Hours at 75°F (24°C), Pot Wfe ends when coating loses body and begins lo sag. Pot life times will be Ian at hl{tlar t1mp1raturts.

Cleanu & Safet Cleanup Safety Ventilation Caution Use Thinner #'2 or Acetone. In ca:ie of $pihge, absorb and dispose of In accordance wtth locel eppflceble regulations.

RHd end follow all caution statements on this product dell shHt end on tho MSOS for this proclJct. Employ normal workmanlike safety precautia,s. Hypersensitive persons should wnr protective clothing, glOYH and use prot1ctiv1 crHm Of'I face, han ds tnd a/I 1iq>os.ed t rtH.

When usad in enclosed 1r111s, thorough air circulation must be used Cllring and 111't1r appllcatk,n until th*

coating is cured. The ventilation system should be capable of p,eventing Iha solvent vapor concentration from,11ching lht tower expl oslon limit for lhe sotvtn~

used. Ustf shouk:I test and monito, exposure levels to imiure all personnel 11re below guidelines:. If not sure or If not eblt to monitor l*v.. s, use MSHA,tljl0SH apprOYed supplied air,espitator.

This prod.let contllins flamm Ible s<>Nants, KHp away from sparks arid open hm*s. All 1l1ctrie:al equipment and lnsta.llations should be made and grounded in acc:o,dsnct with th* National Electric Code. In ""'

where 1xploslon hazards e,XIR, workmen should b1 required to use non.ferrous t ools and 'W'li!llr conductive and non-sparking shoes.

A lication Conditions Condition Material Surface Ambient Humidity Normal 85'-85°F 66°-85°F 65'*85°F 3().60%

(18'*29"C)

(18'*29"C)

(18'*29'C)

Mink'num 55°F 50' F 50' F 0%

(13'C)

(10'C)

(10'C)

Ma>dmum 90' F 110' F 100°F 85%

(32'C)

(43°C)

(38°C)

This product Stmply requires the substrate temperature to be above the dew point. Condensation due to substrate temperatures below the dew point can cause flash rusting on prepared 'Steel and interfere 'Mth proper adhesion to the substrate. Special application techniques may be required above or below normal application condklons.

Curin Schedule SlJ'"facoTemp.

Dry to Dry to Topcoot w/

Final

& 50% Relatlw Humidity Handle Other Finishes c..-o 50'F (10'C) 18 Hours 48Hours 21 Days 60'F (16'C) 12 Hours 32Hours 14 Days 75'F (24'C) 6 Hours 16Hours 7 Days 90'F (32'C) 3 Hours 8 Hours 4 Days These times are based on a 10.0 mil (250 micron) dry film thickness. Higher film thickness. insufficient ventiJation a-cooler temperatures 'MU require longer cure times and could result in solvent entrapment and premature failure. E)(oessl'Ye humld~y or condensation on the surface during curing can 111erlere with the cure. can cause dlscoloratlon and may result i1 a surface haze. Any haze or blush mim be removed by water washing before rocoating. During high humidity conditions, It Is recommended that 1he appticaticn be done v.hile temperatures are increasing. If the final cure time Is exceeded, the surface must be abraded by sweep blas1ing prior to 1he application of ad<lltlonal coals.

Packaging, Handling & Storage Shipping Woig>t (Approxlmoto)

Flash Point (5etaflash)

Storage (General)

Storage TemperatU'e

& Hurndity Shelf Life

~

12 lbs(6 kg)

Part A:

53°F (12'C)

~

58 lbs (26 kg)

Part B:

>200°F (93'C)

Store Indoors, 40'

• 110'F (4°-43°C) 0-90% RelallYII Humld~y Part A & B: M in. 36 mcnlhs at 75°F (24°C)

'Shelf Life: factual stated shelf Ille) When kept at recommended storage conditions and In original unopened co ntainers.

¥oaJl.u:x o1~u9;.!;1e!:!\\~;\\~c~! ~~

oonta1ned h8rt1n IS tf\\Je and accl.l'ate on lhe elate Of put)IICSbon and IS SUb,18ct 10 Cheoge WlttiOUt pnor notice User "1USI Cffllact Cart>ol1ne Compatly to venry oorrettntu before si,.ol')ilng or o1'08nng No guera111ee of ecancy 11 grven or Implied Wt guarantee our J)roducts to conf~ 10 Cart,ohnt ~S"tly oortl'OI W8 atsumt no rt1ponSJbi1t..,. tor eo1o1traj** performance or lrlJllntl rtlUlllnj tom us* L1al)ll1ty, If~* II t1m1te<1 to replaotmtnt 0~0C11,1ctt NO OTHER WARRANT'( OR GUAANIITe-e OF ANY KIND IS M.AOE av CARBOLlNE.

~r~~er~: i~de~ ~1~i~~y t~~:RATION OF lAW. 0 OTHERWISE. INCLUDNG ERCHANT.oBtLITY AND FITNESS FOR A ?AATICULAR PURPOSE C1tbd11lf11J> and Thl,mahna~

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8.A-7 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

~OL I EC PROPRIETARY lrffORMATION Industrial Marine Coatings 6.13 ZINC CLAD II PLUS INORGANIC ZINC-RICH COATING B69VZ12 B69VZ13 B69VZ15 B69D11 BAsE AcCWAAl'DR AcCELERATOR ZINC DUST PRODUCT INFORMATION Revised 12/05

....,.,*.cc****,*

• • .PRODUCT D !=SCRIP:TIQN';_fi:, 0 }

• 't+ \\I',:;* ~ !:COMMENDED lJSES [;

• ZINC CLAD II PLUS Is a solvent-based, three component, In-organic ethyl slllcate, zinc rich coating. This Is fast drying, high solids, low voe coating with 82%, by weight, ol zinc dust In the dry film.

• Coating sell-heals to resume protection ii damaged

• Provides cathodic/sacrificial protection by the same mecha-nism as galvanizing

• Forms an Inorganic barrier to moisture and solvents

• Meets Class B requirements for Slip Coefficient and Creep Resistance, 0.67

• Meets AASHTO M-300 specification

'.) '. !.! *. ' ) P,RODUC~ CttA.RACTERISTICS Finish:

Color:

Volume Solid:

WelglltSolld:

voe (EPA Method 24):

Flat Gray-Green 76% :1: 2%, mixed 90% :1: 2%, mixed Unreduced:

Reduced 4%:

<320 g/l.; 2.67 lb/gel (mixed)

<340 g/l.; 2.B lb/gal Zinc Content In Dry FIim:

82% by weight Mix Ratio:

3 components, pramaasured 3.66 gallons mixed Recomme~dod Spreading Rate per coat:

Wet mils.

-a.o -6.0 Dry mils:

2.0 - 4.0 Coverage:

400 - 61 o sq tugal approximate Noto: Brusn application Is tor smal areas only.

Appllcallol1 olcoating above maximum or below minimum recommended spreading rale may adversely affect coating perfonnance.

Drying Schedule @ 4.~Jlo'!i wot @ J~-~H:

@100"F To louch:

25 minutes 20 minutes 5 minutes To handle:

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes 15 minutes To topcoat:

7 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 8 hours

+g ~~~~

~ ~~~~s

~6h~~~s

~i~~~rs D,ylng time Is lemperalure, humidity, and film U,ickness dependent.

Pot Life:

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> O 77°F High humidity will shorten pol life Sweat-In-time:

None required, but material should be mixed tor at least 5 minutes before use Shelf Life:

Part A - 12 months, unopened Part B - 24 months, unopened

ro~

i~d~trr;~~~t*tri~i3;~

Flash Point (mixed):

Reducer/Clean up:

Above 70°F:

. Below 70°F:

Zinc Rich 55°F R2KT41,150 Flash Naphtha R2K4, "ylane 6.13 For use over,prepared blasted steel and galvanized steel In areas such as:

• Bridges

• Refineries

• Shop or field application

• Drilling rigs

• As a one-coat maintenance coating or as a permanent primer for severe corrosive environments (pH range 5-9)

• Ideal for application at low temperatures or service at high temperatures and/or humidity conditions

• Fresh and demlnerallzed water Immersion service (non-potable)

• Compliance with Class B Slip Coefficient rating when used alone or as part of a system with Stael Spec Epoxy Prlmer as a topcoat

.P ERFORMANCE C HAR~CTERISTICS System Tested: (unless otherwise Indicated)

Substrate:

Steel Surlace Preparalion:

SSPC-SP10 1 ct.

Zlr1c Clad II Plus @ 3.0 mils dlt Adhesion:

• Method:

ASTM D4541 Result:

689 psi Direct Impact. Resistance:

Method:

ASTM D2794*92 Result:

60 in lbs.

Dry Heat Resistance:

Method:

ASTM D2485 Result:

750°F*

Flexibility:

Method:

ASTM D522, 160" bend, 1' mandrel Resull:

Passes Pencil Hardness:

Method:

ASTM D3363 Result:

3H Seit Fog Resistance:

Method:

ASTM B117, 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> Result:

Rallng 9 per ASTM D714 for blistering Rallng 9 per ASTM 0 61 o for rusting Slip Coefllclont (zinc only):

Method:

AISC Specification for Structural Joints Using ASTM AS25 or ASTM A490 Bolts Result:

Class B, 0.67 Slip Coefficient (system listed below):

1 ct.

Zinc Clad II Plus @ 2.0 - 4.0 mils dft 1 ct.

Steel Spec Epoxy Primer @ 4.0 - 6.0 mils dft Method:

AISC Specifiction for Structural Joints using ASTM A325 or ASTM A490 Bolts Result:

Passes Class B,.56 Provides performance comparable to products formulated to specifications Mll*P-36336 and Mil-P-46105.

• Acceptable for use up to 1 OOO'F when topcoated with Kem HI-Temp Heat-Flex II 800 Aluminum.

continued on back HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8.A-8 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Industrial Marine Coatings 6.13 ZINC CLAD II PLUS INORGANIC ZINC-RICH COATING B69VZ12 B69VZ13 B69VZ15 B69011 BASE AcCW:RAlOR Acc:aERAltlA ZINC DUST PRODUCT INFORMATION Steel, Immersion:

1 ct.

Zinc Clad II Plus @ 2.0

• 4.0 mils dft Steel, Epoxy Topcoat, Atmospheric:

1 ct.

Zinc Clad II Plus @ 2.0 - 4.0 mils dft 1 ct.

Macropoxy 646 @ 5.0

• 10.0 mils dft Steel, Polyurethano Topcoat, Atmosphorlc:

1 ct.

Zinc Clad II Plus @ 2.0

• 4.0 mils dft 1 ct.

Macropoxy 646 @ 5.0 - 10.0 mils drt 1 cl.

Acrolon 218 HS @ 3.0

• 6.0 mils dfl Stoel, Polyurethane Topcoat, Atmosphorlc:

1 ct.

Zinc Clad II Plus @ 2.0

• 4.0 mils dft 1 cl.

Macropoxy 646 @ 5.0

• 10.0 mils dft 1 ct..

HI-Solids Polyurethane @ 3.0 - 4.0 mils dft NOTE: 1 ct. of DTM Wash Primer can be used as an intermediate coat under recommended topcoats to prevent pinhollng.

Steel (Class B Compliant System):

1 ct.

Zinc Clad II Plus @ 2.0

• 4.0 mils dft

.1 ct.

Steel Spec Epoxy Primer, red @ 4.0

• 6.0 mils dft The systems listed above are representative of the product's use. Other systems may be appropriate.

The lnformollon and r1c.ommonda11on1 aat forth In this Product Dala Shoot af*

bo*od upon 1111a conductod by oron bohall olThe Sh1rwln-Wllllam1 CompMy.

Such Information and recommendaUans set forth herein mo subfect lo change ond pertain to tho p,oduct offered al lhe Um, of publfcnllon. Consult your Sherwln-Willlnma represontallvo to obtain tho moat recent ProtJucl Data lnfor*

matlon and AppllcaUon Buneun.

.... S tiRFA°CE *P REPARATION Surface must be clean, dry, and In sound condition. Remove all oil, dust, grease, dirt, loose rust, and other foreign material to ensure adequate adhesion.

Refer to product Application Bulletin for detailed surface prepa-ration Information.

Minimum recommended surface preparation:

Iron & Steel:

Atmospheric:

Immersion:

Do not tint.

Temperature:

Relative humidity:

SSPC-SP6/NACE 3, 2 mil prollle SSPC-SP10/NACE 2, 2 mil profile TINTING 2o*F minimum, 100°F maximum (air, surface, and material)

At least 5°F above dew point 40% - 90% maximum Waler misting may be required at humidities below 50%

Refer to product Application Bulletin for detailed application Information.

Packaging:

PartA:

PartB:

PartF:

Weight per gallon:

3.66 gallons total, mixed 2.21 gallon kit 0.20 gallon 73 lbs zinc dust 26.83 +/- 0.2 lb, mixed

.. 1...

Refer lo the MSDS sheet before use.

Published technical data and Instructions are subject to change without notice. Contact your Sherwin-WIiiiams repre*

sentatlve for additional technical data and Instructions.

The Shorwln*Wllllams Company warranls our products lo ba free or manufactur-ing dolocl1 In accord wllh appnc:oblo Sh1rwln-Wllllam1 quollty conlrol procoduroo.

U1blllty for producb proven dal1ctlvo, II any, Is llmllod to roplacomont ol lho defocllvo product or the refund of Iha purchase prlco paid for lhe defectf"Je product as doformlnod by Shorwln-Wllllom*. NO OTHEA WARRANTY OR GUAR*

ANTEE OF ANY KIND IS MADE BY SHERWIN-WILLIAMS, EXPRESSED OR IMPLIED, STATUTORY, BY OPERATION OF LAW OR OTHERWISE, INCLUD*

ING MERCHANTABILITY AND FITNESS FOR A PARTICUlAA PURPOSE.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8.A-9 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Industrial Marine Coatings 6.13A ZINC CLAD II PLUS INORGANIC ZINC-RICH COATING B69VZ12 B69VZ13 B69VZ15 069011 BASE ACCW!RATOR ACCW!AATOR ZlNc DusT APPLICATION BULLETIN Revised 12/05

',. I', A l>PL!CATION. C ONDITIONS : ) '

Zinc rich coatings require dlrec*t contacl between the zinc pig-Temperalure:

menl in the coating and the metal substrate for optimum per-20'F minimum, 100'F maximum (air, surface, and material) formance. Surface must be dry, free from oil, dirt, dust, mill scale or other contaminants to ensure adequate adhesion.

Iron & Steel (atmospheric service):

Remove all oil and grease from surface by Solvent Cleaning per SSPC-SP1, Minimum surface preparation Is Commercial Relative humidity:

At least 5'F above dew point 40%

• 90% maximum Water misting may be required at humidities below 50%

=~~~1, ~~e:~~ir ~1!5~~;!~~:tg;a~1~

0~:,e~;~~~~~1~i 1-i-. --. ;-. -, - ;-* _ A_P_P_. L-IC_A_:r-16_N_E_a_ut-P-.M-E_N_f_'.-. -: -. -----1 NACE 2. Blast clean all surlaces using a sharp, angular abra-1----'----'--.;._-'---'------'-'---'----'----1 sive for optimum surface profile (2 mils). Prime any bare steel The following Is a guide. Changes In pressures and tip sizes the same day as It Is cleaned or before !lash rusting occurs.

may be needed for proper spray characteristics. Always purga Iron & Stool (lmmorslon sorvlce):

Remove all oil and !jreasa from surface by Solvent Cleaning per SSPC-SP1, Minimum surface preparation Is Near While Melal Blast Cleaning per SSPC-SP10/NACE 2. Blasl clean all surfaces using a sharp, angular abrasive for optimum sur-face profile (2 mils). Remove all weld spatler and round all sharp edges by grinding. Prime any bare steel the same day as It Is cleaned or before flash rusting occurs.

Note: If blast cleaning with steel media Is used, an appropri-ate amount of steel grit blast media may be Incorporated lnlo the work mix lo render a dense, angular 1.5

• 2.0 mil surface prollle, This method may result In Improved adhesion and per-formance.

Zinc Rich 6.13A spray equipment before use with listed reducer. Any reduction must be compliant with existing voe regulations and com-patible with the existing environmental and application condl*

lions.

Reducer/Clean up Above 70'F '"""""'"""' R2KT4, 150 Flash Naphlha Below 70°F................... R2K4, Xylene Airless Spray (use Te11on packings and continuous agllatlon)

Unit............................... Greco 30:1 Pressure....................... 2700 psi Hose............................. 3/8' 10 llp.................................. 019" *.021" FIiter............................. 30 mesh Reduction..................... As needed up to 4% by volume For continuous operation In larger 8f8llS, use SpooRoAl~ess Commander Zlnc Pump. Set baDchecks lo maximum lravel for viscous malenal.

Conventional Spray (continuous agitation required)

Gun............................... Binks 95 Fluid Nozzle.................. 66 Fluid Hose.................... 1/2' ID, 50 ft maximum Air Nozzle..................... 63PB Air Hose........................ 1/2' ID, 50 ft maximum Atomization Pressure... 25 psi Fluid Pressure.............. 10-20 psi Reduction..................... As needed up to 4% by volume Keep pressure pot at level of applicator to avoid blocking or fluid line due to weight of material. Blow back coating In lluld line al lntermlllent shutdowns, but continue agitation at pres-sure pot.

Brush............................... For touch up In small areas only If specific applfcation equipment Is not listed above, equiva-lent equipment may be substituted.

continued on back HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 8.A-10 Rev. 5

HOLTEC PROPRIETARY INFORMATION Industrial Marine Coatings 6.13A ZINC CLAD II PLUS INORGANIC ZINC-RICH COATING B69VZ12 B69VZ13 B69VZ15 B69D11 a.SE ACCELERATOR ACCEWIATOR ZrNcDusr APPLICATION BULLETIN Surface preparation must be completed as Indicated.

Zinc* Clad II Plus comes In premeasured containers, which when mixed provides ready-lo-apply malerlal.

Mixing Instructions:

Thoroughly agitate Binder, Part A. Using continuous air driven agllatlon, slowly mix all of Zinc Dust, Part F, lnlo all of Binder Part A unlll mixture Is completely uniform. Continue agitation and add Part 8. Aller mixing, pour mixture through 30-mesh screen. Mixed material must be used within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Do not mix previously mixed material with new. No 'sweat-in' period Is required.

If reducer solvent Is used, add only atter components have been thoroughly mixed.

Continuous agitation of mixture during application is required, otherwise zinc dust will quickly settle out.

Apply paint at the recommended film thickness and spread*

Ing rate as Indicated below:

Recommended Spreading Rate per coat:

Wet mils:

3.0

• 6.0 Dry mils:

2.0

• 4.0 Coverage:

400

• 610 sq fVgal approximate Noto: Brush application Is for small areas only.

Application of coating above maximum or below minimum reoommended spreading rate may adversely atteclcoaling performance.

Drying Schedule @ 4.0 mils wet @ 50% AH:

@40'F

@ n"F

@100"F To touch:

25 minutes 20 minutes 5 mlnules To handle:

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes 15 minutes To topcoat:

7 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 8 hours To cure:

7 days 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 24 hours To stack 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Dryinglimolstemperature,humldlty,andfllmlhlcknossdopendent Pot Life:

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> @ n*F Hlghhumldllywlllshonenpotrde Sweat-In-time:

None required, bul material should be mixed for el least 5 minutes before use Clean spllls and spatters immediately wilh Reducer A2KT4, 150 Flash Naphtha or R2K4, Xyle,ne. Clean hands and tools Immediately after use with Reducer R2KT4, 150 Flash Naph*

tha or R2K4, Xylene. Follow manufaclure(s safely recommen-dallons when using any solvent.

Tho tnrarmallon and,eccmmendaUons set lor1h In this Product Dalo Sheet are bao*d upon tasls ccnduclod by or on be hell cl The Shoiwln-Wllltoms Company.

Such 1nlormat1on ond rocomm1nd1tlon1 sol for1h horoln are aublect lo chungo 2nd portnln to Iha-product ollered at the time of publlcatlon, Consult your Shorwln-Wlllli1m1 r*prasantatlvo to obtain 1ha mo,t rlKlont Product Data Infor-mation ind Appllcnllon Bullotln.

Topcootlng: Note minimum cure times at normal condlllons before top*

coating. Longer drying periods are required If ~rimer cannot be water

~~~t~fif.;'ft~i:;'~eJ'o~~~~~h~n~cu1:1:1:1s ng may be required at Occasionally topcoats will pinhole or delamlnate from zinc-rich coat-ings. This Is usually due to poor ambient conditions or laulty application onopcoals. This can be mlnlmlzcd by:

• Provide adequate venlllallon and suitable appllcallon and subslralc lemperalure.

• If plnhotlng develops durin'ktopcoellng, appty a mist coat of the loll;

~o1

~trt ~~~ed up to 50%.

!low 1 O mmulos lash on and follow wt h An lnlermedlato c0wl ls recommended lo provide uniform appearance of the topcoat.

~~~~ ft:Je"gr~~;,lces. welds, and sharp angles to prevent ea~y fall-

~~~~r~n9v~l/rn~1fJt~~a:r~ a~~:s~ :ilpi~~'iil:f. itn~~~;~&.";r~~

spray al a right angle.

Spreading rates are calculated on volume solids and do not Include an application loss factor due lo surface promo, roughness or porosity, of

~a~l~~~a;~;f~~: ~~~~~~mmi:. ~ti:,ffiP/~.'\\1'ifuW~~~x?~~~~iw~~~:

cverthlnnlng, climatic conditions, and excessive mm build.

Excessive reduction of matorlaJ can affect mm build, appoaranco, and performance.

Do not mix previously catalyzed malorlal with new.

Do not apply the material beyond recommended pol life.

In order to ovoid blocka~o of sp~ equipment, clean equipment be lore llts:sg'~:J~\\~f."rlod!I o extend downtime with Roducer R2KT4, 150 Koep pressure pol,al J*vel of appUcotor to avoid blocking of fluid lino due lo weight ol mater al. Blow back coaling In fluid line at lnlennlltent shuldowns, bul continue egilallon al pressure pot.

Application above recommended mm lhlckness may result In mud crack*

Ing and poor topcoat appearance.

During u,e early sto.~os of dr;Jng, tho coaling Is sanslllvo to rain, dow, mrs 7~~~Jm ~!~~,,SJ~::'n~~g~~~

0ti*~f fi~lsl1/J."2t~~~rn~:~.d-

~~~f ~n~~Yrlh~ ~gg:;c!~~ir~ g~ !'I.T~e~og~\\~ Wa~n'::ts,i~\\e!:~.~g be used.

Refer lo Product lnloonallon shoot for addlllonel porformanco charaa.

lerisllcs and aronerlles.

'. * *.. '1 ' i '.,., SAFETYPRECAirTJO~S.. i: r,

Refer lo the MSDS before use.

Published technical data end Instructions are subject lo change without notice. Contact four Sherwin-Williams repre-sentative for addillonal lechnlce data and lnstrucllons.

Tho Shorwtn-Wllllnm11 Company warrants our producls lo bo froa ol 1nanufactur*

Ing derecls In accord with appllcable Sher'WUl*Willfams quality COf'\\trol procedures.

Ual:JIUty for produc\\S proven defective, If any, Is Umlled lo replacomenl al tha dolectlvo product or tho rolund ol tho purchase prlco paid lor tho dofocllva product as detormlnod by Shorwln*Wllllams. NO 0TH EA WAAAANlY OR GUAA*

ANTEE OF ANY KINO IS MAOE BY SHERWIN*WILLIAMS, EXPRESSED OR IMPLIED, STATUTORY, BY OPERATION OF LAW OR OTHERWISE, INCLUD*

ING MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE.

HOLTEC INTERNATIONAL COPYRIGHTED INFORMATION REPORT HI-2114830 8.A-11 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

HOLTEC F'RO~RIETARY lt~FORMATION CHAPTER 9: OPERATING PROCEDURES

9.0 INTRODUCTION

This chapter contains the operating procedures required for the dry storage of spent nuclear fuel at an on-site HI-STORM FW ISFSI. The decay heat, initial enrichment, bumup and cooling time of the SNF must accord with the restrictions in the Technical Specification. The unloading procedure is also described in this chapter. This sequence of activities is collectively referred to as sho1t-term operations in this safety analysis report (SAR).

The procedures provided in this chapter are prescriptive to the extent that they provide the basis and general guidance for plant personnel in preparing detailed, written, site-specific, loading, handling, storage, and unloading procedures. Users may add, modify the sequence of, perfonn in parallel, or delete steps as necessary provided that the intent of this guidance are met and the requirements of the Certificate of Compliance (CoC) are complied with literally. The information provided in this chapter complies with the provisions ofNUREG-1536 [9.0.1).

The information presented in this chapter along with the technical basis of the system design described in this SAR will be used to develop detailed operating procedures. Equipment specific operating details such as valve manipulation, canister drying method, special rigging, etc., will be provided to individual users of the system based on the specific ancillary equipment selected and the configuration of the site. In preparing the site-specific procedures, the user must consult the conditions of the CoC, equipment-specific operating instructions, and the plant's working procedures as well as the info1mation in this chapter to ensure that the short-term operations shall be carried out with utmost safety and ALARA.

The following generic criteria shall be used to determine whether the site-specific operating procedures developed pursuant to the guidance in this chapter are acceptable for use:

All heavy load handling instructions are in keeping with the guidance m industry standards, and Holtec-provided instructions.

The procedures are in conformance with this FSAR and the COC.

The operational steps are ALARA.

The procedures contain provisions for documenting successful execution of all safety significant steps for archival reference.

Procedures contain provisions for classroom and hands-on training and for a Holtec-approved personnel qualification process to ensure that all operations personnel are adequately trained.

The procedures are sufficiently detailed and articulated to enable craft labor to execute them in literal compliance with their content.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-1 Rev. 5

I IOLTEG PROPRIET.ARY INFORMATION The operations described in this chapter assume that the fuel will be loaded into or unloaded from the MPC submerged in a spent fuel pool. With some modifications, the information presented herein can be used to develop site-specific procedures for loading or unloading fuel into the system within a hot cell or other remote handling facility.

Users are required to develop or modify existing programs and procedures to account for the implementation of the HI-STORM FW system. Written procedures are required to be developed or modified to account for such items as handling and storage of systems, structures and components identified as important-to-safety, heavy load handling, specialized instrument calibration, special nuclear material accountability, fuel handling procedures, training, equipment, and process qualifications. Users shall implement controls to ensure that all critical set points do not exceed the design limit of lifting equipment and appurtenances.

Control of the operation shall be performed in accordance with the user's Quality Assurance (QA) program to ensure critical steps are not overlooked and that the cask has been confirmed to meet all requirements of the CoC before being released for on-site storage under Part 72.

Fuel assembly selection and verification shall be performed by the user in accordance with written, approved procedures that ensure that only SNF assemblies authorized in the CoC are loaded into the MPC. Fuel handling shall be performed in accordance with written site-specific procedures.

ALARA notes and warnings in this chapter are included to alert users to radiological issues.

Actions identified with these notes and warnings are of an advisory nature and shall be implemented based on a site-specific determination by radiation protection personnel.

Section 9.1 provides a technical basis for loading and unloading procedures. Section 9.2 provides the guidance for loading the HI-STORM FW system. Section 9.3 provides the procedures for ISFSI operations and general guidance for performing maintenance and responding to abnonnal events. Responses to abnormal events that may occur during normal loading operations are provided with the procedure steps. Section 9.4 provides the procedure for unloading the HI-STORM FW system.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-2 Rev. 5

HOLl EC F'ROFRIETARY IMFORM4Tl0lll 9.1 TECHNICAL AND SAFETY BASIS FOR LOADING AND UNLOADING PROCEDURES The procedures herein are developed for the loading, storing, and unloading of spent fuel in the HI-STORM FW system. The activities involved in loading of spent fuel in a canister system, if not carefully performed, may present physical risk to the operations staff. The design of the HI-STORM FW system, including these procedures, the ancillary equipment and the Technical Specifications, serve to minimize potential risks and mitigate consequences of potential events.

The primary objective of the information presented in this chapter is to identify and describe the sequence of significant operations and actions that are important to safety for cask loading, cask handling, storage operations, and cask unloading to adequately protect health and minimize danger to life or property, protect the fuel from significant damage or degradation, and provide for the safe performance of tasks and operations.

In the event of an extreme abnormal condition the appropriate procedural guidance to respond to the situation must be available and ready for implementation. As a minimum, the procedures shall address establishing emergency action levels, implementation of emergency action program, establishment of personnel exclusions zones, monitoring of radiological conditions, actions to mitigate or prevent the release of radioactive materials, and recovery planning and execution and reporting to the appropriate regulatory agencies, as required.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-3 Rev. 5

lelObTi;C PROPRIETARY INFORMATION Table 9.1.1 OPERATIONAL CONSIDERATIONS POTENTIAL EVENTS METHODS USED TO ADDRESS AN ADVERSE EVENT Cask Drop During Handling Cask lifting and handling equipment is designed to Operations ANSI Nl4.6, as required.

Cask Tip-Over Prior to welding of the The design of the Lift Yoke prevents inadvertent MPC lid disconnection during periods where it is attached.

The annulus seal, bottom lid, and Annulus Contamination of the MPC external Overpressure System minimize the potential for the shell MPC external shell to become contaminated from contact with the spent fuel pool water.

Contamination spread from cask Processing systems are equipped with exhausts that process system exhausts can be directed to the plant's processing systems.

Fuel assemblies are not directly exposed to air or Damage to fuel assembly cladding oxygen during loading and unloading operations.

from oxidation Fuel will be blanketed with an inert gas when not immersed in water. Water is introduced at a slow rate to avoid thermal shocking of the system.

Vacuum gauges will be isolated from pressurized gas Damage to Vacuum Drying System and water systems when not used for vacuum.

vacuum gauges from positive pressure Isolation valves allow gauges to be easily replaced in service.

The area around MPC lid shall be appropriately Ignition of combustible mixtures of monitored for combustible gases prior to and during gas (e.g., hydrogen) during MPC lid welding or cutting activities. The space below the welding or cutting MPC lid shall be purged prior to and during these activities.

MPC gas sampling allows operators to determine the Excess dose from failed fuel integrity of the fuel cladding prior to opening the assemblies during unloading MPC. This allows preparation and planning for failed fuel. The RVOAs allow the vent and drain ports to be operations operated like valves and prevent the need to hot tap into the penetrations during unloading operation.

Excess dose to operators The procedures provide ALARA Notes and Warnings when radiological conditions may change.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-4

I IOLTEG PROPRIET.ARY IMFORMAJIQN Table 9.1.1 OPERATIONAL CONSIDERATIONS POTENTIAL EVENTS METHODS USED TO ADDRESS AN ADVERSE EVENT Excess generation of radioactive waste The HI-STORM FW system uses process systems that minimize the amount of radioactive waste generated. Such features include smooth surfaces for ease of decontamination efforts, prevention of avoidable contamination, and procedural guidance to reduce decontamination requirements. Where possible, items are installed by hand and require no tools.

Fuel assembly misloading event Procedural guidance is given to perform assembly selection verification and a post-loading visual verification of assembly identification prior to installation of the MPC lid.

Incomplete moisture removal from The vacuum drying process reduces the MPC MPC pressure in a controlled manner to prevent the formation of ice. Vacuum is held below 3 torr for 30 minutes with the vacuum pump isolated to assure dryness. If the forced helium dehydration process is used, the temperature of the gas exiting the demoisturizer is held below 21 °F for a minimum of 30 minutes. The TS require the surveillance requirement for moisture removal to be met before entering transport operations.

Incorrect MPC lid installation Procedural guidance is given to visually verify correct MPC lid installation prior to HI-TRAC removal from the spent fuel pool.

Load Drop Rigging diagrams and procedural guidance are provided to users for all applicable lifts. Component weights are provided to users on a site-specific basis.

Heavy loads are handled in accordance with the guidance ofNUREG-0612.

Over-pressurization of MPC during Pressure relief devices in the water and gas loading and unloading processing systems limit the MPC pressure to acceptable levels.

Overstressing MPC lift lugs from side Procedural guidance is provided for all heavy load loading handling activities on a site-specific basis.

Overweight cask lift Procedural guidance is given to alert operators to potential overweight lifts. Site-specific weight evaluations are provided.

Personnel contamination by Procedural guidance is given to warn operators prior cutting/grinding activities to cutting or grinding activities.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIA L REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-5

letObTi;C PROPRIETARY INFORMATION Table 9.1.1 OPERATIONAL CONSIDERATIONS POTENTIAL EVENTS METHODS USED TO ADDRESS AN ADVERSE EVENT Transfer cask carrying hot particles Procedural guidance is given to scan the transfer cask out of the spent fuel pool prior to removal from the spent fuel pool.

Unplanned or uncontrolled release of The MPC vent and drain po11s are equipped with radioactive materials metal-to-metal seals to minimize the leakage during moisture removal and helium backfill operations.

Unlike elastomer seals, the metal seals resist degradation due to temperatw-e and radiation and allow future access to the MPC ports without hot tapping. The RVOAs allow the port to be opened and closed like a valve so gas sampling may be performed.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-6

HO! TEC PROPRIETARY INFORMATIOl<l 9.2 PROCEDURE FOR LOADING THE HI-STORM FW SYSTEM IN THE SPENT FUEL POOL 9.2.1 Overview of Loading Operations The HI-STORM FW system is used to load, transfer, and store spent fuel. Specific steps, required to prepare the HI-STORM FW system for fuel loading, to load the fuel, to prepare the system for storage, and to place it in storage at an ISFSI are described in this chapter. The MPC transfer may be performed in the cask receiving area, at the ISFSI, or any other location deemed appropriate by the user. HI-TRAC VW and/or HI-STORM FW may be moved between the ISFSI and the fuel loading facility using any load handling equipment designed! for such applications. Users of the HI-STORM FW system are required to develop detailed written procedures to control on-site transport operations. Instructions for general lifting, handling, and placement of the HI-STORM FW overpack, MPC, and HI-TRAC VW vary by site and are provided on a site-specific basis in Holtec-approved procedures and instmctions.

The broad operational steps are explained below and illustrative figures are provided at the end of this section (note the figures are strictly illustrative and do not show minor details such as the trunnions used in Version P of the HI-TRAC VW in lieu of the Lift Block). At the start of loading operations, an empty MPC is upended. The empty MPC is raised and inserted into the HI-TRAC VW. The annulus is filled with plant demineralized water I and an inflatable seal is installed in the upper end of the annulus between the MPC and HI-TRAC VW to prevent spent fuel pool water from contaminating the exterior surface of the MPC when it is submerged in the pool. The MPC is filled with either spent fuel pool water or plant demineralized water (borated as required)2. The HI-TRAC VW top flange is outfitted with the lift blocks and the HI-TRAC VW and MPC are then raised and lowered into the spent fuel pooP for fuel loading using the lift yoke. For HI-TRAC VW Version P, lifting trunnions embedded in the top flange engage with the lift yoke to raise and lower the HI-TRAC and MPC. Pre-selected assemblies4 are loaded into the MPC and a visual verification of the assembly identification is performed.

While still underwater, a thick shielded lid (the MPC lid) is installed. The lift yoke remotely engages to the HI-TRAC VW lift blocks or to the HI-TRAC VW Version P lifting trunnions to lift the HI-TRAC VW and loaded MPC close to the spent fuel pool surface. When radiation dose rate measurements confirm that it is safe to remove the HI-TRAC VW from the spent fuel pool, the cask is removed from the spent fuel pool. The lift yoke and HI-TRAC VW are decontaminated, in accordance with instructions from the site's radiological protection personnel, as they are removed from the spent fuel pool.

2 3

4 Users may substitute domestic water or radiologically clean iborated water in each step where demineralized water is specified.

Users may also fill the MPC with water during HJ-TRAC placement in the spent fuel pool.

Spent Fuel Pool as used in this chapter generically refers to the users designated cask loading location.

Damaged fuel assemblies arc loaded and stored in Damaged Fuel Containers in the MPC basket.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 9-7 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

I IOLTEC PROPRIETARY INFORMATION HI-TRAC VW is placed in the designated preparation area and the lift yoke is removed. The next phase of decontamination is then performed. The top surfaces of the MPC lid and the upper flange of HI-TRAC VW are decontaminated. The neutron shield water jacket is fi lled with water (if drained). The inflatable annulus seal is removed and an annulus shield is installed. Dose rates are measured at the MPC lid to ensure that the dose rates are within expected values.

The MPC water level and annulus water level are lowered slightly, the MPC is vented, and the MPC lid is welded on using the automated welding system. Visual examinations are performed on the tack welds. Liquid penetrant (PT) examinations are perfo1med on the root and final passes. A progressive PT examination as described in the Code Alternatives listed in the CoC is performed on the MPC Lid-to-Shell weld to ensure that the weld is satisfactory. As an alternative to volumetric examination of the MPC lid-to-shell weld, a multi-layer PT is performed including one intermediate examination after approximately every three-eighth inch of weld depth. The MPC welds are then pressure tested followed by an additional liquid penetrant examination perfom1ed on the MPC Lid-to-Shell weld to verify structural integrity. To calculate the helium backfill requirements for the MPC (if the backfill is based upon helium mass or volume measurements), the free volume inside the MPC must first be determined. This free volume may be determined by measurement or detennined analytically. The remaining bulk water in the MPC is drained.

Depending on the burn-up or decay heat load of the fuel to be loaded in the MPC, moisture is removed from the MPC using either a vacuum drying system (VDS) or forced helium dehydration (FHD) system. For MPCs without high burn-up fuel or with high burnup fuel and with sufficiently low decay heat, the vacuum drying system may be connected to the MPC and used to remove all liquid water from the MPC. The annular gap between the MPC and HI-TRAC is filled with water during vacuum drying to promote heat transfer from the MPC and maintain lower fuel cladding temperatures. The internal pressure is reduced and held in accordance with Technical Specifications to ensure that all liquid water is removed.

An FHD system is required for high-bum-up fuel at higher decay heat (it can be used as an alternative to vacuum drying) to remove residual moisture from the MPC. Gas is circulated through the MPC to evaporate and remove moisture. The residual moisture is condensed until no additional moisture remains in the MPC. The temperature of the gas exiting the system demoisturizer is maintained in accordance with Technical Specification requirements to ensure that all liquid water is removed.

Following MPC moisture removal, by VOS or FHD, the MPC is backfilled with a predetermined amount of helium gas. The helium backfill ensures adequate heat transfer during storage, and provides an inert atmosphere for long-term fuel integrity. Cover plates are installed and seal welded over the MPC vent and drain ports with liquid penetrant examinations performed on the root and final passes (for multi-pass welds). The cover plate welds are then leak tested.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-8 Rev. 5

HOLTEC f"ROl"RIETARY lt~FORMATION The MPC closure ring is then placed on the MPC and aligned, tacked in place, and seal welded providing redundant closure of the MPC confinement boundary closure welds. Tack welds are visually examined, and the root and final welds are inspected using the liquid penetrant examination technique to ensure weld integrity.

The annulus shield (if utilized) is removed and the remaining water in the annulus is drained.

The MPC lid and accessible areas of the top of the MPC shell are smeared for removable contamination. HI-TRAC VW sw'face dose rates are measured in accordance with the technical specifications. The MPC lift attachments are installed on the MPC lid. The MPC lift attachments are the primary lifting point on the MPC. MPC slings are installed between the MPC lift attachments and the lift yoke.

MPC transfer may be performed inside or outside the fuel building. The empty HI-STORM FW overpack is inspected and positioned with the lid removed. Next, the mating device is positioned on top of the HI-STORM FW and HI-TRAC VW is placed on top of it. The mating device assists in the removal of the HI-TRAC VW bottom lid and helps guide the HI-TRAC VW during its placement on the HI-STORM FW. The MPC slings are attached to the MPC lift attachments.

The MPC is transferred using a suitable load handling device.

Next, the HI-TRAC VW bottom lid is removed and the mating device drawer is opened. The MPC is transferred into HI-STORM FW. Following verification that the MPC is fully lowered, the MPC slings are disconnected from the lifting device and lowered onto the MPC lid. Next, the HI-TRAC VW is removed from the top of HI-STORM FW5. The MPC slings and MPC lift attachments are removed. Plugs are installed in the empty MPC lifting holes to fi ll the voids left by the lift attachment bolts. Next, the mating device is removed. The HI-STORM FW lid, along with the temperature elements (if used), and vent screens may be installed at any time after the mating device is removed. The HI-STORM FW is secured to the transporter (as applicable) and moved to the ISFSI pad. The HI-STORM FW overpack and HI-TRAC VW transfer cask may be moved using a number of methods as long as the lifting equipment requirements of this FSAR are met. Finally, the temperature elements connections are installed (if used), final dose rate measurements are taken, and any thermal testing (if required) is performed to ensure that the system is functioning within its design parameters.

5 The empty HI-TRAC VW may be removed from the mating device with its bottom lid installed or removed.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 9-9 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 Rev. 5

I IOLTEC PROPRIETARY INFORMATION 9.2.2 Preparation of HI-TRAC VW and MPC Note:

Handlin of loaded e ui ment shall onl be erformed if the ambient tem erature is above 0°F I.

Place HI-TRAC VW in the cask receiving area.

2.

Perform a HI-TRAC VW receipt inspection and cleanliness inspection (See Table 9.2.5 for example).

3.

Clear the HI-TRAC VW top for installation of the MPC.

4.

Remove any road di1t. Remove any foreign objects from cavity locations.

5.

If necessary, perform a radiological survey of the inside of HI-TRAC VW to verify there is no residual contamination from previous uses of the cask.

6.

If necessary, configure HI-TRAC VW with the bottom lid*.

7.

Perform an MPC receipt inspection and cleanliness inspection (See Table 9.2.4 for example).

8.

Install the MPC inside HI-TRAC VW m accordance with site-approved nggmg procedures.

9.

If necessary, perform an MPC, lid, closure ring, drain line, vent, and drain port cover plate fit test and verify that the weld prep is in accordance with the approved fabrication drawings.

Note:

Annulus filling and draining operations vary by site. Instructions for filling and draining the annulus along with the use of the ammlus overpressure system are provided on a site-specific basis.

I 0.

Fill the annulus with non-contaminated water to just below the inflatable seal seating surface.

11.

Install the inflatable annulus seal around the MPC.

12.

To the extent practicable, apply waterproof tape over any empty bolt holes or locations where water may create a decontamination issue.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-10

I IOLTEC PROPRIETARY INFORMATION Note:

Canister filling and draining operations vary by site. Instructions are provided on a site-specific basis.

13.

Fill the MPC with water to approximately 12 inches below the top of the MPC shell.

Refer to LCO 3.3.1 for boron concentration requirements.

ALARA Note:

Wetting the components that enter the spent fuel pool may reduce the amount of decontamination work to be perfonned later.

14.

Place HI-TRAC VW in the designated cask loading area.

15.

Verify spent fuel pool for boron concentration requirements in accordance with LCO 3.3.1. Testing must lbe completed within four hours prior to loading and every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after in accordance with the LCO. Two independent measurements shall be taken to ensure that the requirement of IO CFR 72. l24(a) is met.

9.2.3 MPC Fuel Loading 6

Note:

When loading an MPC requiring soluble boron, the boron concentration of the water shall be checked in accordance with LCO 3.3.1 before and during operations with fuel and water in the MPC.

1.

Perform a fuel assembly selection verification using plant fuel records to ensure that only fuel assemblies that meet all the conditions for loading, as specified in the Approved Contents Section of Appendix B to the CoC, have been selected for loading into the MPC. Perform a verification of the types, amounts, and location of non-fuel hardware using plant fuel records to ensure that only non-fuel hardware that meet the conditions for loading, as specified in the Approved Contents Section of Appendix B to the CoC, have been selected for loading into the MPC.

2.

Load the pre-selected fuel assemblies into the MPC in accordance with the approved fuel loading pattem6.

3.

Perform a post-loading visual verification of the assembly identification to confirm that the serial numbers match the approved fuel loading pattern.

4.

If required, install fuel shims where necessary in the fuel cells.

Damaged fuel must be loaded into Damage Fuel Containers in the MPC basket.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 9-11 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017

lelObTi;C PROPRIETARY INFORMATION 9.2.4 MPC Closure

1.

install MPC lid and remove the HI-TRAC VW from the spent fuel pool as follows:

a.

Rig the MPC lid for installation in the MPC in accordance with site-approved rigging procedures.

b.

Install the drain line to the underside of the MPC lid.

c.

Align the MPC lid and lift yoke so the drain line will be positioned in the MPC for installation.

d.

Seat the MPC lid in the MPC and visually verify that the lid is properly installed.

e.

Record the time to begin the time-to-boil monitoring, if necessary.

Note:

See FSAR Section 4.5.3 for more information regarding the determination and monitoring of time-to-boil.

f.

Engage the lift yoke to HI-TRAC VW.

ALARANote:

Activated debris may have settled on the top face of HI-TRAC VW and MPC during fuel loading. The cask top surface should be kept under water until a preliminary dose rate scan clears the cask for removal. Soluble boron concentration, when applicable, shall be monitored to prevent non-compliance with the Technical Specification LCO 3.3.1.

g.

Raise the HI-TRAC VW until the MPC lid is just below the surface of the spent fuel pool. Survey the area above the cask lid to check for hot particles. Remove any activated or highly radioactive particles from the HI-TRAC VW or MPC.

h.

Continue to raise the HI-TRAC VW under the direction of the plant's radiological control personnel. Continue general decontamination activities.

1.

Remove HI-TRAC VW from the spent fuel pool while performing outer decontamination activities in accordance with directions from the radiological control personnel.

j.

Place HI-TRAC VW in the designated cask preparation area.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-12 Rev. 5

I IOLTEC PROPRIETARY INFORMATION Note:

If the transfer cask is expected to be operated in an environment below 32 °F, the water jacket shall be filled with an ethylene glycol solution (25% ethylene glycol). Otherwise, the jacket shall be filled with clean potable or demineralized water. Depending on weight limitations, the neuh*on shield jacket may remain filled (with pure water or 25% ethylene glycol solution, as required). Cask weights shall be evaluated to ensure that the equipment load limitations are not violated.

k.

If previously drained, fill the neutron shield jacket with plant demineralized water or an ethylene glycol solution (25% ethylene glycol) as necessary.

I.

Disconnect any special rigging from the MPC lid and disengage the lift yoke in accordance with site-approved rigging procedures.

Warning:

MPC lid dose rates are measured to ensure that dose rates are within expected values. Dose rates exceeding the expected values could be an indication that fuel assemblies not meeting the CoC have been loaded.

m.

Measure the dose rates at the MPC lid and verify that the combined gamma and neutron dose is below expected values.

n.

Perfo1m decontamination and a dose rate/contamination survey of HI-TRAC.

o.

Prepare the MPC annulus for MPC lid welding by removing the annulus seal and draining the annulus approximately 6 inches.

2.

Prepare for MPC lid welding as follows:

a.

Clean the vent and drain ports to remove any dirt or standing water. Install the RVOAs to the MPC lid vent and drain ports, leaving caps open.

b.

Lower the MPC internal water level in preparation for MPC lid-to-shell welding.

ALARANote:

The MPC exterior shell survey is performed. Indications of contamination could require the MPC to be unloaded. In the event that the MPC shell is contaminated, users must decontaminate the annulus. If the contamination cannot be reduced to acceptable levels, the MPC must be returned to the spent fuel pool and unloaded. The MPC may then be removed and the external shell decontaminated.

c.

Survey the MPC lid top surfaces and the accessible areas (approximately the top three inches) of the MPC external she ll. Decontaminate the MPC lid and accessible surfaces of the MPC shell in accordance with LCO 3.2.1.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-13 Rev. 5

I IOLTEC PROPRIETARY INFORMA I ION

3.

Weld the MPC lid as follows:

a.

As necessary, install the MPC lid shims around the MPC lid to make the weld gap uniform and to close the gap to the requirements of the licensing drawings.

b.

Install the Automated Welding System (AWS).

Note:

It may be necessary to remove the RVOAs to allow access for the automated welding system.

In this event, the vent and drain port caps should be opened to allow for thermal expansion of the MPC water.

Caution:

A radiolysis of water may occur in high flux conditions inside the MPC creating combustible gases. Appropriate monitoring for combustible gas concentrations shall be performed prior to, and during MPC lid welding operations. The space below the MPC lid shall be purged with ine1t gas prior to, and during MPC lid welding operations, including welding, grinding, and other hot work, to provide additional assmance that flammable gas concentrations will not develop in this space.

c.

Perform combustible gas monitoring and purge the space under the MPC lid with an inert gas to ensure that there is no combustible mixture present in the welding area.

Note:

MPC closure welding procedures dictate the perfom1ance requirements and acceptance requirements of the weld examinations.

d.

Perform the MPC lid-to-shell weld and NDE in accordance with the licensing drawings using approved procedures. Repair any weld defects in accordance with the applicable code and re-perform the NDE until the weld meets the required acceptance criteria.

4.

Perform MPC lid-to-shell weld pressme testing m accordance with site-approved procedures.

5.

Repeat the liquid penetrant examination on the final pass of the MPC lid-to-shell weld.

a.

Repair any weld defects in accordance with the applicable code requirements and re-perform the NDE in accordance with approved procedures.

6.

Drain the MPC and terminate time-to-boil monitoring and boron sampling program, where required.

Note:

Detailed procedures for MPC drying are provided on a site-specific basis. The following summarize those procedures.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-14 Rev. 5

I IOLTEC PROPRIETARY INFORMATION

7.

Dry and backfill the MPC (Vacuum Drying Method).

Note:

During drying activities, the annulus between the MPC and the HI-TRAC VW must be maintained full of water. Water lost due to evaporation or boiling must be replaced to maintain the water level.

a.

Fill the annulus between the MPC and HI-TRAC VW with clean water. The water level must be within 6" of the top of the MPC.

b.

Attach the vacuum drying system (VDS) to the vent and drain port RVOAs.

Other equipment configurations that achieve the same results may also be used.

Caution:

Rapidly reducing the pressure in the VDS piping and MPC while the system contains significant amounts of water can lead to freezing of the water and to improper conclusions that the system is dry. To prevent freezing of water, the MPC internal pressure should be lowered in a controlled fashion. The vacuum drying system pressure will remain at about 30 torr until most of the liquid water has been removed from the MPC.

c.

Start the VDS system and slowly reduce the MPC pressure to below 3 torr.

Note:

Helium backfill shall be in accordance with the Technical Specification using 99.995%

(minimum) purity. If at any time during final closure operations the helium backfill gas is lost or oxidizing gases are introduced into the MPC, then the dryness test shall be repeated and the MPC refilled with helium in accordance with the Technical Specifications.

d.

Perform the MPC drying pressure test in accordance with the Technical Specifications.

e.

When the MPC is dry, in accordance with the acceptance criteria in the LCO 3.1. l, close the vent and drain po1t valves.

f.

Backfill the MPC in accordance with LCO 3.1. l using site-specific procedures.

g.

Disconnect the VDS from the MPC.

h.

Close the drain port RVOA cap and remove the drain pott RVOA.

1.

If used, stop the water flow through the annulus between the MPC and HI-TRAC.

Drain.

J.

Close the vent port RVOA and disconnect the vent port RVOA.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-15 Rev. 5

I IOLTEC PROPRIETARY INFORMATION

8.

Dry and Backfill the MPC (FHD Method):

Note:

Helium backfill shall be in accordance with the Technical Specification using 99.995%

(minimum) purity. When using the FHD system to perform the MPC helium backfill, the FHD s stem shall be evacuated or ur ed and the s stem o erated with hi h uri helium.

Note:

MPC internal pressure during FHD operation must comply with Technical Specification.

Caution:

MPC internal pressure <luting FHD operation may be less than the Technical Specification minimwn backfill requirement. In the event of an FHD System failme where the MPC internal pressure is below the Technical Specification limit, the MPC internal pressure must be raised to at least 20 si to lace the MPC in an acce table condition.

a.

Attach the moisture removal system to the vent and drain port R YOAs. Other equipment configurations that achieve the same results may also be used.

b.

Drain the water from the annulus.

c.

Circulate the drying gas through the MPC while monitoring the circulating gas for moisture. Collect and remove the moisture from the system as necessary.

d.

Continue the monitoring and moisture removal until LCO 3.1.1 is met for MPC dryness.

Note:

The demoisturizer module must maintain the temperature of the helium exiting the FHD below the Technical Specification limits continuously from the end of the drying operations until the MPC has been backfilled and isolated. If the temperature of the gas exiting the FHD exceeds the temperature limit, the dryness test must be repeated and the backfill re-performed.

e.

Continue operation of the FHD system with the demoisturizer on.

£ While monitoring the temperatures into and out of the MPC, adjust the helium pressure in the MPC to provide a fill pressure as required by LCO 3.1.1.

g.

Open the FHD bypass line and Close the vent and drain port RVOAs.

h.

Shutdown the FHD system and disconnect it from the R YOAs.

1.

Remove the vent and drain port RYOAs.

9.

Weld the vent and drain pott cover plates and perform NDE in accordance with the licensing drawings using approved procedures. Repair any weld defects in accordance with the applicable code and re-perform the NDE until the weld meets the required acceptance criteria.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-16 Rev. 5

I IOLTEC PRe~RIETARY INFORMATIOl<l

10.

Perform a leakage test of the MPC vent port cover plate and drain port cover plate in accordance with the following and site-approved procedures:

a.

If necessary, remove the cover plate set screws.

b.

Flush the cavity with helium to remove the air and immediately install the set screws recessed approximately 114 inch below the top of the cover plate.

c.

Plug weld the recess above each set screw to complete the penetration closure welding in accordance with the licensing drawings using approved procedures.

Repair any weld defects in accordance with the applicable code and re-perform the NDE until the weld meets the required acceptance criteria.

d.

Flush the area around the vent and drain cover plates with compressed air or nitrogen to remove any residual helium gas.

e.

Perfom1 a helium leakage rate test of vent and drain cover plate welds in accordance with the Mass Spectrometer Leak Detector (MSLD) manufacturer's instructions and leakage test methods and procedures of ANSI Nl4.5 [9. l.2]. The MPC Helium Leak Rate acceptance criterion is provided in LCO 3.1.1.

11.

Weld the MPC closure ring as follows:

a.

Install and align the closure ring.

b.

Weld the closure ring to the MPC shell and the MPC lid, and perform NDE in accordance with the licensing drawings using approved procedures. Repair any weld defects in accordance with the applicable code and re-perform the NDE until the weld meets the required acceptance criteria.

c.

If necessary, remove the A WS.

9.2.5 Preparation for Storage ALARA Warning:

Dose rates will rise around the top of the annulus as water is drained from the annulus. Apply appropriate ALARA practices.

Caution:

Limitations for the handling an MPC containing high burn-up fuel in a HI-TRAC VW are evaluated and established on a canister basis to ensure that acceptable cladding temperatures are not exceeded. Refer to SAR Chapter 4.

1.

Drain the remaining water from the annulus.

2.

Perform the HI-TRAC VW surface dose rate measurements in accordance with the Technical Specifications. Measured dose rates must be compared with calculated dose rates that are consistent with the calculated doses that demonstrate compliance with the HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-17 Rev. 5

I IOLTEC PRO~RIETARY INFORMATIOl<l dose limits of 1 OCFR 72.104(a). Remove any surface contamination from the HI-TRAC surfaces as required by LCO 3.2.1.

Note:

HI-STORM FW receipt inspection and preparation may be performed independent of procedural sequence, but prior to transfer of the loaded MPC. See Table 9.2.3 for example of HI-STORM FW Receipt Inspection Checklist.

3.

Perform a HI-STORM FW receipt inspection and cleanliness inspection in accordance with a site-approved inspection site-approved inspection checklist, if required.

Note:

MPC transfer may be performed at any location deemed appropriate by the licensee. The following steps describe the general transfer operations. The HI-STORM FW may be positioned on an air pad, roller skid or any other suitable equipment in the cask receiving area or at the ISFSL The HI-STORM FW or HI-TRAC VW may be transferred to the ISFSI using any equipment specifically designed for such a function. The licensee is responsible for assessing and controlling floor loading conditions during the MPC transfer operations.

Installation of the lid, vent screen, and other components may vary according to the cask movement methods and location of MPC transfer.

9.2.6 Placement of HI-STORM FW into Storage

1.

Position an empty HI-STORM FW module at the designated MPC transfer location.

2.

Remove any road dirt with water. Remove any foreign objects from cavity locations.

3.

Transfer the HI-TRAC VW to the MPC transfer location.

Note:

For most efficient heat rejection, the HI-TRAC transfer cask is envisaged to be routinely handled in the vertical orientation. However, architectural constraints at a plant, such as a low roll-up door opening or a low hung overhead duct work, may require the cask to be tilted or even downended for a short duration during this transfer step (as described in Subsection 4.5.1).

In such a case, the continued thermal compliance of the cask's contents to ISG-11 Rev 3 will be verified by simulating the short term handling operation on the NRC-reviewed Fluent model and any possible adverse effect on the occupational dose shall be mitigated by use of suitably configured custom shielding."

4.

Install the mating device on top of the HI-STORM FW.

5.

Position HI-TRAC VW above HI-STORM FW.

6.

Align HI-TRAC VW over HI-STORM FW and mate the components.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-18 Rev. 5

I IOLTEC PROPRIETARY INFORMATION

7.

Attach the MPC to the lifting device in accordance with the site-approved nggmg procedures.

8.

Raise the MPC slightly to remove the weight of the MPC from the mating device.

9.

Remove the bottom lid from HI-TRAC VW using the mating device.

ALARA Warning:

Personnel should remain clear (to the maximum extent practicable) of the HI-STORM FW annulus when HI-TRAC VW is removed due to radiation streaming. The mating device may be used to supplement shielding during removal of the MPC lift rigging.

10.

Lower the MPC into HI-STORM FW.

11.

Disconnect the MPC lifting slings from the lifting device.

Note:

It may be necessary, due to site-specific circumstances, to move HI-STORM FW from under the empty HI-TRAC VW to install the HI-STORM FW lid, while inside the Part 50 facility. In these cases, users shall evaluate the specifics of their movements within the requirements of their Part 50 license.

12.

Remove HI-TRAC VW from on top of HI-STORM FW with or without the HI-TRAC bottom lid.

13.

Remove the MPC lift rigging and install plugs in the empty MPC bolt holes*.

14.

Place HI-STORM FW in storage as follows:

Note:

Closing the mating device drawer while the MPC is in the HI-STORM will block air flow.

The mating device drawer shall remain open, to the extent possible, such that the open air path is at least as large as the HI-STORM Lid vent openings until the mating device is to be removed from the HI-STORM. When the mating device drawer is closed for mating device removal, the process shall be completed in an expeditious manner.

a.

Remove the mating device.

b.

Inspect the HI-STORM FW lid studs and nuts or lid closure bolts for general condition. Replace worn or damaged components with new ones.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-19

I IOLTEC PROPRIETARY l~JFORMATION Note:

Unless the lift has redundant drop protection features ( or equivalent safety factor) for the HI-STORM FW lid, the lid shall be kept less than 2 feet above the top smface of the overpack.

This is performed to protect the MPC lid from a potential HI-STORM FW lid drop.

c.

Install the HI-STORM FW lid and the lid studs and nuts or lid closure bolts*.

d.

Remove the HI-STORM FW lid lifting device and, if necessary, install the hole plugs* in the empty lift holes. Store the lifting device in an approved plant storage location.

Warning:

HJ-STORM FW dose rates are measured to ensure they are within expected values. Vose rates exceeding the expected values could indicate that fuel assemblies not meeting the CoC may have been loaded.

e.

Perform the HI-STORM FW smface dose rate measurements in accordance with the Technical Specifications. Measured dose rates must be compared with calculated dose rates that are consistent with the calculated doses that demonstrate compliance with the dose limits of l OCFR 72. l 04( a).

f.

Secure HI-STORM FW to the transpo1ter device as necessary.

Note:

The site-specific transport route conditions must satisfy the requirements of the Technical Specification.

g.

Perform a transport route walkdown to ensure that the transport conditions are met.

h.

Transfer the HI-STORM FW to its designated storage location at the appropriate pitch.

1.

Attach the HI-STORM FW temperature elements (if used) and screens.

15. If required per CoC Condition #8 the user must perform the following annular air flow thermal test or cite a test report that was performed and prepared by another user.

a.

The annular air flow thermal test shall be conducted at least 7 days after the HI-STORM is loaded in order for the overpack to establish thermal equilibrium.

b.

The user or other qualified engineer shall calculate and record the actual heat load of the fuel stored in the HI-STORM.

c.

To minimize the effects on the annular air flow, the test shall be perfom1ed when the weather is relatively dry and calm.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-20

HOLTEC flROflRIETARY lt~FORMATION

d.

The ambient air temperature at the cask shall be recorded.

e.

The test data shall be collected for the annular flow between the MPC and HI-STORM inner shell as follows:

1.

The outlet vent screen shall be removed from one outlet vent, if necessary for instrument access. Alternatively, if access ports have been provided in the HJ-STORM lid, the access po11 plugs may be removed and access po11s used for instrument access.

2.

A hot wire anemometer or similar flow measuring instrument shall be inserted into the annular space between the MPC and HI-STORM inner shell.

3.

The flow measuring instrument shall be at positioned at least 6" below the top of the MPC and shall not significantly block the air flow.

4.

The instrument shall not be placed too close to the MPC or HJ-STORM shells to avoid edge effects on the flow.

5.

The outlet gamma shield and vent screen shall be re-installed if removed.

6.

Measurements of the air flow shall be taken and recorded for a minimum of three places radially across the annular gap.

7.

The outlet vent screen and gamma shield shall be removed from the outlet vent, if necessary, and the flow measuring instrument removed.

8.

The outlet gamma shield and vent screen shall be re-installed if removed.

9.

Re-install access port plugs if removed.

f.

Air flow in each of the three remaining outlet vents or access ports shall be measured and recorded in accordance with step 15.e above.

g.

All test data shall be transmitted to the general license holder for evaluation and validation of the thermal model.

h.

Users shall forward test and analysis results to the NRC in accordance with 10 CFR 72.4.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-21 Rev. 5

lelOb+EG PROPRIETARY INFORMATIOl<l Table 9.2.1 HI-STORM FW SYSTEM ANCILLARY EQUIPMENT OPERATIONAL DESCRIPTION Equipment Important To Safety Description Cilassification

• Air Pads/Rollers Not Important To Safety Used for HT-STORM FW or HT-TRAC VW cask positioning. May be used in conjunction with the cask transporter or other HT-STORM FW or HT-TRAC VW lifting device.

Annulus Not Important To Safety The Annulus Overpressure System is used for protection Overpressure System against spent fuel pool water contamination of the external MPC shell and baseplate surfaces by providing a slight annulus overpressure during in-pool operations.

Automated Welding Not Important To Safety Used for remote field welding of the MPC.

System Cask Transporter Not Important to Safety Used for handling of the HI-STORM FW overpack and/or unless used for MPC the Hl-TRAC VW Transfer Cask around the site. The transfers cask transporter may take the form of heavy haul transfer trailer, special transporter or other equipment specifically designed for such a function. May also be used for MPC transfers if a1Poropriately configured.

Lid and empty Not Important To Safety, Used for rigging components such as the HI-TRAC VW component lifting Rigging shall be provided top lid, bottom lid, MPC lid, A WS, and HI-STORM FW rigging in accordance with Lid and the empty MPC.

NUREG 0612 Helium Backfill Not Important To Safety Used for controlled insertion of helium into the MPC for System pressure testin.g, blowdown and placement into storage.

HI-STORM FW Determined site-A special lifting device used for connecting the crane (or Special Lifting specifically based on type, other primary lifting device) to the HI-STORM FW for Device location, and height of lift cask handling.

being performed. Special lifting devices shall be provided in accordance with ANS! N 14.6.

HI-TRAC VW Lift Determined site-Used for connecting the crane (or other primary lifting Yoke/Lifting Links specifically based on type device) to the HT-TRAC VW for cask handling. Does not and location, and height of include the crane hook (or other primary lifting device).

lift being performed. Lift May include one or more extensions to prevent immersion yoke and lifting devices for of the crane hook into the spent fuel pool water..

loaded HI-TRAC VW handling shall be provided in accordance with ANSI N l4.6.

HJ-TRACVW Not Important To Safety A steel frame used to support HI-TRAC VW during transfer frame delivery, on-site movement and upending/downending operations.

• Per Holtec's QA program, components may be purchased to a higher safety category than what is designated in this table.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-22 Rev. 5

I IOLTEC PROF'RIETARV INFORMAi ION Table 9.2. l HI-STORM FW SYSTEM ANCILLARY EQUIPMENT OPERATIONAL DESCRIPTION Equipment Important To Safety Description CJassification

• inflatable Annulus Not important To Safety Used to prevent spent fuel pool water from contaminating Seal the external MPC shell and baseplate surfaces during in-pool operations.

MPC Lift J mportant To Safety -

MPC lift attachments consist of the strongback and Attachments Category A. MPC Lift attachment hardware. The MPC lift attachments are used Attachments shall be to support the MPC during MPC transfer from HJ-TRAC provided in accordance VW into HI-STORM FW and vice versa. The ITS with ANSI Nl4.6.

classification of the lifting device attached to the attachments may be lower than the attachment itself, as detennined site-specifically. Lift Attachments may take different forms based on site specific needs and may include remote disconnect features.

Pressure Test System Not lmportant to Safety Used to pressure test the MPC lid-to-shell weld.

HI-TRAC Lift Block Important-To-Safety Used to attach the HI-TRAC to the lifting yoke.

Category A. Lift Blocks shall be provided in accordance with ANSI Nl4.6.

Mating Device I mportant-To-Safcty -

Used to mate HI-TRAC VW to HI-STORM FW during Category B transfer operations. Used to shield operators during MPC transfer operations. Includes sliding drawer for use in removing HI-TRAC VW bottom lid.

MPC Lifting Slings Important To Safety -

Used to secure the MPC to the overhead lifting device Category A (When used during HI-TRAC VW bottom lid removal and MPC inside a Part 50 structure);

transfer operations. Attaches between the MPC lift Important To Safety -

attachments and the lift yoke or overhead lifting device.

Category B (When used outside a Part 50 structure)

- Rigging shall be provided in accordance with NUREG 0612.

MPC Upending Not Important to Safety Used to evenly support the MPC during handling and Device upending operations and help control the upending process.

MSLD (Helium Not Important lo Safety Used for helium leakage testing of the MPC closure Leakage Detector) welds.

Vacuum Drying Not Important To Safety Used for removal of residual moisture from the MPC System following water draining.

Forced Helium Not Important To Safety Used for removal of residual moisture from the MPC Dehydration System following water draining.

Vent and Drain Not Important To Safety Used to access the vent and drain ports. The vent and RVOAs drain RVOAs allow the vent and drain ports to be operated like valves.

Weld Removal Not Important To Safety Semi-automated weld removal system used for removal of System the MPC field weld to support unloading operations.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-23

I IOLTEC PROPRIETARY INFORMATION Table 9.2.2 HI-STORM FW SYSTEM INSTRUMENTATION

SUMMARY

FOR LOADING AND UNLOADING OPERATIONS t Instrument Function Contamination Survey Monitors fixed and non-fixed contamination levels.

Instruments Dose Rate Monitors/Survey Monitors dose rate and contamination levels and ensures Equipment proper function of shielding. Ensures assembly debris is not inadvertently removed from the spent fuel pool during overpack removal.

Flow Rate Monitor Monitors fluid flow rate during various loading and unloading operations.

Heliwn Mass Spectrometer Ensures leakage rates of welds are within acceptable limits.

Leakage Detector (MSLD)

Volumetric Examination Used to assess the integrity of the MPC lid-to-shell weld.

Testing Rig Pressure Gauges Ensures correct pressure during loading and unloading operations.

Temperature Gauges Monitors the state of gas and water temperatures during closure and unloading operations.

Vacuum Gages (Optional)

Used for vacuum drying operations and to prepare an MPC evacuated sample bottle for MPC gas sampling for unloading operations.

Moisture Monitoring Used to monitor the MPC moisture levels as part of the Instmments moisture removal system.

t All instruments require calibration. See figures at the end of this section for additional instruments, controllers and piping diagrams.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-24

HOLTEC PROPRIETARY INFORMATIOl<l Table 9.2.3 HI-STORM FW SYSTEM OVERP ACK INSPECTION CHECKLIST Note:

This checklist provides the basis for establishing a site-specific inspection checklist for the HI-STORM FW overpack. Specific findings shall be brought to the attention of the appropriate site organizations for assessment, evaluation and potential corrective action prior to use.

HI-STORM FW Overpack Lid:

1.

Lid studs and nuts or lid closure bolts shall be inspected for general condition*.

2.

The painted surfaces shall be inspected for corrosion and chipped, cracked or blistered paint.

3.

All lid surfaces shall be relatively free of dents, scratches, gouges or other damage.

4.

The lid shall be inspected for the presence or availability of studs and nuts and hole plugs, as required.

5.

Lid lifting device attachment points/bolt holes shall be inspected for dirt and debris, deformation, and thread condition as applicable.

6.

Lid bolt holes shall be inspected for general condition.

7.

Vent screens shall be inspected for proper fit and for tears and holes that would allow debris entry into the vent openings.

8.

Vent openings shall be inspected for foreign material that may cause vent blockage.

HI-STORM FW Main Body:

1.

Lid bolt holes shall be inspected for dirt, debris, and thread condition.

2.

Vents shall be free from obstructions.

3.

Vent screens shall be inspected for proper fit and for tears and holes that would allow debris entry into the vent openings.

4.

The interior cavity shall be free of debris, litter, tools, and equipment.

5.

Painted surfaces shall be inspected for corrosion, and chipped, cracked or blistered paint.

6.

The nameplate shall be inspected for presence, legibility, and general condition and conformance to Quality Assurance records package.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-25

I IOLTEC PROPRIETARY INFORMATION Table 9.2.4 MPC INSPECTION CHECKLIST Note:

This checklist provides the basis for establishing a site-specific inspection checklist for MPC.

Specific findings shall be brought to the attention of the appropriate site organizations for assessment, evaluation and potential corrective action prior to use.

MPC Lid and Closure Ring:

1.

The MPC lid and closure ring surfaces shall be relatively free of dents, gouges or other shipping damage.

2.

The drain line shall be inspected for straightness, thread condition, and blockage.

3.

Vent and Drain attachments shall be inspected for availability, thread condition operability, and general condition.

4.

Fuel spacers (if used) shall be inspected for availability and general condition.

5.

Drain and vent port cover plates shall be inspected for availability and general condition.

6.

Serial numbers shall be inspected for readability.

7.

The MPC lid lift holes shall be inspected for thread condition*.

8.

The MPC lid, cover plates, and closure ring shall be checked for proper fit-up.

MPC Main Body:

1.

All visible MPC body surfaces shall be inspected for dents, gouges, or other shipping damage.

2.

Fuel cell openings shall be inspected for debris, dents, and general condition.

3.

Basket panels shall be inspected for gross deformation that may inhibit fuel assembly insertion.

4.

Lift lugs shall be inspected for general condition.

5.

Lift lug threads shall be in inspected for thread condition

6.

Verify proper MPC basket type for contents.

7.

Serial numbers shall be inspected for readability.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-26

I IOLTEC PRe~RIETARY INFORMATIOl<l Table 9.2.5 HI-TRAC VW TRANSFER CASK INSPECTION CHECKLIST Note:

This checklist provides the basis for establishing a site-specific inspection checklist for the HI-TRAC VW Transfer Cask. Specific findings shall be brought to the attention of the appropriate site organizations for assessment, evaluation, and potential corrective action prior to use.

HI-TRAC VW Main Body:

1.

The painted surfaces shall be inspected for corrosion, chipped, cracked, or blistered paint.

2.

Annulus inflatable seal groove shall be inspected for cleanliness, scratches, dents, gouges, sharp corners, burrs, or any other condition that may damage the inflatable seal.

3.

The nameplate shall be inspected for presence and general condition.

4.

The neutron shield jacket shall be inspected for leaks.

5.

Neutron shield jacket pressure relief device shall be inspected for presence and general condition.

6.

The neutron shield jacket fill and neutron shield jacket drain plugs shall be inspected for presence, leaks, and general condition.

7.

Bottom lid flange surface shall be clean and free of large scratches and gouges that may inhibit sealing of the lid to body.

8.

The threaded anchor locations, if provided, shall be inspected for thread damage, excessive wear, and general condition.

HI-TRAC VW Bottom lid:

1.

Seal shall be inspected for cracks, breaks, cuts, excessive wear, flattening, and general condition.

2.

Drain line shall be inspected for blockage and thread condition.

3.

The lifting holes shall be inspected for thread damage.

4.

The bolts shall be inspected for indications of overstressing (i.e., cracks and deformation, thread damage, and excessive wear*).

5.

The painted surfaces shall be inspected for corrosion, chipped, cracked, or blistered paint.

6.

Threads shall be inspected for indications of damage.

• Upon installation, studs, nuts, and threaded plugs shall be cleaned and inspected for damage or excessive thread wear (replaced if necessary) and coated with a light layer of Loctite N-5000 High Purity Anti-Seize ( or equivalent).

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-27

HI-TRA,C LIFT BLOCK HOLTEC PROPRIETARY INFORMATION FIGURE 9.2.1: MPC INSTALLATION IN HI-TRAC HOLTEC CNTERNA TTONAL COPYRIGHTED MA TERJAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-28

I IOLTEC PROF'~ll:TARV INFORMAi ION FIGURE 9.2.2: HI-TRAC LIFTING SHOWN USING A REPRESENTATIVE LIFT YOKE HOLTEC £NT.ERNA TTONAL COPYRJGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-29

I IOLTEC PROPRIETARY INFORMA'TIOI~

FIGURE 9.2.3: HI-TRAC PLACEMENT IN THE SPENT FUEL POOL HOLTEC £NT.ERNA TTONAL COPYRJGHTED MATERIAL REPORT HI-21 14830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-30

MOb+EG PROPRIETARY INFO~MATIOI~

FIGURE 9.2.4: FUEL ASSEMBLY PLACEMENT IN THE MPC (CRANE NOT SHOWN)

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-31

1 IOLTEO PROPRIETARY INFORMATlm4 FIGURE 9.2.5: MPC LID INSTALLATION USING THE LIFT YOKE HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-32

I IOLTEC PROPRIETARY INFORMATlm 4 FIGURE 9.2.6: HI-TRAC REMOVAL FROM THE SPENT FUEL POOL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-33

MObl'EC PROPRIETARY INFO~MATIOI~

FIGURE 9.2.7: HI-TRAC PLACEMENT IN THE CASK PREPARATION AREA HOLTEC £NT.ERNA TIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-34

HObTEC 12ROPRIETARY INEORMAIION FIGURE 9.2.8: HI-TRAC PLACEMENT ON THE ID-STORM 100 OVER.PACK USING THE MATING DEVICE HOLTEC INT.ERNA TIONAL COPYRIGHTED MATERIAL REPORT HI-21 14830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-35

HQI TEC PROPRIETARY IMFORMATlm4 FIGURE 9.2.9: HI-TRAC READY FOR MPC TRANSFER INTO HI-STORM FW OVERPACK HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-36

MObTEC PROPRIETARY INFORMATION FIGURE 9.2.10: MPC TRANSFER INTO HI-STORM FW OVERP ACK (CUT-AWAY VIEW)

HOLTEC CNT.ERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-37

HOLTEC flROflRIETARY ltffORMATION FIGURE 9.2.11: MPC SHOWN FULLY LO\\\\i'ERED INTO HI-STORM (HI-TRAC NOT SHOWN)

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-38

HObTEC PROPRIETARY INFORMATION FIGURE 9.2.12: HI-STORM FW OVERPACK MOVEMENT SHOWN WITH A REPRESENTATIVE CASK TRANSPORTER HOLTEC £NT.ERNA TIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-39

I IOLTEC PROPRIETARY INFORMATlm4 FIGURE 9.2.13: HI-STORM SHOWN IN STORAGE WITH THE LID INSTALLED HOLTEC £NT.ERNA TIONAL COPYRIGHTED MATERIAL REPORT HI-21 14830 Rev. 5 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-40

I IOLTEC PROPRIETARY INFORMATION 9.3 ISFSI OPERATIONS The HI-STORM FW system heat removal system is a totally passive system. Maintenance on the HI-STORM FW system is typically limited to cleaning and touch-up painting of the overpacks, repair and replacement of damaged vent screens, and removal of vent blockages (e.g., leaves, debris). The heat removal system operability surveillance should be performed after any event that may have an impact on the safe functioning of the HI-STORM FW system. These include, but are not limited to, wind storms, heavy snow storms, fires inside the ISFSI, seismic activity, flooding of the ISFSI, and/or observed animal or insect infestations. The responses to these conditions involve first assessing the dose impact to perfonn the corrective action (inspect the HI-STORM FW overpack, clear the debris, check the cask pitch, and/or replace damaged vent screens), perform the corrective action, verify that the system is operable ( check ventilation flow paths and radiation). In the unlikely event of significant damage to the HI-STORM FW, the situation may warrant removal of the MPC, and repair or replacement of the damaged HI-STORM FW overpack. If necessary, the procedures in Section 9.2 may be used to reposition a HI-STORM FW overpack for minor repairs and maintenance. In extreme cases, Section 9.4 may be used as guidance for unloading the MPC from the HI-STORM FW.

Note:

The heat removal system operability surveillance involves performing a visual examination on the HI-STORM FW exit and inlet vent screens to ensure that the vents remain clear or verifying the temperature rise from ambient to outlet is within prescribed limits if using a temperature monitoring system. The metallic vent screens if damaged may allow leaves, debris, or animals to enter the duct and block the flow of air to the MPC.

ALARA Warning:

Operators should practice ALARA principles when inspecting the vent screens. Binoculars or horoscopes may be used to allow the operator to perform the surveillance from a low dose area.

1. Perform the heat removal operability surveillance in accordance with the CoC.

2. ISFSI Security Operations shall be performed in accordance with the approved site security program plan.

HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL REPORT HI-2114830 HI-STORM FW SYSTEM FSAR Revision 5, June 20, 2017 9-41 Rev. 5