ML20137D086

Discusses Licensee & NRC Insp of Various Technical Problems Re VSC-24 at ANO on 960506-10

ML20137D086
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/15/1996
From:	Stokley J SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	Marissa Bailey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9703260007
Download: ML20137D086 (44)

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f _ _Y May 15,1996 j Science Applications Intemational Corporation An Emp'oyee-Owned Company Ms. Marissa G. Bailey U.S. Nuclear Regulatory Commission Division of Fuel Cycle and Material Safety One White Flmt -

_g3 11555 Rockville Pike 3(oM Rockville, MD 20852 1 1

Subject:

Contract NRC-02-95-003, Task Order No.18, Inspection at ANO to Assist in Evaluation of 72.48 Issues and Dry Run Procedures.

Dear Ms. Bailey:

l SAIC participated in the NRC inspection of various technical problems related to the VSC-24 l at Arkansas Nuclear One (ANO). The inspection was a site visit, held May 6 through 10,1996.

The NRC team included yourself; the Region IV Team Coordinator, Vincent Everett; Region IV health physicist, Tom Andrews; the NRC resident inspector, Jim Melfi; NMSS representatives, Ken Battige and Steve O'Connor; NRR representatives, Paul Harris, and Meena Khanna; as well as two members from SAIC, David Williamson, and myself. I Following NRC direction, a total of 73 issues identified by ANO as "72.48 issues" were i evaluated by the inspection team. Enclosed are the issues which SAIC evaluated. We have l already provided you with a disc in Wordperfect 5.1 for your convenience. Significantly, no  ;

issues evaluated by the SAIC team were identified as unresolved safety issues at the time of the  ;

inspection.

Many of the design changes reviewed during the inspection were previously evaluated by SAIC as a part of the review of Amendment 1 of the VSC-24, which is currently being processed by the NRC as an amended version of the original Certificate of Compliance. These design changes were appropriately documented by ANO. Two minor discrepancies relating to specific drawings were noted in our enclosed report, item number 52, " Fabrication Specifications for the MSB, MTC, and VCC."

As a matter of record, SAIC notes that the review ofitems associated with the heavy lift program (NUREG 0612) was not pursued during this inspection, because Region IV inspector, Chuck Paulk has been following this issue. Ilowever during SAIC's review ofitem number 73, " Dry Cask Impact Inhibitor " the SAIC team requested calculation packages 92-D-20001-40 and - 42.

The intent of requesting these backup documents was to follow the analysis to show how the dry cask impact inhibitor was designed, and what the basis for the deceleration was. SAIC did not have time to perform an in-depth review of these calculation packages, but a preliminary reading showed that ANO has extensively pursued the cask drop issue inside the spent fuel pool.

9703260007 960515 NMSS ADOCK 05000313 g PDR 11251 Roger Bacon Drive, Reston, Virginia 22090 *(703) 318-4500 Other SAIC Omces. Amunuerque. Conwah Sonngs. Dayton, Fans Chwch. Huntsville. Las Vegas, Loe Alton, Los Anyetes McLean, Oak Rasge, Ortank. San Dego. Seattle. Tucson

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5AE l l This letter evaluation and the enclosures ate submitted in partial satisfaction of the statement of  !

! work described in the subject task order.

i I Sincerely, t 1

ohn R. Stokley, P.E.

cc w/o enclosure:

David Tiktinsky, Project Officer, NMSS John Eastman, Contract Administration John Linehan, Director, PMDA NRC Document Control Branch j Eiic Leeds, NMSS Fritz Sturz, NMSS Mike Raddatz, NMSS i cc w/ enclosure Steve O'Connor, NMSS bec w/ enclosure:

David Williamson j l

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l ANO 10CFR72.48 Reviews l

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l Independent Spent Fuel Storage Inspection Arkar..sas Nuclear One May 6 - 10, 1996 John R. Stokley David H. Williamson Science Applications International Corporation 11251 Roger Bacon Drive Reston, Virginia 22090 (703) 318-4600 (703) 709-1042 FAX I

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: John Stokley, P.E., Science Applications International Corporation ANO, REVIEW NUMBER: 1000.131 REVIEW TITLE: 10CFR50.59 Review Program  !

l DESCRIPTION: This procedure was basically an update of the l plant's normal procedure for conducting-50.59 reviews. It designates'that 10CFR72.48 reviews must be performed by personnel associated'with the ISFSI project, and not by 50.59 reviewers, unless that reviewer is also designated as a 72.48 reviewer.

REVIEW CONCLUSIONS: The revision to the existing procedure is appropriate in order to distinguish between the two parts of the i Code of Federal Regulations. The training / familiarization requirements necessary to perform 10CFR72.48 reviews are specific !

to the ISFSI project. l l

RECOMMENDED POSITION: Accept the change to the procedure, subject to Part 50 approval.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT l 5/7/96 PREPARED BY: John Stokley, P.E., Science Applications International Corporation ANO REVIEW Nm(BER: Procedure 1005.002 Rev./ Change No. 13  ;

REVIEW TITLE: Control of Heavy Loads

. DESCRIPTION: The existing procedure controlling the handing of heavy loads at ANO was revised to include the ISFSI activities.

The procedural changes apply to turbine building cranes as they will be used to handle the MTC,MSB and the other special pieces of equipment inside the spent fuel pool / auxiliary building.

Everything in this procedure takes place inside the spent fuel pool building.

REVIEW CONCLUSIONS: The changes to this procedure are appropriate,however because this procedure is a 10CFR50 function, the final approval should come from the Part 50 personnel.

I RECOMMENDED POSITION: Accept the change, subject to Part 50 approval. '

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT l 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications ,

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! ANO REVIEW NUMBER: Procedure 1302.024 Rev./ Change No. O I

, REVIEW TITLE: Dry Fuel Storage Equipment Preparation 4

DESCRIPTION: This procedure ensures the proper preparation and organization of the VSC components and support equipment  ;

necessary to begin loading fuel into the casks.

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!' REVIEW CONCLUSIONS: The level of detail included in this  ;

procedure is consistent and in conformance with requirements of i the CofC. >

RECOMMENDED POSITION: ncetptable, pending concurrence with Part '

50 review.

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i INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96  ;

l J PREPARED BY: David Williamson, P.E., Science Applications  !

-International Corporation l

i ANO REVIEW NUMBER: Procedure 1302.024 Rev. O PC-1 REVIEW TITLE: Dry Fuel Storage Equipment Preparation 1

DESCRIPTION: This procedure clarifies height restrictions on lifting the MTC in the Fuel Handling Area. Specifically, the I

proposed change allows the same relaxation in the installation of the MTC on the work platform as when removing the MTC from the platform. ,

l REVIEW CONCLUSIONS: This change results in uniformity of height restrictions.

RECOMMENDED POSITION: Acceptable, pending concurrence with Part 50 review.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/9/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO REVIEW Nm(BER: Procedure 1302.024 Rev./ Change No. 1 REVIEW TITLE: Dry Fuel Storage Equipment Preparation DESCRIPTION: This procedure ensures proper preparation of the VSC components and support equipment necessary to begin loading fuel -

into the casks. Specifically, this procedure requires cleanliness inspections as stated in SAR Sections 8.1 and 9.1.1.2.

REVIEW CONCLUSIONS: The level-of detail included in this procedure is consistent and in conformance with requirements of the CofC.

RECOMMENDED POSITION: Acceptable, pending concurrence with Part 50 review.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO REVIEW NUMBER: OP-1302.024 Rev./ Change No. Rev 2 REVIEW TITLE: Dry Fuel Storage Equipment Preparation DESCRIPTION: The change to the procedure involves the addition of requirements for impact limiters on the MTC and the verification that the ceramic tiles are in place in the VCC.

REVIEW CONCLUSIONS: The impact limiter is required when the MTC/MSB is lifted higher than 60 inches above the train bay floor in order to reduce loads imparted to the MTC/MSB in the event of a cask drop. The tiles are required to eliminate rusting at.the MSB VCC interface and thus to facilitate retrieval of the MSB from the VCC at end of life.

RECOMMENDED POSITION: Acceptable, pending concurrence with Part 50 review.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT l 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO REVIEW 17 UMBER: Procedure 1302.024 Rev./ Change No. 2 PC-1

-REVIEW TITLE: Dry Fuel Storage Equipment Preparation DESCRIPTION: This change provides additional details on lifting the MTC. No fuel is in the MTC at this time. The changes correspond to steps already included in procedure 1302.025.

REVIEW CONCLUSIONS: This change is consistent with the requirements of the CofC.

RECOMMENDED POSITION: Acceptable, pending concurrence with Part 50 review.

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1 INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 l PREPARED BY: John Stokley, P.E., Science Applications l International Corporation ANO , EVALUATION Nm(BER: 1302.025 Rev./ Change Rev'1 PC'1, PC 2,  ;

PC 3, and Rev 2 PC 1 >

EVALUATION TITLE: Spent Fuel Removal and Dry Storage Operations I

l DESCRIPTION: This procedure covers the loading of the spent fuel-into the VSCs, and movement-to and placement of these casks on the storags pad. Through procedure steps 9.9.74,the subject matter relates to activities covered by 10 CFR 50. The balance of the procedures relate to matters occurring outside the spent fuel pool building and are covered by 10 CFR 72. The change in this ,

procedure precludes moving the MTC over the train bay or through the spent fuel pool area equipment hatch. The change was prompted by a concern about the acceptability of the SAR cask drop j analysis. Various other revisions were included.

l REVIEW CONCLUSIONS: This procedure was not reviewed-in all detail, however most (about 95%) of the procedure is covered by 10 CFR 50.

l RECOMKENDED POSITION: Accept the procedure, pending concurrence of Part 50 review. Accept the procedures which relate to the.10 i CFR 72. The basis is the C of C, specifically, the limiting  !

condition of operation 14.2.13 of the SER for the C of C.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: John Stokley,.P.E., Science Applications International Corporation ,

L ANO REVIEW NW(BER: 1402.091, Rev 4 l l REVIEW TITLE: Visual Inspection of Special Lifting Devices  !

DESCRIPTION: This procedure added the dry fuel storage ,

components, the MTC/MSB and the MTC yoke, to the items requiring visual inspection before use as part of the control of heavy loads.

REVIEW CONCLUSIONS: The inclusion of these items is appropriate as a part of 10CFR50 requirements, NUREG-0612, and ANSI N14.6 -

1978.

RECOMMENDED POSITION: Accept the revision to the procedure,  !

subject to Part 50 concurrence. '

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33, 34, and 35 INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: John Stokley, P.E., Science Applications International Corporation

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1 ANO EVALUATION NmGER: 1402.230 Rev. O, Rev 1, and Rev. 2 i i

l EVALUATION TITLE: VCC Rail Car Hydraulic Jacking and Air Transporter Operation DESCRIPTION: This procedure provides operating instructions for the hydraulic jacking system which is used to raise and lower the

VCC rail car and the VCC air transporter which is used to lift ,

and move the VSC with the MSB on the pad. I REVIEW CONCLUSIONS: This procedure is written as a part of the general requirements and conditions outlined in 14.1.2 of the SER-

for the C of C, " operating procedures." The procedure will be subject to dry run prior to actual handling of the VCC.

RECOMMENDED POSITION: Recommend acceptance of procedure.

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INSPECTION' REPORT-ANO NUCLEAR POWER PLANT l 5/9/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation i

ANO REVIEW NUMBER: Procedure 1415.048 Rev./ Change No. O REVIEW TITLE: Helium Leak Detection for Dry Fuel Storage MSB DESCRIPTION: This procedure was developed to define the techniques and methods for required helium leak testing on the MSB welds.

REVIEW CONCLUSIONS: The procedure was examined and found to be

in compliance with 1.2.2 and 1.2.7 of the C of C.

RECOMMENDED POSITION: Acceptable. The changes do not require a 72.48 evaluation.

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PREPARED BY: . David Williamson, P.E., Science Applications i International Corporation "

i ANO REVIEW NtmBER: Procedure 2107.005 Rev./ Change No. 10, PC 2 >

l REVIEW TITLE: Lighting and Miscellaneous Electrical Distribution DESCRIPTION: This procedure adds descriptions of the breakers i used in supplying power to the dry fuel storage pad area and the i train bay to support dry cask activities. .

REVIEW CONCLUSIONS: This level of detail is below that required l by the C of C.  ;

I RECOMMENDED POSITION: Acceptable. The changes do not require a  !

72.48 evaluation. ,

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT I 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO REVIEW NUMBER: Procedure 2203.008 Rev./ Change No. 6 REVIEW TITLE: Natural Emergencies DESCRIPTION: This procedure change was. developed to describe actions to be taken to ensure the operability of loaded VSCs after a natural emergency such as tornado, earthquake ,' or flood.

REVIEW CONCLUSIONS: The required actions comply with the statements on inspections after natural emergencies as specified in Section 12.2.3.2 of the VSC SAR.

RECOMMENDED POSITION: Acceptable, pending conversion of Rev. 6 from draft to approved status.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT j 5/7/96 l i PREPARED BY: David Williamson, P.E., Science Applications

International Corporation i i

ANO EVALUATION NtMBER: VSC SAR, and Fabrication Specification l for the MSB, MTC, and VCC, Rev./ Change No. SAR Rev. 0AA EVALUATION TITLE: Document Change Notices ANO-075 and ANO-083 for AVCC Fabrication Specification Relating to Concrete Placement Temperature and Density DESCRIPTION: This document provides for the reduction in concrete density from 145 to 144 lb/ cubic foot to improve constructability of the VCC. Also the maximum allowable concrete placement temperature was increased from 85 to 90 F.

REVIEW CONCLUSIONS: Sierra Nuclear Corporation prepared DCN No.

ANO-075 and ANO-083 to verify the acceptability of a reduction in concrete density from 145 to 144 lb/cu ft and an increase in allowable temperature placement from 85 to 90 F. These DCNs were reviewed and found to be consistent with calculations and construction requirements previously approved. SNC originally and conservatively neglected the reinforcing steel when performing the shielding calculations. The provided calculations show that inclusion of the steel density actually allows for a reduction in density to 142. While the cited ACI code for Hot Weather Concreting, ACI-305, cautions that " difficulty may be encountered with concrete at temperatures approaching 90'F and every effort should be made to maintain it at a lower temperature," the higher temperature is reasonable upper limit.

RECOMMENDED POSITION: Acceptable. The change does not result in an unreviewed safety question.

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4 INSPECTION REPORT-ANO NUCLEAR POWER PLANT l 5/7/96

. PREPARED BY

John Stokley, P.E., Science Applications  !

j International Corporation j ANO EVALUATION Nm(BER: VSC SAR, and Fabrication Specifications i for the MSB,MTC, and VCC '

i EVALUATION TITLE: Changes to VSC Components: MTC, MSB, and VCC i relating to increased length, weight, and other miscellaneous >

j' changes for application of the system to ANO

DESCRIPTION

This 10 CFR 72.48 evaluation was done to include  !

i the types of changes listed in the title. Virtually all of the i

drawings as well as the fabrication specifications have been

' changed. The original C of C for the VSC 24 system includes CE 16x16 fuel. Many of the changes and supporting calculations for i the longer CE 16x16 fuel without control components have  :

previously been submitted by the Vendor SNC, and reviewed by the }

NRC staff as a part of the application for the Amendment 1 version of the VSC 24. This version has not been approved by the ,

NRC staff at this time. In order to perform this inspection in l the time allotted for the inspection, the reviewer has drawn on  ;

. the work previously performed as a part of the Amendment 1  !

version, except that any reference to the fuel with control I components is excluded. Only issues relating to structural, i thermal hydraulic, dose, materials, fabrication specifications j are considered for this inspection. Nuclear criticality safety  !

for the fuel with control components is currently being reviewed  :

! by the Staff, but is not complete.

j Topics covered in this change include: j

A. Desian Chances Associated with the MTC l

j 1. An increase in the length of the MSB, MTC, and VCC of i approximately 12 inches to accommodate the longer CE 16x16 fuel l; without control components.

! 2. An increase in weight of all of the above components.

3. An increase in the center of gravity of all of the above a

components.

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4. The deletion of the middle shell on the MTC. This shell was

originally included to provide a mold surface for the lead pour.

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5. Revised MTC lifting trunnions from solid material, instead of i i

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l hollow trunnions filled with shielding material.

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6. Additional gusset plates between the hydraulic cylinder and the MTC shield doors.

7. MTC drawings and fabrication specs changes to a revised epoxy enamel coating.

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8. MTC drawing notes and bill of materials changed to reflect ANO j requirements.

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9. Redesign of the MTC cask wall, rail assembly, shield doors, j and lifting yoke to reduce the hook weight of the loaded MTC to a maximum of 200,000 pounds.

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[ B: Desion Chances Associated with the MSB

1. The MSB overall length is increased to 192.3 inches to accommodate the longer fuel. (The design changes refer to B & W Mark B fuel with control components and CE 16x16 fuel without I control components.)

2. Increase the diameter and thread depth for the 6 hoist rings I in the MSB structural lid to accommodate the heavier weight.

3. Redesign the shield lid and support plate to be a one-piece I

unit.

. 4. Redesign the vent and drain system to include only one swagelock quick disconnect fitting and one pipe plug.

5. Redesign the drain pipe connection.

6. Redesign the weld at the MSB shell intersection with the bottom plate to be a double-bevel groove weld.

' 7. The MSB shell and bottom plate revised to include epoxy enamel.

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8. Revise drawings and bill of materials to reflect the ANO l fabrication specifications. l C: Desian chances associated with the VCC 1

1. Change in length of the VCC to accommodate the longer fuel. I

2. Alignment plates lengthened to provide more effective shielding during MSB transfer from the MTC.

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3. Chamfer outside corners of VCC instead of radius.

4. Change VCC drawing notes and bill of materials to meet ANO 22

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fabrication requirements. l

5. Revise VCC fabrication specifications to increase the air content by volume from 3 % to 6 %.

I REVIEW CONCLUSIONS:

A: Desion chances associated with the MTC

1. The change in length was assessed for an increase in dose, and environmental impact. These impacts were reviewed by ANO and the NRC inspector. There is negligible impact on the ALARA program or the environment.

2. The increase in weight has been reviewed by ANO and the NRC inspector ( as apart of the Amendment 1 task), and do not involve an unreviewed safety question, a significant increase in occupational exposure, or an unreviewed environmental impact, i

3. The increase in the center of gravity has been reviewed by ANO and the NRC inspector (as a part of the Amendment 1 task),

and does not involve an unreviewed safety issue, significant increase in occupational dose, or an unreviewed environmental impact.

4. Deletion of the middle shell of the MTC has been reviewed by j the NRC inspector and found to be satisfactory. No appreciable 1 increase in occupational dose was detected in the analytical work submitted by the vendor, and checked by the reviewer.

5. Revised lifting trunnion to solid material. This has been reviewed by the NRC inspector and found to be satisfactory. The Basis as NUREG 0612, for heavy lifts.

6. Additional gusset plates for the hydraulic cylinder do not involve an unreviewed safety issue.

7. The revised epoxy enamel coating do not involve an unreviewed safety issue.

8. Revision of MTC drawing notes and b.il of materials. The dotails of the drawings were reviewed in conjunction with the supporting analysis packages for the Amendment 1 of the VSC 24 system. The changes for the MTC do not involve an unreviewed safety issue, hcwever the material changes from A514 grade P or Q to A1 6061 T6 for the cask lifting yoke has not been reviewed.

In view of the fact that this piece of equipment is used inside the spent fuel pool building, the approval and determination of no unreviewed safety issue is to be determined by a 10 CFR 50 review.

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9. The details of the redesign of the MTC cask inner wall, rails and shield doors have been reviewed as a part of the Amendment 1 task and found to have no unreviewed safety issues. The MTC cask lifting yoke has not been reviewed as a part of this inspection.

The approval of the yoke is to be made a part of a 10 CFR 50 review.

B. Desion chances associated with the MSB

1. Change in length of the MSB has been evaluated by the 10CFR72.48 process and by the NRC inspector as a part of the Amendment 1 task. No unreviewed safety issues exist provided no fuel with control components is loaded. The C of C does not currently include any fuel with control components.  !

2. Increase in length of the thread size / depth was reviewed by the 10 CFR 72.48 process and by the NRC inspector as a part of l the Amendment 1 task. No unreviewed safety issues exist.

3. Redesign the shield lid and support plate _as a one-piece shield lid has been reviewed as a part of the 10 CFR 72.48 process and by the NRC inspector as a part of the Amendment 1 task. There are no unreviewed safety issued.

4. The revision to the vent and drain system has been reviewed as a part of4the 10 CFR 72.48 process and by the NRC inspector.

There are no unreviewed safety issues.

5. The change in the drain pipe connection in the shield lid has been reviewed. There are no unreviewed safety issues.

6. The epoxy coating has no unreviewed safety issues.

7. With the exception af the girth weld connecting the MSB shell and the bottom lid, and the weld sizes for the storage sleeve assembly,the changes to the MSB drawing notes and bill of materials have been reviewed as a part of the 10 CFR 72.48 process and by the NRC inspector. The weld callout on drawing AMSB-24-002 sheet 2 of 2 dated 4/26/96, Rev. 4 for the girth weld is not approved. When the NRC inspector raised this. question with ANO, a previous Revision 3 of this drawing showed a correct weld callout. The lastest Revision 4 has a drawing error, and the MSB bottom weld was fabricated to the correct weld.

The welds associated with the basket assembly on drawing AMSB 004 sheet 1 of 4 is reduced in size compared with the drawings approved for the C of C. Sheet 2 of 2 of AMSB-24-002 should be corrected. With the one exception noted on drawing AMSB-24-004, there are no unresolved safety issues.

C. Desian chances associated with the VCC

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1. The change in length of the VCC has been reviewed as a part of the 10 CFR 72.48 process and by the NRC inspector as a part of the Amendment 1 task.

There are no unreviewed safety issues, provided that only fuel approved in the C of C is stored in the VSC, i.e., no control components.

2. The change in length of the alignment plate does not involve an unreviewed safety issue.

3. The change in chamfer radius was made to simplify fabrication and does not involve an unreviewed safety issue.

4. Changes to the VCC drawings were reviewed under the review titled " Miscellaneous Minor Clarification Changes to Subject Documents;" the changes do not involve an unresolved safety issue.

5. The fabrication specification was revised to allow up to 6%

, air entrainment. As the specification also stipulates a density requirement of 144 lb/ cubic ft as evaluated in the evaluation titled " Document Change Notices ANO-075 and NOA-083 for AVCC Fabrication Specification Relating to Concrete Placement Temperature and Density," the change does not involve an unresolved safety issue.

RECOMMENDED POSITION:

A. Desion chances associated with the MTC Recommend that all of the design changes associated with the MTC for the ANO application be accepted to the extent that the fuel to be loaded does not include control components, i.e., it must conform to the fuel specification as recorded in the C of C.

With regard to the MTC cask yoke, the recommendation is that the ANO design be reviewed as a part of 10 CFR 50.

B. Desion chances associated with the MSB With one exception, recommend that all of the design changes associated with the MSB for the ANO application be accepted except that any reference to the fuel with control components is not approved for loading. The exception is the basket assembly weld. The drawing for the girth weld needs correcting.

C. Desion changes associated with the VCC Recommend that all of the design changes associated with the VCC for the ANO application be accepted to the extent that the fuel to be loaded does not include control components, i.e., it must conform to the fuel specification as recorded in the C of C.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications j International Corporation ANO REVIEW Nm4BER: VSC, SAR, SER, and Fabrication Specifications

for the MSB, MTC, and VCC, Rev./ Change No. SAR Rev. 0AA REVIEW TITLE: Miscellaneous Minor Clarification Changes to Subject Documents t

. . DESCRIPTION: This document lists a number of changes which were

! deemed by ANO to be of minor significance. These changes are i generally for editorial, correction, and clarity purposes. Each

item as listed below was identified in-the " Miscellaneous Minor

Clarification Changes to Subject Documents" and was individually

evaluated. l

) REVIEW CONCLUSIONS:

l Item Change Recommendation SER Review 9 correct fuel name acceptable j SAR Review 3 change fab spec name acceptable 11 change fab spec name acceptable  ;

63' change drawing numbers acceptable  !

MSB Fabrication Specification 1 change spec nwnber acceptable 5 change drawing numbers acceptable 10 additional records are to be maintained acceptable Drawing AMSB-24-001 20 drawing clarification acceptable 22 labeling requirement acceptable 33 additional labeling requirement acceptable Drawing AMSB-24-002 40 labeling requirement acceptable MTC Fabrication Specification 1 change fab spec name acceptable 2 added lifting yoke to fab spec acceptable 3 added lifting yoke figure acceptable 4 added client name acceptable 13 added lifting yoke description acceptable 15 added requirement for MSDS sheets acceptable 24 addition of nameplate for yoke acceptable 25 added reference to MTC yoke acceptable VCC Fabrication Specification 27

1 change fab spec name acceptable 2 added requirements in purchase order acceptable 3 added customer name acceptable 4 added costing stipulations acceptable 11 added VCC weight acceptable i 23 formwork construction practice acceptable 25 clarification of standards acceptable 38 revised labeling requirements acceptable Drawing AMSB-24-003 46 drawing correction acceptable 47 drawing clarification acceptable 48 drawing clarification acceptable 49 drawing clarification acceptable Drawing AMSB-24-004 74 drawing correction acceptable Drawing AVCC-24-001 42 added nameplates acceptable 4 44 drawing clarification acceptable

54 drawing clarification acceptable 55 drawing clarification acceptable 56 drawing clarification acceptable 57 drawing clarification acceptable 58 item clarification acceptable Drawing AVCC-24-002 60 drawing clarification acceptable 61 drawing clarification acceptable 64 drawing clarification acceptable 65 drawing clarification acceptable 67-70 part renumbering acceptable 73 outlet fitup revision acceptable 81 outlet numbering acceptable ,

82-84 drawing clarifications acceptable 1 86 drawing clarification acceptable 88 drawing clarification acceptable Drawing AVCC-24-003 92 deleted shim acceptable 94-97 drawing clarifications acceptable Drawing AVCC-24-004 l 104-105 air outlet revision acceptable i 109 outlet numbering acceptable 111 welding revision acceptable

)

i Drawing AVCC-24-005 112-127 drawing clarifications acceptable Drawing AVCC-24-006 130,132,133,135,137,138 rebar location clarifications acceptable Drawing AVCC-24-007 141,142 revised number of items required acceptable Drawing AMTC-24-001 27,30 drawing clarifications acceptable 31 increased number of trunnions acceptable j 38,39 drawing clarifications acceptable l 28 i l

1

l Drawing AMTC-24-002

- 44,45,50,56,58 nameplate addition and drawing clarifications  ;

acceptable Drawing AMTC-24-003 62 drawing clarification acceptable Drawing AMTC-24-005 75,78,79 nameplate addition acceptable j- Drawing AMTC-24-006 l 90,94-97,99 change to solid trunnion acceptable

. Drawing AMTC-24-008

' 103,105-114 l door revision acceptable  !

Drawing AMTC-24-009 i 116-120 modified ram linkage acceptable '

RECOMMENDED POSITION: acceptable I

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58. j INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/8/96 PREPARED BY: John Stokley, P.E., Science Applications International Corporation ANO EVALUATION NUMBER : VSC SAR, and Fabrication Specification for the MTC EVALUATION TITLE: MTC Lifting Trunnions Changed to Solid Material DESCRIPTION: The-MTC trunnions have been changed from a hollow steel pipe with lead shielding and RX-277 grout to a solid steel <

trunnion. Additionally two more trunnions were added at 90 around the MTC from the original trunnions to permit suspending the MTC from the work platform. Finally the weld for the outer shell includes a backing ring on the ANO drawings.

REVIEW CONCLUSIONS: The changes to the trunnions have been evaluated as a part of the 10 CFR 72.48 process. Also the NRC inspector has prior to_the inspection reviewed the change details as a part of the Amendment 1 task, except the detail for the backing ring. The overall conclusion is that there are no unreviewed safety concerns RECOMMENDED POSITION: Accept the changes for the MTC lifting trunnions.

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. INSPECTION REPORT-ANO NUCLEAR POWER PLANT  !

5/9/96

$ PREPARED BY; John Stokley, P.E., Science Applications ,

International Corporation j ANO EVALUATION NUMBER: VSC SAR 4 EVALUATION TITLE: MSB Shield Lid Change from Two Piece Lid to i

One Piece Lid i l l 4

DESCRIPTION: The MSB shield lid as originally approved consisted i of two 2.5 inch thick steel plates sandwiching a 2 inch section of RX-277 neutron shielding and supported on a 2.5 inch steel i

support plate.The design change calls for the lid to be  !

manufactured as one component to facilitate assembly into the MSB

] shell. The modified lid has the same amount of shielding and the i

multi-piece unit.  !

! REVIEW CONCLUSIONS: This design change has been evaluated by ANO as a part of the 10 CFR 72.48 process. It has also been ,

! evaluated by the NRC inspector as a part of the Amendment 1 task.  !

l There are no outstanding safety concerns. The shielding is the

! same and the structural integrity is the same.  !

1 j RECOMMENDED POSITION: Accept the design modification.

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60.

INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/7/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO EVALUATION NUMBER: VSC SAR, and Fabrication Specifications for the MSB Rev./ Change No. SAR Rev. 0AA EVALUATION TITLE: Elimination of "Swagelock" Quick Disconnect from the MSB Drain Line DESCRIPTION: Eliminates a "Swagelock" Quick Disconnect from the MSB Drain Line. Substitutes use of a NPT plug at top of drain  ;

line for the valving function of the quick disconnect fitting. '

Does not change the fitting on the line used for pressurization, backfilling, and venting.

REVIEW CONCLUSIONS: The design change still permits acceptable draining, drying, backfilling, re drawdown, refilling, and pressurization operations associated with preparation of the cask for loading and unloading. There should be two drawdowns of the cask interior to $3 torr and backfill with inert gas following the drawdowns after the drain line has been sealed by the plug.

During preparation for unloading, the cask pressure should be drawn down to below atmospheric, and the cask should be maintained at lower than atmospheric pressure during removal of the plug and connection of the refilling system. With appropriate procedures, the change does not result in an unreviewed safety question.

RECOMMENDED POSITION: Acceptable. The change does not result in an unreviewed safety question.

32

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• INSPECTION REPORT-ANO NUCLEAR POWER PLANT  !

5/7/96 PREPARED BY: David Williamson, P.E., Science Applications

-International' Corporation ANO REVIEW Nm4BER: VSC SAR, and Fabrication Specifications for the  ;

MSB, MTC, and VCC

-REVIEW TITLE: Changes to VSC Document Relating to the Safety Classification of Components l

DESCRIPTION: This document makes changes to drawings and '

fabrication specifications by noting that certain items may be of  ;

l commercial grade. The safety classification for items are added to the MSB and MTC Fabrication Specification.

REVIEW CONCLUSIONS: The listed changes are consistent with past I

practice in allowing use of commercial grade items depending on the safety classification. The additional listing of safety classifications in the fabrication specifications provide information.

RECOMMENDED POSITION: Acceptable. The changes do not require a  !

72.48 evaluation.

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65.

INSPECTION REPORT-ANO-NUCLEAR POWER PLANT 5/9/96 PREPARED BY: David Williamson, P.E., Science Applications International Corporation ANO REVIEW NUMBElt: VSC SAR, and Fabrication Specifications for the MSB, MTC, and VCC REVIEW TITLE: Use of Carboline Top Coat', Carbozinc 11, and Keeler & Long Paint DESCRIPTION: Coatings are to be applien co the VSC components to minimize corrosion, to protect components from the pool chemistry, to protect the pool chemistry from the carbon steel components and for ease of decontamination following loading.

REVIEW CONCLUSIONS: The coatings meet the requirements stated in the SAR.

RECOMMENDED POSITION: Acceptable. The changes do not require a 72.48 evaluation.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/9/96 PREPARED BY: John Stokley, P.E. , Science Applications International Corporation ANO EVALUATION NUMBER: VSC SAR and Fabrication Specifications for the MSB i EVALUATION TITLE: Reduction in Height of the Shim Material for j the MSB Shield Lid Weld i 4

DESCRIPTION: The MSB is positioned in the shell by means of

. shims to be fitted after loading the fuel. These are installed i to achieve the best possible fit-up in order to maintain constant

weld settings for the seal weld. The length of the shim material t

is reduced by this modification. By reducing the length of the shim, the utility estimates that the fit up time will be reduced, thereby reducing exposure of welders.

] REVIEW CONCLUSIONS: This design change has been reviewed as a part of the 10 CFR 72.48 process. The inspector concurs that it does not raise an unreviewed safety issue since the shim was not 1

credited in the shielding analysis, and structurally there is no

. reduction in safety margin.

RECOMMENDED POSITION: Accept the design change.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT

]

5/7/96

PREPARED BY

David Williamson, P.E., Science Applications International Corporation ANO REVIEW NUMBER: DCP 92-2001 I.P. Rev 2 Change 0 REVIEW TITLE: High Level Waste Storage Project DESCRIPTION: This project involves the installation and relocation of water and instrument air lines in the spent fuel j area and installation of a service air line to the ISFSI pad.

i REVIEW CONCLUSIONS: This level of detail is below that included in the SAR and SER.

RECOMMENDED POSITION: Acceptable. The changes do not require a 1

72.48 evaluation.

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 5/8/96 4

1 i

PREPARED BY: David Williamson, P.E., Science Applications- j q International Corporation i ANO REVIEW NUMBER: Document No. DCP 92-2001, Rev./ Change No. DCPR i 7 1 i

4 REVIEW TITLE: High Level Waste Storage Project

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DESCRIPTION: This DCPR adds water lines in the spent fuel pool area, adds a service air line to the cask storage pad, moves a i

"al air line, and installs rtds on the first eight casks.

I VIEW CONCLUSIONS: This 3evel of detail is below that included l 1 in the SAR and SER.  :

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j RECOMMENDED POSITION: Acceptable. The changes do not require a l 72.48 evaluation. I I

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INSPECTION REPORT-ANO NUCLEAR POWER PLANT 1 i

5/9/96  :

PREPARED BY: David Williamson, P.E., Science Applications l International Corn ^ ration l ANO REVIEW NtmBER: Document No. PC 963036P101 Rev./ Change No. O i l

REVIEW TITLE: Dry Cask' Impact Inhibitor  !

DESCRIPTION: An impact limiting pad is installed on a load j resisting beam in the train bay to prevent a 50 foot cask drop i from penetrating the train bay floor or breaching an MSB.

REVIEW CONCLUSIONS: Calculation packages 92-D-2001-40 and -42 were cited but not reviewed by the NRC reviewer. According to I the information supplied in this PC 963036P101 document, these two calculation packages show that the impact limiter on the beam will keep forces on the MSB from exceeding 51 g's which is less than the 124 g design basis for the MSB.

RECOMMENDED POSITION: Accept subject to Fart 50 approval.

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