ML021580366
| ML021580366 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Peach Bottom, Oyster Creek, Susquehanna, Maine Yankee, FitzPatrick, 07201004, 07201015, 07201027, 07201008, 07201021, Holtec, 07100018, 07100784 |
| Issue date: | 06/06/2002 |
| From: | Tokar M NRC/NMSS/SFPO |
| To: | Ronald Bellamy NRC/RGN-I/DNMS/DLB |
| References | |
| +sispjld120050505, -RFPFR | |
| Download: ML021580366 (6) | |
Text
June 6, 2002 MEMORANDUM TO:
Ronald Bellamy, Chief Decommissioning and Laboratory Branch Division of Nuclear Material Safety, Region I FROM:
Michael Tokar, Chief /RA/
Transportation and Storage Safety and Inspection Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
SUBJECT:
REGION I INDEPENDENT SPENT FUEL STORAGE INSTALLATION INTEGRATED INSPECTION PLANS Your memorandum dated May 9, 2002, provided a response to our joint memorandum from the Office of Nuclear Reactor Regulation (NRR) and the Spent Fuel Project Office (SFPO) dated February 20, 2002. Our memorandum requested that any revised or new integrated inspection plans (IIPs), as described in Nuclear Regulatory Commission (NRC) Inspection Manual Chapter (MC) 2690, be submitted for review and approval. Your memorandum provided the requested IIPs, for eight independent spent fuel storage installation (ISFSI) sites. You stated that a new IIP was developed for Haddam Neck and the previously submitted ISFSI IIPs had been updated. You noted that the IIPs contained details of inspections of ISFSI activities, including the scheduled activity dates and explained that the dates were subject to change.
SFPO approves the IIPs you submitted, subject to the incorporation of the comments provided in the attachment
Attachment:
SFPO Comments to Region I Integrated Inspection Plans cc w/att:
H. Gray, DRS R. Ragland, DNMS J. Wray, DNMS D. Coe, DIPM, NRR D. Norkin, DIPM, NRR
June 6, 2002 MEMORANDUM TO:
Ronald Bellamy, Chief Decommissioning and Laboratory Branch Division of Nuclear Material Safety, Region I FROM:
Michael Tokar, Chief (Original Signed by:)
Transportation and Storage Safety and Inspection Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
SUBJECT:
REGION I INDEPENDENT SPENT FUEL STORAGE INSTALLATION INTEGRATED INSPECTION PLANS Your memorandum dated May 9, 2002, provided a response to our joint memorandum from the Office of Nuclear Reactor Regulation (NRR) and the Spent Fuel Project Office (SFPO) dated February 20, 2002. Our memorandum requested that any revised or new integrated inspection plans (IIPs), as described in Nuclear Regulatory Commission (NRC) Inspection Manual Chapter (MC) 2690, be submitted for review and approval. Your memorandum provided the requested IIPs, for eight independent spent fuel storage installation (ISFSI) sites. You stated that a new IIP was developed for Haddam Neck and the previously submitted ISFSI IIPs had been updated. You noted that the IIPs contained details of inspections of ISFSI activities, including the scheduled activity dates and explained that the dates were subject to change.
SFPO approves the IIPs you submitted, subject to the incorporation of the comments provided in the attachment
Attachment:
SFPO Comments to Region I Integrated Inspection Plans cc w/att:
H. Gray, DRS R. Ragland, DNMS J. Wray, DNMS D. Coe, DIPM, NRR D. Norkin, DIPM, NRR DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML021580366.wpd DISTRIBUTION:
PUBLIC NRC File Center SFPO r/f NMSS r/f To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE SFPO E SFPO E
SFPO E
NAME PNarbut E Ziegler M Tokar DATE 6 /4 /02 6/ 5 /02 6/ 6 /02 OFFICIAL RECORD COPY ADAMS: ML021580366
ATTACHMENT SFPO Comments to Region I Integrated Inspection Plans Please add the following modifications and additions to the indicated integrated inspection plans:
1.
HADDAM NECK (CY) SITE ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 1, Section E, first bullet to state:
Design and fabrication of components Complete Observation of TSC and VCC fabrication Complete The design inspections of NAC were performed by SFPO in June 1998 (IR 71-0018/98-207) and in May 2001 (IR 72-1015/01-201). NAC fabrication oversight controls were assessed during an inspection of component fabrication activities at Ionics, Incorporated, in March 2001 (IR 72-30/01-201). Control of the design and fabrication activities was adequate.
2.
CALVERT CLIFFS ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 2, Section E, second paragraph bullet to state:
.......When Calvert Cliffs was going through licensing of an ISFSI, NRCs programs were still under development. and poor recording keeping standards were in place.
Modify Attachment 2, Section E, first paragraph following the first bullet to state:
Reconstitution of the design, fabrication, NDE, and Quality Assurance inspections for the NUHOMS-24P could not be reconstituted, it is assumed that it was performed by SFPO.
The design inspections of the NUHOMS casks (Pacific Nuclear Fuel Services, then Vectra Technologies, then Transnuclear West, and now Transnuclear Incorporated) were performed by SFPO starting in 1993, and documented in inspection reports IR 72-1004/93-07,95-203, 96-207,97-209, 98-208,98-209, 98-211, and 00-201. Fabrication inspections were performed by SFPO at Vectras fabricators and documented in inspection reports IR 72-1004/93-07,95-202, 96-201,96-211, 98-210,99-201, 99-202,00-201, and 72-1004/01-201. A 10CFR 72.48 design change inspection was performed by SFPO at Calvert Cliffs and documented in inspection report 72-0008/99-201.
Design and fabrication control issues were identified and satisfactorily resolved.
Region Inspectors conducted reviews of activities regarding the cask storage pad construction (IR 50-317/91-25). A review was conducted by RI concerning the resolution of design issues associated with the NUHOMS Dry Cask Storage System (IR 50-317/98-01).
3.
FITZPATRICK NUCLEAR PLANT ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 3, Section E, first bullet and its following paragraph to state:
Initial Observations of MPC fabrication at US T&D Done Design inspections of Holtec were performed by SFPO in December 1997 (IR 71-0784/97-216), September 2001 (IR 72-1014/01-201) and a follow up inspection in May 2002 (IR 72-1014/02-202). Holtec fabrication oversight controls were assessed by SFPO at US Tool and Die in June 1999 (IR 72-1008/99-201) and February 2002 (IR 72-1014/02-201). Region I inspectors examined the fabrication of components for Hatch and FitzPatrick respectively in March 2001. Region I inspectors also conducted reviews of activities regarding the cask storage pad (IR 05000333/2000-004) and Reactor Building Crane (RBC) (IR 05000333/2000-013).
4.
MAINE YANKEE SITE ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 4, Section E, first paragraph following the first bullet to state:
The design inspections of NAC were performed by SFPO in June 1998 (IR 71-0018/98-207) and in May 2001 (IR 72-1015/01-201). NAC fabrication oversight controls were assessed during an inspection of component fabrication activities at Ionics, Incorporated, in March 2001 (IR 72-30/01-201). Control of the design and fabrication activities was adequate.
5.
OYSTER CREEK SITE ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 5, Section E, first paragraph following the first bullet to state:
The design inspections of the NUHOMS casks (Pacific Nuclear Fuel Services, then Vectra Technologies, then Transnuclear West, and now Transnuclear Incorporated) were performed by SFPO starting in 1993, and documented in inspection reports IR 72-1004/93-07,95-203, 96-207,97-209, 98-208,98-209, 98-211, and 00-201. Fabrication inspections were performed by SFPO at Vectras fabricators and were reported in inspection reports IR 72-1004/93-07,95-202, 96-201,96-211, 98-210,99-201, 99-202,00-201, and 72-1004/01-201. Design and fabrication control issues were identified and satisfactorily resolved. While not all fabrication vendors involved in Oyster Creek products were inspected, the Transnuclear quality assurance program fabrication and design controls were applicable to these activities and were adequate.
- 6.
PEACH BOTTOM ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 6, Section E, first paragraph following the first bullet to state:
SFPO performed an inspection of design controls at Transnuclear, NY, in May 1997 (IR 72-1021/97-206) and plans a followup inspection in July 2002. SFPO performed a fabrication, NDE, and quality assurance inspection for the TN-68 spent fuel storage casks at Precision Components Corporation in February 1999 (IR 72-1027/99-201).
Regional inspections were performed in November/December 1999 (IR 72-1027/05000277/1999009). Inspectors conducted reviews of activities regarding the
cask storage pad construction, pad preparations, and concrete pours (IR 50-277/98-07,50-277/98-08,50-277/98-10, 50-277/98-11, 50-277/99-02). Additionally, inspectors verified the licensee evaluated safety related and important to safety underground systems along the route that the Spent fuel transporter will travel from the power block to the ISFSI (50-277/99-06).
7.
SUSQUEHANNA ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 7, Section E, first paragraph following the first bullet to state:
The design inspections of the NUHOMS casks (Pacific Nuclear Fuel Services, then Vectra Technologies, then Transnuclear West, and now Transnuclear Incorporated) were performed by SFPO starting in 1993, and documented in inspection reports IR 72-1004/93-07,95-203, 96-207,97-209, 98-208,98-209, 98-211, and 00-201. Fabrication inspections were performed by SFPO at Vectras fabricators and were documented in inspection reports IR 72-1004/93-07,95-202, 96-201,96-211, 98-210,99-201, 99-202,00-201, and 72-1004/01-201. Design and fabrication control issues were identified and satisfactorily resolved.
Regional Inspectors conducted reviews of activities regarding the cask storage pad construction, pad preparations, and concrete pours (IRs IR 50-387/99-09 and 50-387/96-09).
8.
YANKEE ROWE SITE ISFSI INTEGRATED INSPECTION PLAN Modify Attachment 8, Section E, first paragraph following the first bullet to state:
The design inspections of NAC were performed by SFPO in June 1998 (IR 71-0018/98-207) and in May 2001 (IR 72-1015/01-201). NAC fabrication oversight controls were assessed during an inspection of component fabrication activities at Ionics, Incorporated, in March 2001 (IR 72-30/01-201). Control of the design and fabrication activities was adequate. While not all fabrication vendors involved in Yankee Rowe products were inspected, the NAC quality assurance program fabrication and design controls were applicable to these activities and were adequate.
Because of the adequate NAC oversight, inspection of Yankee Rowe components at Hitachi and Nooder were not considered to be necessary. The observation of fabrication of VCC at Nooder, Inc. is optional. TSC and VCC components inspection when received onsite after receipt and take approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.