ML043370318
| ML043370318 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, 07200011 |
| Issue date: | 12/01/2004 |
| From: | Spitzberg D Division of Nuclear Materials Safety IV |
| To: | Shetler J Sacramento Municipal Utility District (SMUD) |
| References | |
| +sispmjr200506 IR-04-004 | |
| Download: ML043370318 (9) | |
See also: IR 05000312/2004004
Text
December 1, 2004
Mr. James Shetler, Assistant General Manager
Energy Supply
Sacramento Municipal Utility District
6201 'S' Street
P.O. Box 15830
Sacramento, California 95852
SUBJECT: NRC INSPECTION REPORT 050-00312/04-004; 072-00011/04-004
Dear Mr. Shetler:
This report refers to NRC inspections conducted on October 5-6, 12, and 27-28, 2004, at your
Rancho Seco Nuclear Generating Station. On November 3, 2004, a telephonic exit briefing
was conducted with Mr. Steve Redeker, Manager, Plant Closure and Decommissioning.
The inspections included the heavy lifts of the B steam generator upper section, the collection
of soil samples from beneath the spent fuel pool floor, and a review of the analysis for
accidental explosion or rapid burning of natural gas at the Cosumnes Power Plant. The
enclosed report presents the scope and results of the inspections. No violations of NRC
requirements were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response (if any) will be made available electronically for public inspection
in the NRC Public Document Room or from the Publicly Available Records (PARS) component
of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please note that on October 25, 2004, the NRC suspended public access to ADAMS, and
initiated an additional security review of publicly available documents to ensure that potentially
sensitive information is removed from the ADAMS database accessible through the NRC's web
site. Interested members of the public may obtain copies of the referenced documents for
review and/or copying by contacting the Public Document Room pending resumption of public
access to ADAMS. The NRC Public Document Room is located at NRC Headquarters in
Rockville, MD, and can be contacted at 800-397-4209 or 301-415-4737 or pdr@nrc.gov.
Should you have any questions concerning this inspection, please contact Scott Atwater at
(817) 860-8286 or the undersigned at (817) 860-8191.
Sincerely,
/R.J. EVANS FOR RA/
D. Blair Spitzberg, Ph.D., Chief
Fuel Cycle and Decommissioning Branch
Sacramento Municipal Utility District -2-
Docket Nos.: 050-00312; 072-00011
License Nos.: DPR-54; SNM-2510
Enclosure:
NRC Inspection Report
050-00312/04-004; 072-00011/04-004
cc w/enclosure:
Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, N.W.
Washington, D.C. 20037
Jerry Delezenski, Superintendent
Quality and Compliance
Sacramento Municipal Utility District
Rancho Seco Nuclear Generating Station
14440 Twin Cities Road
Herald, California 95638-9799
Sacramento County
Board of Supervisors
700 H. Street, Suite 2450
Sacramento, California 95814
Dana Appling, General Counsel
Sacramento Municipal Utility District
6201 S Street
P.O. Box 15830
Sacramento, California 95813
Ed Bailey, Radiation Program Director
California Radiologic Health Branch
State Department of Health Services
P.O. Box 997414 (MS 7610)
Sacramento, California 95899-7414
Cindy Buchanan, Site Document
Control Supervisor
Rancho Seco Nuclear Generating Station
14440 Twin Cities Road
Herald, California 95638-9799
James D. Boyd, Commissioner
California Energy Commission
1516 Ninth Street (MS 34)
Sacramento, California 95814
Sacramento Municipal Utility District -3-
bcc w/enclosure (via ADAMS distrib):
EECollins
JBHickman, NRR/DLPM/PDIV-2
ACMcMurtray, NRR/DSSA/SPLB
DBSpitzberg
EMGarcia
SPAtwater
KEGardin
FCDB File
ADAMS: :Yes 9No Initials: SPA
- Publicly Available 9Non-Publicly Available 9Sensitive :Non-Sensitive
DOCUMENT NAME: s:\dnms\fcdb\spa\rs04-04.wpd final r:\_dnms
RIV:DNMS:FCDB RIV:DNMS:FCDB C:FCDB
EMGarcia SPAtwater DBSpitzberg
/S.ATWATER FOR RA/ /RA/ /R.EVANS FOR RA/
11/29/04 11/29/04 12/01/04
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
ENCLOSURE
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.: 050-00312; 072-00011
License Nos.: DPR-54; SNM-2510
Report No.: 050-00312/04-004; 072-00011/04-004
Licensee: Sacramento Municipal Utility District
Facility: Rancho Seco Nuclear Generating Station
Location: 14440 Twin Cities Road
Herald, California 95638
Dates: October 5-6, 12, 27-28, and November 3, 2004
Inspectors: Emilio M. Garcia, Health Physicist
Scott P. Atwater, Health Physicist
Approved By: D. Blair Spitzberg, Ph.D., Chief
Fuel Cycle and Decommissioning Branch
Attachment: Supplemental Information
ADAMS Entry : IR 05000312-04-004; 072-00011/04-004 on 10/05/04 -11/03/04;
Sacramento Municipal Utility District; Rancho Seco Nuclear
Generating Station; Decommissioning Report; No Violations.
-2-
EXECUTIVE SUMMARY
Rancho Seco Nuclear Generating Station
NRC Inspection Report 050-00312/04-004; 072-00011/04-004
During these inspections, the inspectors observed movement of the B steam generator upper
section from its D-Ring enclosure to the transfer trailer and sampling of the soil beneath the
spent fuel pool floor. The inspectors also reviewed the analysis for accidental explosion or
rapid burning of natural gas at the Cosumnes Power Plant and its effect on the Rancho Seco
Independent Spent Fuel Storage Installation (ISFSI).
Decommissioning Performance and Status Review
- The crane and rigging capacities, lifting heights, load travel paths, procedural controls,
and personnel safety measures were appropriate for the segmented steam generator
heavy lift evolutions. The work observed was being conducted in a safe and orderly
manner consistent with generally accepted industrial rigging and crane practices
(Section 1.2.a).
- The site characterization samples of the soil beneath the spent fuel pool floor were
collected in accordance with site procedures, and sample integrity was maintained at all
times. Preliminary results from the licensee gamma spectroscopy analysis indicated no
radioactivity levels above background. A follow-up letter will be sent to the licensee
once the sample results are received from the Oak Ridge Institute for Science and
Education and are reviewed by the NRC (Section 1.2.b).
Operation of an ISFSI
- The inspectors concurred with the licensees conclusion that the impact on the Rancho
Seco ISFSI from an explosion or rapid burning of natural gas at the Consumnes Power
Plant or Gas Metering Station was bounded by the ISFSI design for tornado and flood
events (Section 2.2).
-3-
Report Details
Summary of Facility Status
The Rancho Seco facility was undergoing active decommissioning with dismantlement work in
progress in the auxiliary, reactor and spent fuel buildings and outdoor areas. The licensee had
removed all 493 spent fuel assemblies from the spent fuel pool. Twenty-one canisters had
been loaded with spent fuel and transferred to the Independent Spent Fuel Storage Installation
(ISFSI). Most major components in the auxiliary building have been removed, packaged and
shipped for disposal. In the reactor building, most of the major piping, the four reactor coolant
pumps, the core flood tanks, the reactor vessel head, and the pressurizer had been removed,
packaged and disposed. The B steam generator had been segmented into upper and lower
sections. Two 24-inch lifting trunnions had been welded to the sides of the steam generator
shell for lifting. In the fuel handling building, most of the spent fuel pool liner had been removed
and released offsite. Borings had been made through the floor of the spent fuel pool for site
characterization sampling of the soil below the pool floor.
1 Decommissioning Performance and Status Review (71801)
1.1 Inspection Scope
The licensee was segmenting the two steam generators into upper and lower sections,
and removing the four resultant sections from the reactor building. Each section was a
heavy load weighing approximately 300 tons. This inspection focused on crane and
rigging capacities, lifting heights, load travel paths, procedural controls, and personnel
safety measures.
The licensee was obtaining site characterization samples of the soil beneath the spent
fuel pool floor. This inspection focused on the sampling methodology, integrity of
samples and preliminary sample results.
1.2 Observations and Findings
a. Movement of the B Steam Generator Upper Section
Both steam generators were to be segmented into upper and lower sections. Each of
the four resultant sections were to be removed from the reactor building, loaded onto a
special rail car assembly and shipped to a disposal site. The licensee had obtained U.S.
Department of Transportation Exemption, DOT-E 13338, which authorized the four
steam generator sections, classified as surface contaminated objects class II (SCO-II),
to be transported from the Rancho Seco station to a low level radioactive waste disposal
site in Clive, Utah without specification packaging. The steam generator shells serve as
the non-specification transportation packages and unique placarding was required. All
four steam generator sections were to be shipped by exclusive use rail freight.
The licensee had contracted with Bigge Power Constructors to remove the four steam
generator sections from the reactor building and load them onto special rail car
assemblies. Each steam generator section weighed approximately 300 tons and the
-4-
reactor building polar crane girders, rails, and rail supports had a rated capacity of
700 tons. However, the crane trolley did not provide the required capacity nor lifting
height, so it was not used. Instead, two steel towers were erected on top of the crane
girders to provide the needed capacity and lifting height. The towers, link chains and
lifting yoke had a rated capacity of 500 tons and the load was raised and lowered
hydraulically.
The B steam generator upper section heavy lifts were conducted in accordance with
Bigge drawing titled Rigging Arrangement - Upper Shell Steam Generator Removal
Project, dated September 3, 2004, and with Bigge drawing titled General Arrangement
- Upper Shell Removal, dated September 9, 2004. These two drawings provided the
building and equipment arrangement, removal sequence, rigging, lift heights and travel
paths. During the site visit of October 5-6, 2004, these drawings were reviewed for
clarity and function. Since a load drop would not impact any spent fuel or safe
shutdown equipment, NUREG-0612, Control of Heavy Loads at Nuclear Power Plants,
did not apply to these lifts. However, the BIGGE crane and rigging practices were
consistent with the NUREG-0612 guidelines in terms of handling system design, load
handling instructions and safe load paths.
During the site visit of October 12, 2004, a 110-percent load test was performed on the
crane and rigging. Just prior to the final cut on the B steam generator shell, the lifting
yoke was attached to the trunnions and 4700 psi of hydraulic pressure, the equivalent of
a 330 ton load, was applied to the towers and lifting chains. The hydraulic pressure was
then reduced to 4300 psi, the equivalent of 300 tons, and the final shell cuts were made.
The upper section of the steam generator was then lifted slightly and a diaper was
installed under the shell to catch any loose debris. The B steam generator upper
section was then lifted over the D-Ring wall to near the center of the reactor building.
On October 13, 2004, the polar crane was rotated into alignment with the equipment
hatch. The B steam generator upper section was then moved to the east and lowered
onto a closure lid in front of the equipment hatch. From October 14-27, 2004, the
closure lid was welded onto the open end of the steam generator section and a
polymeric coating was applied to the exterior to encapsulate any remaining removable
contamination.
During the site visit of October 27-28, 2004, the B steam generator upper section and
welded closure lid were downended and loaded onto the Bigge 10 axle trailer.
Preparations were begun for moving it out of the reactor building and onto a special rail
car assembly for shipment to the disposal site.
The BIGGE craft supervisor directed all load movements through his lead rigger who
executed the heavy lifts via radio contact with the crane operators on top of the crane.
The evolution was performed at a methodical pace and in accordance with the BIGGE
drawings. All personnel stayed clear of the load whenever it was suspended.
-5-
b. Characterization Sampling of Soil Beneath the Spent Fuel Pool
During the site visit of October 27-28, 2004, site characterization sampling of the soil
beneath the spent fuel pool floor was observed. The sampling operation was performed
in accordance with Spent Fuel Pool Subsurface Soil Sampling General Instructions,
dated September 27, 2004, and with Survey Sample Instruction Package
- SB8120070, Rev. 0.
Thirteen of the fifteen planned borings through the concrete in the spent fuel pool floor
had been completed. In each hole, split spoon samples were to be taken at one meter
increments down to a depth of 7 meters below the surface of the spent fuel pool floor.
With this method, the samples were to be collected from the same ground stratum
regardless of variations in spent fuel pool floor thickness. At the time of the inspection,
three holes had been fully sampled and sampling was started in the fourth hole. The
split spoon was approximately 3 inches in diameter, 1 meter in length and was driven
into the earth using a pile driver. As it was extracted from the hole, the exterior was
cleaned and the spoon was placed into a clean polyethylene bag labeled with sample
date, time, and location. The sample spoon was then carried to the preparation area
where it was opened. The center of the sample was collected into two scintillation vials,
one for a split with the NRC. Care was taken to minimize the samples exposure to air.
The remainder of the bulk sample was sifted for rocks and collected into a clean
container. A portion of the bulk sample was then transferred into a marinelli beaker for
a gamma spectroscopy analysis by the licensee. Another portion of the bulk sample
was transferred into a polyethylene container for a split with the NRC. Using this
process, soil samples from the first four borings were split with the NRC. All four
samples were extracted from the first meter of soil below the spent fuel pool floor.
Preliminary analysis results from the licensees gamma spectroscopy analysis indicated
no radioactivity levels above background. The NRC portion of the split samples were
sent to the Oak Ridge Institute for Science and Education (ORISE). ORISE will analyze
the four scintillation vial samples for volatile components such as carbon-14 and tritium
and the four bulk samples for a gamma spectrum. A follow-up letter will be sent to the
licensee once the ORISE results are received and reviewed by the NRC.
1.3 Conclusions
The crane and rigging capacities, lifting heights, load travel paths, procedural controls,
and personnel safety measures were appropriate for the segmented steam generator
heavy lift evolutions. The work observed was being conducted in a safe and orderly
manner consistent with generally accepted industrial rigging and crane practices.
The site characterization samples of the soil beneath the spent fuel pool floor were
collected in accordance with site procedures, and sample integrity was maintained at all
times. Preliminary results from the licensee gamma spectroscopy analysis indicated no
radioactivity levels above background. A follow-up letter will be sent to the licensee
once the sample results are received from ORISE and are reviewed by the NRC.
-6-
2 Operation of an ISFSI (60855)
2.1 Inspection Scope
The inspectors reviewed the Rancho Seco Quality Surveillance Report 04-S-025 which
contained the analysis of an accidental explosion or rapid burning of natural gas at the
Consumnes Power Plant or Gas Metering Station.
2.2 Observations and Findings
The analysis was performed by a licensee contractor. It evaluated a worst case
accidental explosion or rapid burning of natural gas at the new Cosumnes Power Plant
or Gas Metering Station for potential impact on the existing ISFSI. The inspectors
reviewed the analysis and found it to be comprehensive. The analysis concluded that
the impact on the Rancho Seco ISFSI from this event was less severe than the tornado
and flood events for which the ISFSI was designed.
2.3 Conclusions
The inspectors concurred with the licensees conclusion that the impact on the Rancho
Seco ISFSI from an explosion or rapid burning of natural gas at the Consumnes Power
Plant or Gas Metering Station was bounded by the ISFSI design for tornado and flood
events.
3 Exit Meeting Summary
A telephonic exit interview was conducted with Mr. Steve Redeker, Plant Manager, on
November 3, 2004. The general scope and results of these inspections were discussed.
The licensee did not identify as proprietary any information provided to or reviewed by
the inspectors.
ATTACHMENT
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Sacramento Municipal Utility District
D. Brown, ALARA Engineer
R. Burrell, Senior Decommissioning Technician
D. Clark, Senior Mechanical Engineer
J. Delezenski, Quality Assurance/Licensing/Administration/Training Superintendent
P. Melendy, Radiation Protection Technician
S. Porterfield, Supervisor Radiation Engineering Specialist
E. Ronningen, Principal Decommissioning Radiological Engineer
D. Russell, Rad Waste Handler
S. Redeker, Manager, Plant Closure and Decommissioning
J. Witte, Principal Mechanical Engineer
Bigge Power Constructors
T. Garcia, Craft Supervisor
INSPECTION PROCEDURES USED
IP 60855 Operation of an ISFSI
IP 71801 Decommissioning Performance and Status Review
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None
LIST OF ACRONYMS
ISFSI Independent Spent Fuel Storage Installation
ORISE Oak Ridge Institute for Science and Education