Results of Evaluation of Hamaoka Nuclear Power Station No. 4 Seismic Safety Margin Improvement Project
September 4, 2006
Chubu Electric Power Co., Inc.
As part of a voluntary project to improve the seismic safety margin at Hamaoka Nuclear Power Station, Chubu Electric Power is evaluating the complex against its target ground motion (i.e. sufficient to withstand 1,000 gal of horizontal ground motion at bedrock).
(This project was previously announced on January 28, 2005.)
Reactor No. 4 at the complex has now completed evaluation and is undergoing design and structural improvements, including the following: modifications to improve support for pipes and electric circuits, modification of fuel exchanger rail guides, modification of ceiling crane support components in reactor building, oil tank modification, improvement of foundations behind earth retaining walls and around pipes and ducts, and improvements in exhaust pipes.
(This project was previously announced on March 22, 2006.)
Presently, an evaluation has been performed on the seismic safety margin of the Reactor No. 4 facilities following completion of the project to improve this margin. The evaluation confirmed that the facilities critical to seismic resistance design, including those in which no modification was necessary, achieved the target seismic safety margin. This announcement provides an overview of the evaluation results.
More detailed evaluation results may be found in the Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Project Evaluation Report, available starting today at the Hamaoka Nuclear Exhibition Center (Omaezaki City, Shizuoka Prefecture) and the Electricity Museum (Nagoya City, Aichi Prefecture).
Attachment : Overview of Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Improvement Project Evaluation Results
Reference : Status of Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Improvement Project
*The Electricity Museum is closed today, September 4.
Attachment
Overview of Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Improvement Project Evaluation Results
As part of a voluntary project to improve the seismic safety margin at Hamaoka Nuclear Power Station, Reactor No. 4 at the complex has been undergoing design and structural improvements to facilities requiring modification, and portions of the project are now complete as of August 31, 2006. The evaluation confirmed that the facilities critical to seismic resistance design at Reactor No. 4 have achieved the target seismic safety margin. An overview of the evaluation results is provided herein. The evaluation results are summarized as follows.
1. Target ground motion and facilities subject to evaluation
The target ground motion for improving the seismic safety is about 1,000 gal (seismic tremors at bedrock) for horizontal ground motion and about 700 gal (seismic tremors at bedrock) for vertical ground motion. The table below shows the basis for setting the target ground motion.
| Seismic tremors at bedrock | Basis for setting target ground motion |
| Horizontal ground motion approx. 1,000 gal | This figure was found by considering the ground motion of a Tokai area earthquake as projected by the Central Disaster Prevention Council for the current standard ground motion, or S2, adding a margin at the short period and long period ends, and further adding another 30% margin overall. |
| Vertical ground motion approx. 700 gal | This figure was found by providing a margin to the multiplier 0.5, which is the vertical seismic activity ratio for the current standard ground motion, and making it two-thirds the horizontal ground motion. |
The evaluation targeted facilities critical to seismic resistance design. *1
The number of facilities subject to evaluation is shown in the table on the right.
| Category | Number of facilities subject to evaluation |
| Piping | Pipes at 6,461 places (support count) |
| Electric circuits | Electric circuits at 5,327 places (support count) |
| Equipment | 700 units |
| Buildings and structures outside buildings | 6 facilities |
*1: Facilities critical to seismic resistance design include the reactor itself and its peripheral piping, as well as equipment used to shut down or cool the reactor, equipment used to contain radioactivity, fuel equipment and power source and electric power equipment related to these.
2. Target ground motion evaluation procedures
The reactor building and its piping, electrical circuits and machinery underwent seismic response analysis at the target ground motion using an analysis model created to combine the local ground, reactor building and the reactor building's large equipment. Based on the acceleration and seismic force found in this analysis, engineers then evaluated the seismic safety margin through a process of evaluation with response magnification*2 and spectrum modal analysis*3. The seismic safety margin of exhaust pipes and other pipes and ducts outside the building was evaluated with seismic response analysis at the target ground motion.
During the seismic safety margin evaluation, for each component making up the facility (i.e. each component being evaluated), the calculated value (generated value) for the stress, etc. resulting from the target ground motion was confirmed to make sure it was within the standard value.
*2: Response magnification is a technique to calculate generated stress, etc. by taking the ratio of response acceleration from the original design and the response acceleration resulting from the target ground motion, and multiplying it by the stress from the original design.
*3: Spectrum modal analysis is a technique used on piping and equipment that have multiple support points and shake in complicated ways. The technique calculates generated stress, etc. by analyzing maximum response acceleration based on the pipe's or equipment's unique cycle, the response acceleration at this unique cycle, and so on.
3. Evaluation results for target ground motion
Engineers evaluated the seismic safety margin of the Reactor No. 4 facilities following completion of the project to improve this margin. The evaluation confirmed that these facilities critical to seismic resistance design, including those in which no modification was necessary, achieved the target seismic safety margin.
The following table provides examples of evaluation results for particularly critical facilities that were evaluated: those that stop, cool or contain the reactor.
| Facility | Component evaluated | Evaluation content (units) | Generated value | Standard value*4 |
| Reactor pressure vessel | Trunk panel | Stress (MPa) | 175 | 320 |
| Anchor bolts | Stress (MPa) | 165 | 499 | |
| Core support structure | Core support plate | Stress (MPa) | 67 | 427 |
| Shroud support | Stress (MPa) | 82 | 300 | |
| Containment vessel | Dry well | Stress (MPa) | 149 | 495 |
| Box support | Stress (MPa) | 320 | 343 | |
| Residual heat removal pump | Motor stand anchor bolts | Stress (MPa) | 31 | 444 |
| Main vapor piping | Piping | Stress (MPa) | 253 | 375 |
| Reactor building | Shear wall | Shearing strain*5 (--) | 1.04×10-3 | 2.0×10-3 |
| Control rods | Insertability *6 | Displacement (mm) |
16.6 *7 | 40 *8 |
These evaluation results have been summarized in the Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Improvement Project Evaluation Report. This report contains results of seismic response analysis at the target ground motion and seismic safety margin evaluation procedures and results (for representative facilities and about 130 points used as components evaluated).
*4: Standard values are criterion values used to confirm margins for target ground motion. The standard values used were ones stipulated by specifications or otherwise found to be suitable in tests, etc.
*5: The shearing strain value is evaluated for each floor of a building; the value used is the deformation of the top of the shear wall of each floor divided by the shear wall height.
*6: Insertability is the ability of control rods to insert within a standard time during emergency shutdown of a reactor. Specifically, it means that they can be inserted within 1.62 seconds so that 75% of the neutrons they are capable of absorbing will be absorbed.
*7: The value in the control rods' generated value space is the maximum value for fuel assembly relative displacement (i.e. the displacement between the upper and lower ends and the center).
*8: The value in the control rods' standard value space is the standard value found when confirming, during vibration testing, whether the control rods can be inserted within the standard time, even if there is relative displacement of 40mm in the fuel assembly.
Reference
Status of Hamaoka Nuclear Power Station Reactor No. 4 Seismic Safety Margin Improvement Project
As of August 31, 2006 at Reactor No. 4, work is complete on modifications to improve support for pipes and electric circuits and to improve the ground around pipes and ducts, and work is presently proceeding on modification of exhaust pipes. Additional work to be performed includes modification of fuel exchanger rail guides, modification of ceiling crane support components in reactor building, oil tank modification and improvement of the ground behind earth retaining walls. These improvements will be complete by the second half of FY2007. The included photographs indicate the status of areas now under construction and areas when construction is complete.
< Construction status list >
| Category | Construction item | Content | Status | Photo |
| Piping | Piping support modification | • Piping supports have been improved or newly installed. (194 points) | Begun March 23, 2006; finished June 28, 2006. | 1 2 |
| Electric circuits | Electric circuit support modification | • Electric circuit supports (cable trays at 647 points, power lines at 612 points) have been modified. (Total 1,259 points) | Begun March 23, 2006; finished June 19, 2006. | 3 4 5 |
| Equipment | Fuel exchange rail guide modification | • Fuel exchange rail guides will be modified. | They will be modified in succession beginning October 2006. | - |
| Modification of ceiling crane support components in reactor building | • Reactor building ceiling crane support components will be modified. | |||
| Buildings and structures outside buildings | Oil tank modification | • Oil tanks will be modified to lower oil level and connect two tanks by pipe so they can borrow oil from each other.
• Oil spill barriers that support pipes will be modified. |
||
| Improvement of the ground behind earth retaining walls | • The ground behind earth retaining walls near water collecting tanks will be improved. | |||
| Improvement of the ground around pipes and ducts | • Soil around pipes and ducts has been removed and replaced with concrete. | Begun December 21, 2005; finished March 29, 2006. | 6 | |
| Modification of exhaust pipes | • Steel towers will be installed so that existing exhaust pipes will be enclosed. | The work began April 12, 2006 and is currently proceeding. | 7 |







Explanation of photo and accompanying text in brackets [ ].• The text in brackets [ ] below the photo describes the [stress, etc. generated value / standard value: evaluated component]for the facility after modification. • For the photos of piping support, cable tray support and conduit support, the description is one of typical modification methods or a case where the generated value after modification is close to the standard value. • Photos for pipes and ducts and exhaust pipes show the construction status. The text in brackets [ ] describes a case where the generated value after modification is close to the standard value. |