[en] Chinshan nuclear power station of Taiwan Power Company (TPC) will implement long term feed water hydrogen injection this year. For the purpose of effective hydrogen water chemistry (HWC), it is necessary and very important to compare plant data and observe the water chemistry change between before and after performing HWC. This paper contains the insoluble and soluble metal characterization, which is based on the recent data before HWC and includes the following working items: 1) The morphology and its compositions of insoluble iron named crud in the inlet of condensate demineralizer. 2) The trend of crud removal efficiency of condensate demineralizer. 3) The compositions of soluble and insoluble metals in the feed water and reactor water. 4) Crud composition prediction deposited on the fuel. Finally, the above results will be explained in detail with respect to the past operational experience as well as the plant-specific water chemistry condition. (author)

No abstract available

[en] In this study the parameter identification tool (PIT) for the loss-of-coolant accident (LOCA) of a BWR-4 plant with Mark-I containment, Chinshan nuclear power plant (NPP) in north Taiwan, is developed. The PIT is composed of the Simplex search algorithm and the MAAP5 code with the integration approach presented by Tsai et al. The LOCA is assumed to occur after station blackout sequence with the break elevation of 17 m and the break area of 2.1*10^-2 m². The break elevation of 16.93 m and the break area of 2.1*10^-2 m² are identified by the PIT with the imitated plant data, which are the RPV pressure and the shroud water level generated by MAAP5 code. With the identified parameters, the timing of events and source terms in the LOCA of Chinshan NPP can be predicted. It demonstrates that the PIT is helpful and important in severe accident management. (authors)

[en] This paper introduces the design evolution, system schemes and design and construction of main nuclear air cleaning components such as HEPA filter, charcoal adsorber and concrete housing etc. for Qinshan 300MW PWR Nuclear Power Plant (QNPP), the first indigenously designed and constructed nuclear power plant in China. The field test results and in-service test results, since the air cleaning systems were put into operation 18 months ago, are presented and evaluated. These results demonstrate that the design and construction of the air cleaning systems and equipment manufacturing for QNPP are successful and the American codes and standards invoked in design, construction and testing of nuclear air cleaning systems for QNPP are applicable in China. The paper explains that the leakage rate of concrete air cleaning housings can also be assured if sealing measures are taken properly and embedded parts are designed carefully in the penetration areas of the housing and that the uniformity of the airflow distribution upstream the HEPA filters can be achieved generally no matter how inlet and outlet ducts of air cleaning unit are arranged

[en] An anticipated transient without scram induced by main steam isolation valve closure (AMSIV) could subject a nuclear power plant to the most severe of accident conditions. The Chinshan plant analyzer contains a complete boiling water reactor system model and can be revised easily for the user's purpose. These features make the Chinshan plant analyzer suitable for AMSIV analysis. The capability of the Chinshan plant analyzer to analyze an AMSIV is illustrated. An AMSIV is simulated, and the simulation results are similar to the results of other research. Furthermore, the AMSIV response of reducing reactor power by decreasing reactor coolant inventory is simulated, and the results of the simulation are similar to those of other research. During this transient, the reactor power is decreased. However, the margin to core uncovery is also decreased. In addition, a method of reducing the reactor power by increasing the feedwater temperature is studied. The mechanism of reducing the reactor power is associated with decreasing the inlet subcooling. Sensitivities of key parameters are also analyzed. A large negative void coefficient causes in undesirable large peak in the reactor power. A small recirculation pump moment of inertia decreases the reactor power

[en] Leakage resulting from sensing line broken at the weldolet to the recirculating riser was found in Chinshan Nuclear Power Plant. A systematic failure root cause analysis, including fractographic examinations, vibration tests, stress analysis, and failure scenario reconstruction, was established. The root cause for this failure has been identified and effective corrective actions can be implemented. (author)

[en] High Pressure Coolant Injection (HPCI) system is the major safeguard of a GE BWR/4 Reactor. However, it doesn't have a specific injection nozzle on the Reactor. In order to inject coolant into the Reactor, it must use a connection on the FeedWater (FW) System. The FW system is a hot running system, but HPCI is a cold standby system. The connection of the two (2) systems with different fluid temperatures can cause trouble. NRC Information Notice No. 89-80 recognized this fact. Unfortunately, just like, the events described in NRC Notice No. 89-80, their Chin-Shan Nuclear Power Station (GE BWR/4) HPCI system had experienced several waterhammers during system Scheduled Surveillance testing and Cold Quick Start testing. The waterhammers had damaged several valves, some pipe supports and damaged some concrete surfaces near the support attachment points. The trigger of all issues are two (2) malfunctioning valves: injection valve (F006) and the test return valve (F008). Some practical measures are taken to alleviate the situation, and they have resulted in satisfactory success. This paper is going to review the how-and-why of the above issues. Suggestions for design rules are provided

No abstract available

[en] To apply fast and accurate simulation techniques to Taiwanese nuclear power plants, the Chinshan plant analyzer was developed based on the Brookhaven National Laboratory boiling water reactor (BWR) plant analyzer. The Chinshan plant analyzer provides user-friendly, on-line, interactive simulation capability with graphics display and is suitable for control system analysis. During the generator load rejection (GLR) test at the Chinshan BWR power station located in northern Taiwan, the reactor feedwater pump (RFP) tripped because of a high downcomer level (level 8). Feedwater control was then lost because of the RFP trip. By the end of the transient, a huge amount of water had accumulated in the reactor pressure vessel. The margin to main steamline flooding was decreased. An optimization module was developed and added to the Chinshan plant analyzer. With the optimized feedwater controller settings, the maximum downcomer level is below level 8, and RFP does not trip during the GLR transient. The margin to main steamline flooding is increased. These techniques will be applied for improving plant performance in the near future

[en] Taiwan Power Company operates three nuclear power stations and is currently in the process of building a fourth one. In 1989, TPC started surveys and evaluations of computer systems for nuclear power stations, and continuously performs this task once every two years. To match up with the fast pace of changes in technology, TPC has to upgrade the plant computer systems frequently to avoid equipment obsolescence. On the other hand, to save the investment and maximize the cost benefits, TPC has to appropriately use its limited resources. Therefore TPC developed an overall plan. The strategy proposed in this plan will continue to prove effective, both in existing station betterment projects and in new nuclear power station projects. TPC's challenge of implementing this strategy is subject now and will be subject in the future to the dynamic adjustments of the rapid technology changes. (author)