ML20216H551
| ML20216H551 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/28/1997 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2457, NUDOCS 9804210188 | |
| Download: ML20216H551 (11) | |
Text
{{#Wiki_filter:. GNTERDOR t ENERGY l l l l 6501 N State Flouk 2 419-24 4 2300 John K. Wood Oak Hartor.oH 43449 FAX: 419-3218337 Vice Presidert. Nucht Davis-Besse l l 5 l Docket Number 50-346 License Number NPF-3 Serial Number 2457 May 28, 1997 l United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
Subject:
Additional Information for an Exemption from 10CFR70.24(a), " Criticality Accident Requirements" i Ladies and Gentlemen: ) By letter (Serial Number 2440) dated January 30, 1997, Toledo Edison (TE) submitted a request for an exemption from the requirements of 10CFR70.24 (a), " Criticality Accident Requirements," for the Davis-Besse Nuclear Power Station (DBNPS), Unit 1. On February 26, 1997, the NRC Staff OL* ally requested additional information with regards to this exemption request. The requested information is contained in the enclosure to this letter. Toledo Edison requests that the NR7 apptove this exemption request by August 29, 1997. p should you have any questions or require additional informacion, please contact l Mr. James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466. Very truly yours, l h?! 3i D W/laj j enclosure ) j cc: A. B,. Beac;1, Regional Administrator, MRC Region III iA?!G..Ha*.tsen, DB-1fNRC/NRR Project Manatgere co S. 4.asek, DB-1 NRC Senior Resident Inspactor UtL11ty Radiological Safety Board j l 4 i,,i. + j '- 4904210189 970328 PDR ADOCK 05000346 g I F PDR 1 i l m j
Dockst Number 50-346 Licznze Number NPF-3 83 rial Number 2457 Enclosure Page 1 Davis-Besse Nuclear Power Station Request for Exemption from 10CFR70.24(a) " Criticality Accident Requirements" f Resnonse to N2C Reauest for Additional Information By letter (Serial Number 2440) dated January 30, 1997, Toledo Edison (TE) 1 submitted a request for an exemption from the requirements of 10CFR70. 24 (a), " Criticality Accident Requirements," for the Davis-Besse Nuclear Power Station (DBNPS), Unit 1. On February 26, 1997, the NRC Staff orally requested additional information with regards to the exemption request. Below are the NRC Staff's requests and TE's responses. NRC Reauest No. It Describe the procedural controls and/or physical constraints imposed for precluding inadvertent criticality of frash fuel during fuel handling, l inspection, and movement prior to storage in the fresh fuel racks. TE Response Following arrival onsite of a tractor-trailer carrying new fuel assemblies, the shipping containers are receipt-inspected by TE for any damage, or radioactive contamination or leakage. The shipment is confirmed as correct and complete, the containers' flange seals are confirmed as intact, and the containers' accelerometer indications are confirmed as acceptable. Under the direction of a TE Reactor Engineer, the fuel assembly shipping containers are removed from the shipping vehicles into the Auxiliary Building's Fuel Handling Area (see enclosed USAR Figures 1.2-4 and 1.2-5). New fuel handling is performed by using TE-approved fuel handling i procedures. New, unirradiated nuclear fuel assemblies are inspected, unloaded and stored in accordance with DBNPS procedure DB-NE-06102, "New o Fuel Receipt Inspection and Storage," under the direction of a TE Reactor ) i Engineer. The Reactor Engineer must be present for all new fuel movements l in accordance with DB-NE-06102. This procedure requires that a new fuel j [- assembly not be left unattended in an open container, or left in a position i l outside a normal storage location. New fuel assemblies are in their shipping containers on only a temporary, interim basis following unloading from the tractor-trailer shipping vehicle. The design of the shipping containers is such that a critical array cannot be established. l Only one shipping container is opened at a time. As a prerequisite to removal of the fuel assemblion from the shipping containers, a fuel asnembly Movement verification Sheet is also required to have been completed by a Reactor Engineer, and independently reviewed by another Reactor Engineer, to direct where each aosembly is to be stored in the New Fuel Storage Area.
Dockst Number 50-346
- Lictnno Number NPF-3 Serial Number 2457 l
Enclosure Pa,ge 2 I only one new fuel assembly is removed from its shipping container at a time I to the New Puel Storage Area. The movement is physically limited to only I one fuel assc,im'.y at a time because there is only one overhead crane in the Fuel Handling Area. The fuel assembly is handled by the overhead Spent f Fuel Cask Crane (see enclosed USAR Figure 1.2-6). Prior to placing new fuel assemblies into the New Fuel Storage Area, DBNPS procedure DBANE-00100, " Fuel Handling Administration," requires that an engineering criticality analysis calculation has been completed which confirms the storage of the new fuel will comply with the New Fuel Storage Area Criticality Analysis. The appropriate covers of the New Fuel Storage Area are opened and the 1 crane transfers the fuel assembly to its pre-designated storage location in accordance with the Movement verification Sheet. Due to the most recent criticality analysis, Rows C and F of the New Fuel Storage Area racks are not utilized and are marked as such through the use of placards. The prop,er storage locations of the new fuel assemblies are also confirmed through the preparation and review of Inventory Control Area maps by Reactor Engineers in accordance with DB-NE-00100. NRC Recuest No. 2: What are the possible sources of water during new fuel handling operations? How are these sources controlled during the handling of new fuel? TE Resnonse New fuel handling operations are performed in the Fuel Handling Area and New Fuel Storage Area as shown on enclosed USAR Figures 1.2-4 and 1.2-5. There are several sources of water in these areas. For example, the Cask Wash Area, which is located south of the New Fuel Storage Area, has connections for both Domestic Water and Demineralized Water. However, it would be required to hook up hoses to che water connections in order to move the water up into the Fuel Handling Area. There is no reason to be i using hoses and water in the cask Wash Area during new fuel handling 1 activities. There is no automatic fire suppression equipment, such as sprinklers, in the New Fuel Handling or New Fuel Storage Areas. Fire protection hose stations, which use fog nozzles, are located in the vicinity of the Fuel Handling Area. However, the associated valves are closed. Toledo Edison controls the movement and location of new fuel assemblies in a manner that limits the consequences of the introduction of water into these areas. For example, only one new fuel assembly is removed from its shippin7 container at a time. Per DB-NE-06102, a fuel assembly is not to ba '. aft unattended in an open container or left in a position outside a normal storage location. These actions limit any potential exposure to ( water. Furthermore, as described earlier, a Reactor Engineer is present during new fuel movements and provides oversight from the perspective of fuel assembly nuclear safety.
l Docket Number 50-346 l . Licanza Numbar NPF-3 Sarini Number 2457 Enclosure Page 3 NEg,Recuest No. 3; Verify that, with the requested exemption, radiation monitoring remains available to meet the requirements of 10 CFR 50, Appendix A, "Ganeral Design Criterion 63 - Monitoring Fuel and Waste Storage," for fuel storage i f,; areas. Also, include a discussion of the training provided to personnel in responding to area radiation monitor alarms. l TE Resoonset Area Radiation Monitors General Design Criterion (GDC) 63 states: l Appropriate systems shall be provided in fuel storage and radio-active waste systems and associated handling areas (1) to detect conditions that may result in loss of residual heat removal i capability and excessive radiation levels and (2) to initiate appropriate safety actions. The DBNPS was designed, constructed and issued an NRC Operating License without criticality accident alarming monitors in the new Luel storage area or the spent fuel pool storage area. The DBNPS Updated Safety Analysis q Report (USAR) discusses the extent of committed compliance to GDC 63 in Chapter 3, Appendix 3D, Subsection 3D.1.54, " Criterion 63 - Monitoring Fuel and Waste Storage." This subsection identifies that the fuel handling and storage areas are monitored for reactivity releases by area radiation monitors located in the new fuel receiving area (Fuel Handling Area) and the New Fuel Storage Area. Section 12.1.4, " Area Monitoring," of the USAR describes the area radiation monitors installed at the DBNPS. The area radiation monitors provide a continuous indication of gamma-emitting radioactivity in selected plant areas and alarm on high radiation. The Fuel Handling Area has two area radiation monito{s reg 417 andre 8418. Both of these monitors have a detection range of 10 to 10 mrem /hr. These monitors use Geiger-Mueller type detectors. A local indicating and alarm unit is mounted near the detector, which contains a logarithmic counting ratemeter, and a visual and audible alarm. These monitors also provide a visual alarm in the Control Room. Electrical power is provided by uninterruptible instrument distribution panels in order to maintain a regulated and reliable power supply. The Spent Fuel Storage Area also has two area radiation monitors: RE842g and RE8427. Both of these monitors have a detection range of 10 to 10 mrem /hr. These monitors use ionization chamber type detectors. A local indicating and alarm unit is mounted near the detector, which contains a logarithmic counting ratemeter, and a visual and audible alarm. These monitors also provide a visual alarm in the Control Room. Electrical power is provided by uninterruptible instrument distribution panels in order to maintain a regulated and reliable power supply.
l Docket Number 50-346 l License Number NPF-3 Serial Number 2457 Enclosure i Page 4 i Area radiation monitor alarms received at or reported to the Control Room are responded to in accordance with DBNPS procedures DB-OP-02009, " Plant Services Alarm Panel 9 Annunciators," DB-OP-06412, " Process and Area Radiation Monitor," and, as applicable, RA-EP-02861, " Radiological Incidents," DB-OP-02530, " Fuel Handling Accident," and RA-EP-01500, " Emergency Classification." These procedures are included in the licensed operator training programs and include evacuation from the fuel handling area, confirmation of abnormal radiation levels, investigation of abnormal radiation levels by Radiation Protection personnel, evaluation of radiation levels for emergency classification, establishing and posting radiological boundaries, determination of actions to minimize radiation dose, and the initiation of actions to recover from the radiological incident. Therefore, detection of excessive radiation levels and the initiation of appropriate safety actions is met throvah the use of these area radiation monitors in the Fuel Handling Area and Spent Fuel Pool Area. 4 Personnel Training All DBNPS staff badged to work in the Radiologically Restricted Areas of ) the plant receive Radiation Worker Training. This training includes I identification of radiological alarms used in the plant, the proper response to a radiological alarm, and the potential consequences of ignoring a radiation monitor alarm. This training includes a discussion of area radiation monitor alarms r covers the activation of the monitor's audible alarm and its sound, the illumination of the monitor's red bulb light, the increase in indication on the monitor's meter, and the direction to leave the area and report the alarm to Radiation Protection. The training also discusses the increase in one's radiation dose and health risk from improperly responding to a I radiation monitor alarm and the disciplinary action for anyone who purposely ignores a radiation monitor alarm. i. Radiation Protection testing personnel are required to be qualified in order to respond to alarming area radiation monitors under the Radiation Protection tester training / qualification program. l
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