Task Action Plan Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54(f) (Generic Letter 89-06)
April 12, 1989 TO: ALL LICENSEES OF OPERATING PLANTS, APPLICANTS FOR OPERATING LICENSES, AND HOLDERS OF CONSTRUCTION PERMITS SUBJECT: TASK ACTION PLAN ITEM I.D.2 - SAFETY PARAMETER DISPLAY SYSTEM - 10 CFR .50.54(f) - (GENERIC LETTER NO. 89-06) On October 31, 1980, the NRC staff issued NUREG-0737 which provided guidance for implementing Three Mile Island (TMI) action items. On December 17, 1982, Generic Letter No. 82-33 transmitted Supplement 1 to NUREG-0737 to all licensees and applicants to clarify the TMI action items related to Emergency Response Capability, including item I.D.2, Safety Parameter Display System. Supplement 1 extracted the fundamental requirements for emergency response capability from the wide range of regulatory documents issued on the subject. It was written at the conceptual level to allow for a high degree of flexibility in scheduling and design. In recognition of the interrelationships among the action items addressed in Supplement 1, the staff made allowance for each licensee to negotiate a reasonable, achievable schedule for implementing its emergency response capability. However, the staff stated that because the SPDS can provide an important contribution to plant safety, it should be implemented promptly. The staff evaluated licensee/applicant implementation of the safety parameter display system (SPDS) requirements at 57 units and found that a large percentage of designs do not fulfill the requirements identified in Supplement 1 to NUREG-0737. Enclosed with this letter is NUREG-1342 which provides to all licensees, applicants, and construction permit holders the benefit of the staff's experience to aid them in implementing SPDS requirements. NUREG-1342 describes methods used by some licensees/applicants to implement SPDS requirements in a manner found acceptable by the staff. NUREG-1342 also documents design features that the staff found unacceptable and gives the staff's reasons for finding them unacceptable. The information in NUREG-1342 does not constitute new requirements. Supplement 1 to NUREG-0737 establishes the legal requirements for SPDS. These requirements can be met with a relatively simple SPDS as well as with a more elaborate system. Also enclosed is a checklist concerning SPDS implementation. The purpose of the checklist is to provide licensees with a guide to assist them in determining the status of their SPDS with respect to NRC requirements. 8904120042 . - 2 - The checklist, when completed and used in conjunction with NUREG-1342 and photographs of the SPDS layout, will provide licensees with comprehensive information that will facilitate establishing the implementation status of their SPDS. Accordingly, pursuant to 10 CFR 50.54(f), operating reactor licensees and holders of construction permits are requested to furnish within 90 days of the date of this letter, one of the following: 1. Certification that the SPDS fully meets the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342. Licensees should maintain supporting documentation for three years, including the completed checklist and photographs used to establish SPDS implementation status. 2. Certification that the SPDS will be modified to fully meet the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342. The implementation schedule for the modifications shall be provided. Licensees should maintain supporting documentation for three years, including the completed checklist and photographs used to establish SPDS implementation status. 3. If a certification cannot be provided, the licensee shall provide a discussion of the reasons for that finding and a discussion of the compensatory action the licensee intends to take or has taken. Staff review has verified that the following nuclear units have a fully satisfactory SPDS: Catawba 1 and 2, Clinton, Hatch 1 and 2, McGuire 1 and 2, Millstone 3, River Bend, Susquehanna 1 and 2, and Yankee Rowe. No response is required for these units. Because of the very recent full power license reviews conducted for these units, South Texas Project 2 and Vogtle 2 will not be required to respond to this generic letter. Big Rock Point will not be required to respond to this generic letter because of the staff's ongoing review of their proposal for SPDS. This request is covered by Office of Management and Budget Clearance Number 3150-0011 which expires December 31, 1989. The estimated average burden hours is 25 person hours per owner response, including searching data sources, gathering and analyzing the data, and preparing the required letters. These estimated average burden hours pertain only to these identified response- related matters and do not include the time for actual implementation of the requested actions. Comments on the accuracy of this estimate and suggestions to reduce the burden may be directed to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Commission, Records and Reports Management Branch, Division of Information Support Sources, Office of Information Resources Management, Washington, D.C. 20555. . - 3 - If you have any questions about this matter, please contact Richard J. Eckenrode, Section Chief of the Human Factors Engineering Section, Human Factors Assessment Branch, at (301) 492-1105. Sincerely, James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures: 1. NUREG-1342 - A Status Report Regarding Industry Implementation of Safety Parameter Display System 2. Licensee Checklist for Safety Parameter Display System Status 3. Listing of Recently Issued Generic Letters
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021