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.
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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
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.
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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.
James G. Partlow
Associate Director for Projects
Office of Nuclear Reactor Regulation
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
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