ML20236V580
| ML20236V580 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1998 |
| From: | Rathbun D NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA) |
| To: | Bennett R SENATE |
| References | |
| CCS, NUDOCS 9808040058 | |
| Download: ML20236V580 (5) | |
Text
PR E%
34 3
4 UNITED STATES a;
g NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2005tMoot
...../.
July 17, 1998 The Honorable Robert F. Bennett, Chairman Special Committee on the Year 2000 Technology Problem United States Senate Washington, D.C. 20510
Dear Mr. Chairman:
Enclosed is the U.S. Nuclear Regulatory Commission's responses to the post-hearing I
questions from the June 12,1998 hearing before the Special Committee on the Year 2000 Technology Problem. Please contact me if I can be of further assistance.
Sincerely, f. n.l. f g- /
Dennis K. Rathbun, Director Office of Congressional Affairs Fnclosure:
ns Stated I
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9808040058 980717 PDR ORQ NRCCO PDR 1
i
g Questions for Shir ey Ann Jackson, Chairman Nuclear Hegulatory Commission j
s Post-Hearing Guestions frorn the Senate Special Committee On the Year 2000 Technology Problem -
Utilities and the National Power Grid on June 12,1998 i
Statement:
"All of our other mission critical systems are on schedule to be Year 2000 compliant in accordance with OMB guidelines, with three currently being repaired, and three being replaced" (page 2, para.1).
- 1. Question:
What is the target completion date for the NRC mission-critical systems?
j Response: Two of NRC's seven mission-critical systems have been completed. Four of NRC's five remaining mission-critical systems are on schedule to be completed on or before January 1,1999. The final mission-critical system is on schedule to be rempleted by March 1999.
Mission-Critical System Status l
l l Implementation Renovation Validation System Name Milestone l l Milestone l Milestone Date l Complete l Date Complete l Date Complete Repair l
l l
l l
Emergency Response Data System l 08/1098 l l 01/1999 l 03/1999 66 %
35 %
0%
1 09/1998 10%
Emergency Telecommunications 08/1998 65 %
10/1998 0%
System Operations Center Information l 09/1%8 l
42%
12/1998 0%
01/1998 0%
Management System l
l 76 %
1 1
Statement:
"The concept of or 2000 readiness includes the planning, development, and implementation of appropriate contingency plans or compensatory action' for s
items that are not expected to be Year 2000 compliant, to address the possible impact that unrecognized problems may have on safe plant operation' (page 5, para.1).
- 2. Question:
What contingency plans exist and what types of compensatory actions might
)
l be taken in the event such problems occur?
Response: As part of the programs being oursued by nuclear power plant licensees to address the Year 2000 problem, all licensees are developing contingency j
plans in the event unanticipated problems arise. The Nuclear Energy Institute
(NEI) in conjunction with the Nuclear Utilities Software Management Group (NUSMG) is developing additional guidance for nuclear power plant licensees on contingency planning. This guidance will be available later in the Summer of 1993. We currently do not have detailed information on power reactor licensees' contingency plans. However, contingency planning is one of the areas that licensees are to address in their Year 2000 programs in response to NRC's Generic !.etter 98-01 Year 2000 Readiness of Computer Systems at Nuclear Power Plants. Further, the NRC will review licensees' contingency planning as part of the Year 2000 readiness sample inspections.
While contingency plans will be specific to the individual plant based on the specific impact of the Year 2000 problem on the facility, some general types of compensatory actions willlikely be established. Examples of these include:
1)
Provision for access control by augmenting the number of guards on site in the event of a failure in the security computer which prevents the ability to lock doors.
2)
Provision for additional technical staff to perform engineering calculations in the event computer programs fail to work properly.
{
3)
Provision for additional supplies of required materials such as fuel oil for backup diesel generators in the event of longer than anticipated loss of offsite power.
Statement:
"In addition to written responses, we plan to conduct inspections, on a sample basis, to assess licensee preparedness for the Year 2000 (page 3, para. 3).
3.a. Question: Describe the Year 2000 readiness inspection process. How many inspectors I
are there?
Response: The NRC staff has developed a draft Temporary instruction containing guidance for conducting the Year 2000 readiness sample inspections. The i
draft is currently out for comment and will be finalized in August. The NRC staff currently plans to use approximately 4 inspectors to conduct the Year 2000 readiness inspections.
3.b. Question: What are the inspectors' backgrounds?
Response: The NRC staff Year 2000 readiness inspectors are electrical / electronics engineers with backgrounds and knowledge in the review of the design of digital (software) based systems. These inspectors will have specific knowledge in the area of potential Year 2000 problems.
3.c. Question: What time frame is in place regarding the inspections?
Response: The NRC staff plans to begin the Year 2000 readiness inspections in l
September 1998 and complete them by March 1999, 2
i
- 4. Question:
To what extent are NRC's nuclear power plant Year 2000 readiness assessments "self-verifying". Would a greater extent of independent verification be more useful?
Response: In response to our Generic Letter, power reactor licensees will confirm and provide information regarding Year 2000 readiness of their facilities. The NRC will review licensee response to the GL 98-01. The NRC staff assessments and inspection-related activities of licensee Year 2000 programs are fully independent of any activities performed by the licensee. Therefore, the NRC staff review effort on laensee Year 2000 readiness is sufficiently independent to permit decisions to be made on the need for any subsequent actions. If the results of the sample inspections described in response to Question 3 identify generic concerns, either additional inspections will be conducted or additional guidance will be issued.
Statement:
"It should be noted that NEl/NUSMG 97-07 (Nuclear Utility Year 2000 Readiness framework document prepared by the Nuclear Energy Institute) is programmatic and does not address fully all the elements of a comprehensive Year 2000 program. In particular, augmented guidance in the area of risk management, business continuity and contingency planning and remediation of embedded systems is needed to fully address some Year 2000 issues that may arise in licensee program implementation" (page 8, para. 2).
- 5. Question:
Who wid be the source of this guidance, and how can it be best coordinated across the nuclear power industry?
Response: As mentioned abow in the response to Question 2., NEl/NUSMG is developing additional guidarro for the nuclear power industry on contingency planning.
Guidance on riv. management, business continuity and remediation of embedded sysOms is provided in the General Accounting Office (GAO) document, G 1.0/AIMD-10.1.14," Year 2000 Computing Crisis: An Assessment Guide", September 1997 which is referred to in the NRC Generic Letter 98-01,
" Year 2000 Readiness of Computer Systems at Nuclear Power Plants" dated May 11,1993. Additionally, the NRC plans to participate in an industry-sponsored w<vkshop to be offered later this year on industry Year 2000 progress. The NRC will use this opportunity to discuss its initial findings from the Year 2000 inspections it will begin in September.
Statement:
"Notwithstanding our regulatory limits, we recognize the national importance of a broader focus that helps to ensure that potential concems with electrical grid reliability are identified and resolved" (page 0, para.1).
- 6. Question:
What can be done to assure this broader focus?
f Re por se: A broader focus for nuclear power plant Year 2000 readiness beyond nuclear safety is provided in NEl/NUSMG 97-07. This document addresses Year 2000 readiness of all nuclear power plant systems including not only safety-related i
systems, but those necessary for continued plant operation in order to maintain l
l 3
l
e supply to the electrical grid. Moreover, NRC is fully supporting the broader focus as a member of the Energy Sector Working Group of the President's Council on Year 2000 conversion.
i Statement:
"To date, we have not identified or received notification from licensees or vendors that a Year 2000 problem exists with safety-related initiation and actuation systems" (page 9, para. 2).
1
- 7.. Question:
What are the exact reporting requirements of 10 CFR Part 21,10 CFR 50.72, l
and 10 CFR 50.73, which mandate that the NRC be notified of such instances?
How do these regulations relate to the vendors?
Response: 10 CFR Part 21, Reporting of Defects and Noncompliance, specifically requires nuclear power plant licensees and vendors providing safety-related equipment or equipment providing safety functions to report defects and noncompliance identified in that equipment to the NRC. A Year 2000 problem in a safety-related initiation and actuation system is an example of such a reportable defect.10 CFR 50.72, immediate notification requirements for operating nuclear reactors, requires nuclear power plant licensees to immediately notify the NRC of emergency situations and promotly notify the NRC of other non-emergency events such as deviations from plant technical specifications including unanalyzed conditions that significantly compromise plant safety or could prevent the fulfillment of a safety function.
10 CFR 50.73, Licensee Event Report System, requires licensees to submit a Licensee Event Report (LER) within 30 days after discovery of an event which is prohibited by plant technical specifications or results in the plant being in an unanalyzed condition that significantly compromises plant safety or was outside the design basis of the plant. Events covered by 10 CFR 50.72 and 10 CFR 50.73 include equipment failures and design errors such as may result from a Year 2000 problem in a safety related initiati.on and actuation system.
10 CFR 50.72 and 50.73 do not apply to vendora.
4 I
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