ML19339A704
| ML19339A704 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/30/1980 |
| From: | Broughton T METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19339A702 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8011040547 | |
| Download: ML19339A704 (9) | |
Text
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lh LIC 10/30/80 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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METROPOLITAN EDISON COMPANY
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Docket No. 50-289
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(Restart)
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(Three Mile Island Nuclear
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Station, Unit No. 1)
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LICENSEE'S TESTIMONY OF T. GARY BROUGHTON IN RESPONSE TO BOARD QUESTION NO. 11 s
80110405'/7
OUTLINE The purposes and objectives of this testimony are to respond to Board Question No. 11, dated September 26, 1980, which requests evidence that the requirements on page A-45 of NUREG-0578 will be met and the schedule for meeting those requirements.
The referenced requirements are to provide the analysis, emergency procedures and training to substantially improve operator performance du-ing transients and accidents, including events that are caused or.orsened by inappropriate operator actions.
The testimony describes the status of Licensee's participation in the ongoing Anticipated Transients Operator Guidelines program, and reports that implementation of TMI-1 procedures revised as a result of this program, as well as training on the revised procedures, are expected to be completed by the Fall of 1981.
i INTRODUCTION
.This testimony, tr Mr. T. Gary Broughton, GPU Control and t
Safety Analysis Manager, is addressed to Board Question No. 11.
l The question is quoted below, followed immediately by Licensee's response.
i BOARD QUESTION NO. 11 The board is not satisfied with the staff findings in the SER with respect to Recommendation 2.1.9.C (transients and accidents) of NUREG-0578.
The staff concludes that satisf actory progress has been made and the item is complete.
SER, pp. B-10, C8-49.
According to Table B-2, the analyses and procedures were scheduled for completion by early 1980.
We observe that in May of this year, it was reported that "the Staff is performing a generic review of transients and other accidents in accordance with Recommendation 2.1.9 of NUREG-0578" (NUREG-0667, p.
5-26).
We expect the licensee and the staff to present evidence that the requirements on p. A-45 of NUREG-0578 will be met and to explain the schedule for meeting those requirements.
The board, as well as the staff, must have sufficient information'to decide whether satisfactory progress is being made, i
RESPONSE
BY WITNESS BROUGHTON:
i The Board has requested evidence that the requirements on page A-45 of NUREG-0578 will be met and the schedule for meeting these requirements.
Page A-45 discusses Recommendation-2.1.9.c of NUREG-0578, which is to "[p]rovide the analysis, l
emergency procedures, and training to substantially improve i
operator performance during transients and accidents, including events that.are caused or worsened by inappropriate operator actions."
There is a program in progress to meet these requirements at TMI-1, and it is expected that procedures revised as a result of this program will be implemented by the Fall of 1981.
TMI-1 is one of six utilities participating in the B&W Abnormal Transient Operating Guidelines (ATOG) program.
This program provides plant specific guidelines which form the basi
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for:
(1) improved plant procedures, (2) operator training in the understanding of plant transient response, and (3) operator training in the use of the procedures.
The guidelines enable d
diagnosis of plant conditions during the transient, emphasize 4
stabilization of plant conditions, and provide guidance to l
mitigate failures which would interfere with achieving the
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j appropriate plant condition.
In developing the guidelines particular attention has been paid to providing a document which could be used by operators during the transient.
ATOG incorporates several existing guidelines, including those for Loss of Coolant Accidents, and will incorporate Inadequate Core Cooling guidelines.
ATOG is based on existing LOCA analysis plus additional analysis of small steam line breaks, loss of feedwater, loss of offsite power, excessive feedwater addition and steam generator -
tube rupture.
These events, all less severe than the design basis events previously analyzed, were selected for study because they are more likely. to occur than design basis ever.ts and their duration provides for operator interaction.
The analysis of each event began with a collection of data appro-priate to the transient.which specifically described TMI-1.
A l
l diagram was constructed to organize the data to show how specific plant systems and subsystems are expected to function in various operating modes and in the event of failures.
Based on this' data an event tree was constructed assuming the particular initiating event and identifying the desired and possible alternative outcomes, considering equipment malfunc-tions and operator errors.
Next, the scenarios were reviewed j
and grouped as to effect on the plant.
Selected representative scenarios were then simulated with computer codes providing best estimates of plant performance.
l This process and the results are the technical input to the guideline training material.
The plant response to the basic transient and its alternate scenarios, the key symptoms necessary to determine the plant condition and the actions required to stabilize the plant are then explained in the training material.
After analysis of all events, the procedure guideline is i
developed.
A set of instructions is assembled to evaluate the key symptoms which characterize plant conditions.
If abnormal i,
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conditions are indicated, instructions are provided to evaluate additional symptoms, to take action to correct causes of abnormal conditions and/or to take action to achieve plant stability.
Combining the actions common to these events i
produces a single procedure, and therefore a single set of ocerator actions, based on key plant parameters, without requiring that the specific initiating event be known.
Furthermore, by systematically evaluating symptoms, the procedure aids in diagnosis of the event as the plant is being stabilized.
In addition to the improved technical content of these guidelines, human factors considerations have been included in their development.
Presentation of training material, format and level of detail in the guidelines, and the ability of operators to use guidelines during simulated transients have been addressed by a human factors review.
j When ATCG is implemented at TMI-1, these guidelines will be used following reactor trip or when a rapid shutdown from power is required.
Since the procedure is applicable during forced or natural circulation, with or without offsite power, and with normal or emergency feedwater, several existing plant procedures will require modification and some may:be elim-inated.
Furthermore, since the approach to ever.t diagnosis is altered by this procedure, a revised program to train operators in this approach, in the use of this specific procedure and in the use of c:.ser modified procedures is required.
1 P I
c.
W B&W f.
spleted a draft ATOG document for Arkansas Power in e
August, 1980, and has been working on various scages of guideline development for other B&W owners.
With respect to TMI-1, appropriate plant data has been gathered, functional diagrams constructed and event trees are being prepared.
Draft guidelines should be completed in April, 1981.
We expect to receive final TMI-l ATOG from B&W in July, 1981.
Implementation, including conversion of the guidelines f
into plant procedures, modification of interfacing procedures and training cf operators is expected to be complete in September, 1981..,
{
T. GARY 3RCUGHTCN Business Address:
GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 i
Education-3.A.,
Mathematics, Dar tmouth College, 1966.
1 Experi.
Control and Safety Analysis Manager, GPU Service Corporation, 1978 to present.
Responsible for nuclear safety analysis and integrated thermal, hydraulic and control system analysis of. nuclear and fossil plants.
Supervised on-site technical support groups at Three Mile Island, Unit 2 during the post-accident period.
Safety and Licensing Engineer; Safety and Licensing Manager, GPU Service Corporation, 1976 to 1978.
Performed i
and supervised nuclear licensing, environmental licensing and safety analysis for Cyster Creek, Three Mile Island and Forked River plants.
i Served as Technical Secretary to Oyster Creek and Three Mile Island General Office Review Boards.
j i
- Officer, U.S'.
Navy, 1966 to 1976.
Trained at Naval Nuclear Power School, Prototype and Submarine School.
Positions held include Nuclear Propulsion Plant Watch Supervisor, Instructor at DIG prototype plant and Engineering Officer aboard a fast-attack nuclear submarine.
j i
Publicatiens:
EPRI COM-5, RETRAN
'. Program for One-Dimensional Tran ent Thermal-Ey-draulic Analyses of Complex Fluid Flow Systems, Volume 4: Applications, December, 1978, Section 6.1,
" Analysis of Rapid Cooldown Transient - Three Mile Island Unit 2",
with N.G.
Trikouros and J.
F. Harrison.
=
"The Use of RETRAN to Evaluate Alternate Accident Scenarios at TMi-2", with N. G. Trikouros.
?:oceedings of the ANS/ ENS Topical Meeting on Thermal Reactor Safety, April 1980, CONF-300403.
"A Real-Time Method for Analyzing Nuclear Power Plant Transients", with P.S. Walsh.
ANS Transactions, Volume 34 TANSAD 34 1-899 (1980).
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