ML20024A988
| ML20024A988 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/09/1980 |
| From: | Elliott N BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-01, TASK-1, TASK-GB GPU-0053, GPU-53, NUDOCS 8307010256 | |
| Download: ML20024A988 (5) | |
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__ 1 Nuclear Operating Experience Seminar New Orleans Louisiana March 9-11,1980 0
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Post-TMI plant staff training N. S. Elliott Manager, Training Services Customer Service Department Nuclear Power Generation Division 1.unchburg, Virginia Analysis of the TMI-2 Incidant of March 28,1979, is evident now that operators need a significantly has amph==ivad the importance of the operator in improved underd=adiar of the basic fundamentals nuclear safety. Therefore, training and operations and their application to safe operation. Thus, the support must be upgraded to ensure that major theme is " Return to Basics.
operating personnel, when faced with a==-2 1
To apply under*== ding of the " Basics" to the conditions, will respond correctly with protection B&W programs, analysis and design engmeers are of the public as first priority. Babcock & Wilcox, used as instructors to present their areas of the utilities, and other suppliers are worlang with expertise, such as heat transfer, fluid flow.
INPO, NSAC, ANS, AIF, and the NRC to *
=ccidarst analysis, and tren=iant analysis. These improve the industry's perforrnanca and instruc, ors are intimately involved in applying the capabilities in this regard.
tachm.agy is their everyday work, and have at B&W contributes support activities for the least harhalar's degrees in their areas of development of new standards and policy instruction. To be effective instructors, engmeers programs. (The Manager of Traming is a memhae must be trained in appropriate techniques and in of the ANS 3 Nuclear Power Plant Operations adjusting their vocabulary and presentation to Committee and subcommittee che sn for
, operations. oriented peraannal Simulator Standards.) Such g@ tion aids in We are bridging the gap between operation and modifying programs and content to keep ahead of design through increased engineermg involvement.
requirements rather than trying to catch up. We h mutual==ak=ame of ideas and technologies have made ch===== within the prerogatives of our has been of great benefit. Power plant owners and agreed scope of training service based on our ey 4aw are encouraged to utilize plant and home anticipation of areas requiring change. Hopefully.
office engineering personnel in training their these changes will be consistent with the operators as a manna of communication between a
regulatory positions and industry s*=ndards of the plant staff, engineering, and operations.
performance when no.u, d. and will result in To further improve traimag, a system of class better operating performance. The following audits and simulator===aians has been started.
sections address specific chhages in B&W's Company management, supervisory engineers, and I
training programs for plant operators, training staff audit selective classes and provide written critiques to the instructor and the training Training for owners of B&W service group for follow.up and implementation.
Operating units We have also expanded the role of management Training services for owners of B&W operating and engineering in the decaded review of site units consist primarily of req== hee = tion training instructions. This expansion is aimed at becoming j
for operators of the plant who currently hold more directly involved in operation of the NSS.
-l active nuclear operator licana==, and replacement plus the development of anticipated transient training for new operators of these plants. The operating guidatinae (ATOG). This program training programs were originally based on the further enhane== communication and the assumption that trainees had a sophisticated understanding of operations for management as l
unders*-adiar of B&W mielanc steam systems. It
' well as for the engmeers, involved.
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Requalification training Another practical problem is inserting the casualty, involving the steam line break, followed The one week requalification training program by a steam generator rupture. This problem includes four hours of each day devoted to requires the crew to recognize that they have a classroom study, and the remaining four hours to significant radiation release and that plant drills and exercises on the B&W nuclear power cooldown is necessary, along with reduction in plant simulator. Classroom lectures have been radia on release.
l revised to include the fundamentals of thermodynamics and the development of the Replacement operator training protection criteria for the plants. Practical problems associated with tr=naimat analyses and The replace:nent training programs, better known illustration of the Loss of Coolant and Small as " Hot License Programs," have primarily been Break accidents are included in the program to expanded from a two week standard to from three insure that the students can apply the basics. h to five weeks. The length of the course depends on l
program concludes with a discussion of the the utility's requirements. The first one to two I
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opersting experience from B&W units, plus weeks are devoted to reactor physics and startup significant experience from other pressurized training, and the remaining weeks to plant water reactors such as the Prairie Island steem operations. The program concludes with a reactor generator tube failure and the North Anna-1 startup exam, plus a casualty exam in which each sn===ful student must combat one to three overcooling and radiation release event on 4
September 25,1979.
casualty conditions and control the plant safety.
The simulator portion has been restructured to The casualty exam makaa the replacement emphasize team training where each individual, as operators program essentially equivalent to the a member of an operating team, functions in a cold license training programs which have been 4
specific role throughout each exercise. Each used to support initial plant staffing. The incident is brought under control to the poing classroom portion of these programs has been where a recovery plan has been established.
- Ipanded to include review of the basic Certain exercises are required to be carried out to f""damentals (reactor theory, heat transfer, and their complete conclusion (i.e., to a cold shutdown fluid flow) using lectures and numerical problem condition).
solution. The B&W course does not, however, Of particular importance is inclusion of b substitute for a good, basic trainmg course. It small break, loss of-coolant accident, which does provide an additional review of the basics
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app ed to power plant operations and applied li produces plant responses similar to Three Mile Island (e.g., pressurizer level going up while during exert Ise periods on the B&W nuclear power pressure is going down, and stable temperature plant aimniator. Haditional areas of the plant and pressure but with the reactor coolant system control systems and procedures are included as at saturation conditions).
they have been in previous courses.
Multiple casualties are regularly meluded I" Shift technical advisor the program. The multiple casualties are entered as a combined effect, or as a combination of The Shift Technical Advisor Course was developed sequential failures. Sequential failures are to prepare engmeers and licenced senior reactor implemented by b instructor as a logical failure operators to assume duties of Shift T=ehaie=1 Advisor. The first course was conducted in to which the student may relate. Typical of these multi-failures is the loss of all feedwater, including December,1979. The Shift Technical Advisor the auxthary feeds, or a feed valve fading to open Course will be offered at various times durmg and h block valve failing to close on b 1980, and hopefully in subsequent years. The autonistic close signal. Integrated control system course will primarily consist of a one week or input sensor failures are combined with steam lectuWproblem working session, followed by a safety valves remaining open.
second week of simulator operation where the Another multiple casualty involves a power students will perform as shift technical advisors plant in h manual control which experiences a and analyze transients in progress.
drop # control rod or a feed system failure. Each aW casualty requires the operator to reduce power and balance heat generation with heat removal. In Along with the changes to programs, the automatic, the integrated control system (ICS) performance of the B&W nuclear power plant does this function.
simulator has been improved. The Three Mile L-F1
Island incident pointed out the need to continue engineers from the various disciplines in total power plant training sequences to the final nuclear '.,ower 91 ant systems. As B&W worked on its portion of 'he Three Mile Island accident conclusion of cold shutdown.
The first major simulator modification was the support, it was evident that the various disciplines inclusion of two phase conditions h2 the primary of the Engineering and Service Departments could control volume. While saturation is not required to handla their own analysis and engineering.
be demonstrated on the classical loss-of-coolant However, more appreciation of total system accident, the consideration of the small break operation was needed. Our response has been to demands that this condition be demonstrated to develop and institute an Integrated Plant System all operators.
course conducted by B&W for design and service The second modification included the degrading personnel The course is directed by the Training or, loss of natural circulation within the prunary Services group, but conducted entirely by system as a function of void fraction.
instructors from the various disciplines of the One of the most significant modifications to the Engineering Department. The total integrated B&W simulator was on the pressurizer. The systems course requires approximately 50 weeks pressurizer model had to be redesigned to allow to complete with engineers taking one lesson each the primary system to go solid and recover, be week and eriodic exams. Major section exams are completely voided, refilled, regain temperature, given to inoicate completion of a particular major and draw a bubble.
black of instruction. The course is ultimately Another significant modification was to make concluded with a five-unit section on operation flow through the pressurizer relief valve system a using the B&W nuclear power plant simulator.
function of the density of fluid flowing through the relief valves. Most of the time, this fluid is Conclusion steam. However, on certain occasions, the pmnary The most significant question raised as a result of system is solid, and accurate representation of the Three Mile Island incident is the level of water flow through these relief valves is required.
understanding of the operators and their on-the-as are differences in the mass flow rates.
Job performance. We must continue to look at the As a result of reproducing the Three Mile Island performance of operator trainees in an objective incident, we discovered that to better represent way and reasonably assure ourselves that they can boil dry and repressurization, we had to modify perform correctly. We may have to implement the steam generator response, ernmination programs with higher incidences of A special traimng feature was installed on the unsatisfactory performance than we had simulator to account for the unique high pressure considered previously acceptable. In particular, it injection and makeup system of the Davis Besse-1
. may be desirable for plant operators to conduct power plant. Different from other plants. Davis-operating araminations on a simulator following '
Besse 1 has twa low-capacity makaup pumps and requalification training. Requalification, then, two low-head, high pressure injection pumps. The
~would be based on avaminations conducted by a capability of these pumps to cope with the " loss team of utility management and B&W trainmg of all feedwater" needed to be simulated for the stait We welcome utility participation in this
,l Davis Besse-1 operators.
great responsibility of judging operator As a result of the simulator modelimprovement, competence. In particular, we encourage we believe we have significantly improved our participation of the entire owner's management training effectiveness and the ability to perform in structure, including the station superintendent, highly credible manner small breaks, compound plant operations manager, and utility home office casualties, and special training required to support management. The changes to the B&W-training the Davis Besse 1 plant.
programs, as described, are only the beginning.
and much additional development remains.
Babcock & Wilcox. ternal tra..ining Successful development is d.ependent on in B&W has recognized the need to train its participation by owners of B&W operating plants.
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