ML20137L922
| ML20137L922 | |
| Person / Time | |
|---|---|
| Issue date: | 11/26/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | |
| References | |
| RTR-REGGD-01.134, RTR-REGGD-1.134 ACRS-T-1471, NUDOCS 8512030562 | |
| Download: ML20137L922 (183) | |
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UNIIED STATES 1 NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: DOCKET NO:
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEE ON IIUMAN FACTORS O
V LOCATION: WASilINGTON, D. C. PAGES: 182 - 284 DATE: TUESDAY, NOVEMBER 26, 1985
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NATIONWIDE COVERACE
CR25016.0 DAV/dnw 182 1 UNITED STATES OF AMERICA 7-
- , ) 2 NUCLEAR REGULATORY COMMISSION 3 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 4 SUBCOMMITTEE ON HUMAN FACTORS 5
6 Nuclear Regulatory Commission Room 1046 7 1717 H S treet, N.W.
Washington, D. C.
8 Tuesday, November 26, 1985 9
The subcommittee met at 8 : 30 a.m. , Mr. David A. Ward, 10 .
chairman, presiding.
11 12 PRESENT:
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13 MR. DAVID A. WARD MR. CARLYLE MICHELSON 14 DR. FORREST J. REMICK r MR. CHARLES J. WYLIE 15 I KRIS GIMMY, ACRS Consultant i 16 l JOHN SCHIFFGENS, Assigned ACRS Staff Member l I
t 17 i l
18 i 19 l
20 l
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22 23
% -F Reporters, t .
25
(} PUBLIC NOTICE BY THE UNITED STATES NUCLEAR REGULATORY COMMISSIONERS' ADVISORY COMMITTEE ON REACTOR SAFEGUARDS TUESDAY, NOVEMBER 26, 1985 The contents of this stenographic transcript.of the proceedings of the United States Nuclear Regulatory Commission's Advisory Committee on Reactor Safeguards (ACRS), as reported herein, is an uncorrected record of i
the discussions recorded at the meeting held on the above date.
No member of the ACRS Staff and no participant at
() this meeting accepts any responsibility for errors or inaccuracies of statement or data contained in this 3 transcript.
i 4
I O
4 j
O REGULATORY GUIDE 1,134 ENDORSES MEDICAL REQUIREMENTS IN ANSI /ANS 3.4 - 1983
" MEDICAL CERTIFICATION AND MONITORING OF PERSONNEL REQUIRING OPERATOR LICENSES FOR NUCLEAR POWER PLANT EXCEPT:
- LICENSED MENTAL HEALTH PRACTITIONER
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() -
"N0 SOLO" QUALIFIED PERSON SHOULD BE LICENSED
- DOCUMENTATION TO SUPPORT RESUMPTION OF DUTIES AFTER DISABILITY OF 30 DAYS OR LONGER i
I 11/26/85 l ,
0160 01 01 183 3 DAVbw 1 PROCEEDINGS j) 2 MR. WARD: The meeting of the ACRS Subcommittee 3 on Human Factors, which began yesterday, will now 4 reconvene.
5 I'm David Ward, subcommittee chairman.
6 Our first topic today is the discussion of 7 Regulatory Guide 1.135.
8 We'll call on Susan Shankman of the Staff.
9 MS. SHANKMAN: Good morning. I think we talked 10 about the medical requirements in relation to the rule 11 yesterday.
12 (Slide.)
13 The Reg Guide is not significantly different than b'"s 14 the way it went out for public comment. It basically 15 endorses the ANS 3.5 1983 standard.
16 I have a copy with me, if anybody's curious.
17 But the medical requirements, I think there are a 18 few changes to the past ANS standard and the amount of blood 19 work that's necessary. The only exceptions that you take 20 are that if you have a mental condition that needs to be 21 assessed, it must be done by a licensed mental health 22 practitioner, licensed by the state in which it's done.
23 MR. WARD: What does that mean?
24 Does that include a psychologist?
(} 25 MS. SHANKMAN: Yes. They're licensed mental ACE FEDERAL REPORTERS, INC.
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0160 01 02 184 1 DAvbw I health practitioners and the assessment of the condition O 2 would be something that was strictly psychological and not 3 medical. DSN 3, I think is very clear.
4 Are you familiar with that?
5 MR. WARD: No.
6 MS. SHANKMAN: I'm familiar with it, only because 7 I used to work for the Director of the National Institute of 8 Mental Health. DSN 3 is the handbook on which you diagnose 9 mental conditions. In some instances, they will make it 10 clear whether it is pyschological or medical. Medically, 11 you would have to use a psychiattrist.
12 So that's all. But in other words, they have to
(~ , 13 be licensed for medical health, not just a general T.J 14 physician.
15 The other thing is, that we have specified in our 16 Reg Guide that if you ask for a conditional license and the 17 condition is no solo, that the qualified person, that is, 18 the other person in the control room, that they also be 19 licensed, but they don't need, as I understand it, to have 20 the same license. So that an RO could be the other 21 qualified person or an SRO.
22 DR. REMICK: Run that by me again.
23 MS. SHANKMAN: In other words, the idea is, if 24 you have a no solo condition --
( '; 25 MR. WARD: Tell us what that means first.
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0160 01 03 185 l_ DAVbw 1 MS. SHANKMAN: The assumption is that you have a
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2 medical condition that could cause you to lose consciousness 3 or that you are medicated. You have a condition that's 4 under control, like epilepsy or diabetes, which could also 5 cause a coma, but that it's under control, and that our 6 doctor agrees with the facilities doctor, that the condition 7 is basically under control; however, because there is an 8 outside chance that you could lose consciousness or lose 9 judgment, you are conditioned medically. You may not be 10 alone. You may not be the only one responsible for the 11 operation of the reactor.
12 I think this goes back to days when the crews r- 13 were different. So no solo means that you may not be alone b) in the control room.
14 15 MR. WARD: Let's see. Under present rules, no 16 one can be alone in the control room anyway, can theyh?
17 MR. BOGER: That's correct.
18 DR. REMICK: Nonpower reactors, you can, I 19 believe.
20 MS. SHANKMAN: But this applies to power 21 reactors.
22 DR. REMICK: I assume here that it applies to 23 all, doesn; tit?
24 MS. SHANKMAN: No. It's 1.311, and when it says 25 "15.," then it will apply to nonpower reactors.
( })
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0160 01 04 186 DAVbw 1 MR. MICHELSON: Have you considered the 2 possibility that the person may collapse over the control 3 board, and as a consequence actuate various things. Belt ,
4 buckles of late seem to have done actuations from just 5 leaning over the control board.
6 What if somebody collapsed over the control 7 board?
8 MS. SHANKMAN: I guess we'd have to qualify it, 9 so that there's someone strong enough to pick you up.
10 DR. REMICK:
11 MR. MICHELSON: No, collapse over it. I'm gcing 12 to fall over the control board when I faint.
(~) 13 Is that an undue safety risk?
gj 14 MS. SHANKMAN: I'm going to turn this question to 15 Bruce.
16 MR. MICHELSON: Has this ever been analyzed to 17 make sure that's not too much of a problem.
18 MS. SHANKMAN: Bruce?
19 MR. BOGER: I don't think we'ver addressed that.
20 MR. MICHELSON: It might be, if I also weigh 250 21 pounds, and the fellow in there with me weighs 150, he may 22 have a little trouble getting me off without actuating a few 23 other things in the process. And many of these boards now 24 have the miniaturized bact:-lighted push buttons, and many,
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(u )'. 25 you can light a lot of them in a hurry by just fiddling ACE-FEDERAL REPORTERS, INC.
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0160 01 05 187 1 DAVbw I around.
O 2 MR. WARD: Could we go back to the question.
3 Except for Carl's concern, since you can't have a 4 person in the control room by himself anyway, under other 5 regulations, why do you even need this one?
6 Isnt it extraneous?
7 MS. SHANKMAN: Right. It is historical to call 8 it no solo, but I still think the idea is that the license 9 has to be conditioned, so that this member of the team needs 10 someone who is qualified, really, in the control room, 11 DR. REMICK: Need it be limited to the control 12 room? I can see there might be other places where you would 13 want an operator performing functions that might af fect (3
v 14 reactivity, and so on, and manipulating controls, in which 15 you might want somebody else there, if you had this type of 16 condition.
17 MS. SHANKMAN: You're going to have to look in 18 the Reg Guide. I think that's the intent, to make sure that 19 it says that, because I think it talks about, that might 20 cause operational errors. That would not be confined to the 21 control room.
22 DR. REMICK: It could be the spent fuel pool, for 23 example, 24 MS. SHANKMAN: Everybody, when they talk about
() ?5 it, talk about in the control room, but I think the phrase 1
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1 DAVbw 1 in the Reg Guide -- and I will check it -- and I think I O 2 that's a good suggestion, to make it operational errors.
3 MR. WARD: Okay. So you're saying, it's not 4 extraneous, because it applies to places other than -- the 5 control room is already covered by other rules and 6 practices and regulations or something. So it might apply 7 elsewhere.
8 MS. SHANKMAN: I don't want to say exactly. Let 9 me look at the Reg Guide. I think that's a good point.
10 MR. WARD: When will you do that?
11 MS. SHANKMAN: As soon as I get a copy of it.
12 MR. WARD: Can we come to this later in the 13 meeting?
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14 MS. SHANKMAN: Sure.
15 MR. WARD: Let me ask, if this is applied, does 16 this person have a sign hung on him or what?
17 MS. SHANKMAN: The license has it as part of the 18 licensing level, which is really your license. It says, 19 this is conditioned, based on a medical condition.
20 MR. WARD: So if I go into a plant, and I ask an 21 operator or shift supervisor, if there is anyone that he 22 works with who has that condition on his license, I'd expect 23 him to know?
24 MS. SHANKMAN: A shift supervisor? Yes.
(} 25 MR. WARD: Even an RO, because you're saying in ACE-FEDERAL REPORTERS, INC.
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0160 01 07 189 DAVbw I some cases you would expect the RO to be the back-up 2 person.
3 MR. BOGER: I think, Dave, that what we really 4 expect is that each facility would have some sort of 5 administrative control over the shift crew, such that you 6 know it was manned appropriately.
7 I'm not sure that each operator knows what 8 reservations appear on each other operator.
9 MR. WARD: But if an RO has this condition on his 10 license, and I guess I'm confident there's no probicm with 11 the control room, but if I think of the June incident that 12 occurred at Davis-Besse, operators had to go off into the
() 13 plant and get around the plant rather athletically, in a 14 sense, and perform some important operations. I presume 15 some of them were solo for parts of that. I guess those 16 weren't even licensed operators, but were assistant shift 17, supervisors, and the others were auxiliary operators.
18 I'm trying to figure out if this a practical 19 requirement.
20 MS. SHANKMAN: Okay.
21 MR. WARD: We'll talk more about it later?
22 MS. SHANKMAN: Yes. Let me get a chance to look 23 it up, but I think your point is excellent. The intent is 24 that for someone who might have a problem that would cause
/~s (s ) 25 an operational error, that they shouldn't be in a situation 1
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0160 01 08 190 1 DAVbw 1 where that could happen.
2 Let me see what the exact wording is.
3 MR. WARD: I mean, I suspect for most cases, 4 medical cases, epilepsy, for example, it's kind of a 5 nonproblem these days. The industry probably shouldn't 6 worry about it. If you're going to worry about it, I'm just 7 concerned whether you really have a practical --
8 MS. SHANKMAN: I don't know whether epilepsy,
'9 well, some epilepsy is a problem. That's why each one is 10 individually evaluated. The documentation to support 11 resumption of duties after a disability of 30 days or 12 longer. This is just that if someone has a condition that 13 has disabled them, and they can no longer perform licensed 14 duties or they don't meet the original ANS 3.4 standard, 15 because of some illness or accident, then they can be put 16 back into a licensed position.
17 And if it's longer than the period that we talked 18 about yesterday, they would have to go through the refresher ,
19 training, depending on what function they have held in the 20 interim. But without further evaluation from us, they could i
21 be put back into licensed duties, if they've been examined 22 by a licensed medical practitioner, who agrees that they now 23 meet the medical requirements in the ANS 3.4 1983 standard.
l 24 But that the facility has to notify us that all of that has l
i 25 happened and send us supporting medical documentation.
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DAVbw 1 Any questions on that?
i
\J 2 MR. MICHELSON: I have two questions.
3 The first one, back on the solo question. If 4 it's a two-unit control room and the person on Unit 2 is 5 licensed to operate Unit 1 as well, can he be the second 6 person in that control room, so that you're just down to one 7 on Unit 1 and one on Unit 2, as far as this definition is 8 concerned?
9 Is that a no solo then?
10 MR. BOGER: Have one in Unit 1 and one in Unit 27 11 I think there also must be a senior operator in that control 12 room.
7s 13 MR. MICHELSON: At all times, so there's always V 14 at least three in the control room anyway. Okay.
15 .
Now the second question was, how does a medical i
16 practitioner decide, in looking at the criteria, it wasn't 17 clear to me how you decide that this is a medical problem 18 that could possibly affect safety?
19 MS. SHANKMAN: The ANSI standard has a 20 delineation of that issue.
21 MR. MICHELSON: I see. I didn' t read it. It 22 identifies how you decide if this medical disability is a 23 potential jeopardy to safety?
24 MR. WARD: It has some criteria.
("1 25 MR. MICHELSON: I see. It's still always bothers
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0160 01 10 192 1 DAVbw 1 me, you know, how you decide if a person has fainting m
2 spells, is that a safety problem? Well, it might be if he 3 slumps over the control board in the process, and there's 4 only two in the control room, and he sets off the relief 5 valves, and so on.
6 The second operator is going to be mighty busy 7 taking care of the situation and not taking care of him, if 8 there's only two in the control room. That's a busy time 9 for one person to handle. Generally, you go through your 10 drills, I think, with two people in situations like that.
11 Now you're down to a one-person drill.
12 Have you ever performed a one-person drill like s 13 that, to see if one is enough?
14 MS. SHANKMAN: The ANSI standard talks about 15 basic requirements and talks about what kind of conditions 16 would be disqualifying. It also sets standards for 17 cardiovascular functioning and different neurology, 18 respiratory --
19 MR. MICHELSON: Just as a simple example, the 20 fainting spells. Does this qualify you, or do you have to 21 have a no solo situation?
22 MS. SHANKMAN: I would think the cause of the l 23 fainting spells and what the doctor found in the medical 1
24 examination and whether they felt they were going to occur
{} 25 and that they couldn't be controlled.
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0160 01 11 193 2 DAVbw 1 MR. MICHELSON: Yes, but does the doctor
'/ 2 understand what a fainting spell can mean at a nuclear power 3 plant, as opposed to what it means to a person walking down 4 the street?
5 MS. SHANKMAN: The standards suggest that the job 6 duties be included in the information sent to the doctor.
7 MR. MICHELSON: Of course, I don't doubt that he 8 would be qualified to judge the effect on safety, but 9 somebody ought to, unless he's well-qualified himself, which 10 I think would be rare for a physician, 11 MS. SHANKMAN: Would you like to look at the 12 standard?
('S 13 (Document handed to Mr. Michelson.)
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14 MR. WARD: Do you know what the FAA requires of 15 airline pilots, for example, in this area?
16 MS. SHANKMAN: I don't know their exact 17 standards. I think they're similar, looking at conditions 18 that would cause operational errors, and I think they have 19 the same concern, sudden loss of consciousness, inability to 20 make judgments, inability to function, and I would think 21 that they might have some different issues, because you 22 might be concerned with conditions that were 23 pressure-related, that we might not be concerned with.
24 MR. WARD: But I guess a general physician would
(} 25 have a better idea of the risk involved.
I'm getting to ACE-FEDERAL REPORTERS, INC.
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01'60 01 12 194 1 DAVbw 1 Carl's point. The risk there would be more obvious. If a
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2 physician were there, a physician might not understand the 3 risk involved in a nuclear power plant.
4 What sort of physicians do this, do utilities 5 hae?
0 MS. SHANKMAN: I think most of them have doctors 7 that routinely examine their staff. Some of them have 8 doctors that are part of their corporate organizations, the 9 larger utilities.
10 MR. WARD: Does the NRC audit this sort of thing?
11 MS. SHANKMAN: Well, right now, the doctor 12 directly sends the 386 to us with the medical information, s 13 and we send this out to our own physicians that are U 14 consultants to each of the regional offices. Each region 15 has their own medical consultant. We used to have one at 16 headquarters.
17 MR. WARD: So you audit the record or the 18 documentation that way; is that it? Is that what you're 19 saying?
20 MS. SHANKMAN: Our doctor then agrees that the 21 medical report meets the standard. This is basically what 22 we're trying to change under the new rule, which is to stop 23 having every single medical evaluation made by another 24 licensed medical practitioner evaluated and only have t; 25 unusual cases. The ANSI standard, the ANS standard seems V
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0160 01 13 195 DAVbw 1 to be clear enough about what thresholds are required, in 2 terms of functioning medical condition, if you will, and it 3 seems that we didn't need to evaluate.
l l
4 I think one of the things that is happening to 5 back up a little bit is, that where the candidate met the 6 standard, it became a paperwork issue, whether it was sent 7 in on time, documented, whether every line that was supposed 8 to be filled out was filled out, and we spent a lot of time 9 sending people back and forth between one doctor and 10 another.
11 And when it was over, there was really no 12 disagreement about the medical condition, but it was more
(~) 13 documented.
%j 14 This changes the emphasis of who's responsible 15 for that documentation. -
16 Now the facility has to send the certification to 17 us, saying that they're satisfied that this exam has been 18, done, based on this ANS standard and that the candidate 19 meets the standard.
20 21 22 23 24
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(,_) 25 ACE-FEDERAL REPORTERS, INC.
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0160 02 01 196 1 DAVbur 1 DR. REMICK: The physician also has to fill out a l
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I\ ') 2 form, doesn't he, that is returned to the facility and is 3 kept as a scord?
4 MS. SHANKMAN: Yes. But it would be their 5 documentation, not ours.
6 So they are required by us now to be sure that 7 their operator or applicant is satisfactorily examined, and 8 if there is a problem, then we hold them responsible.
9 In the past it was really the medical 10 practitioner that was held responsible, and it is very 11 difficult for NRC to find a medical practitioner or go to 12 the licensing board of the state. We just don't do it.
13 DR. REMICK: But isn' t it a case the operator k_s) 14 goes to the MD, the MD says you are fine, and he goes back 15 to the facility and says he is fine?
16 So if there are conditions that the doctor might 17 find, they should be documented on that form, and the 18 facility should be aware of it?
19 MS. SHANKMAN: What I was going to say is that 20 puts the facility in the loop. If the doctor says this 21 person has minor fainting spells, they could occur, but they 22 have medication that will control them some of the time.
23 The facility then would say that might cause an operational 24 error. You have their judgment in there, too, because they
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25 are certifying to us that the person's health is sufficient (v}
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0160 02 02 197 1 DAVbur 1 in terms of stability. if you will, and that it might not O 2 cause an operational error.
3 So we have added their judgment of how they 4 operate as a nuclear power plant to the opinion of the 5 doctor.
6 I think that also means that the dialogue is 7 between the facility and us with medical consultants rather 8 than the medical persons making the judgment about the 9 operational issue.
10 MR. WARD: Carl, I don't know if you heard that, 11 Does that make you feel better?
12 MR. MICHELSON: No, it doesn't make me feel any
(' 13 better because nowhere in the standard, for example, do we
\_/
14 find any discussion of the fact that you don't consider what 15 the operator may do in the process of experiencing his 16 difficulty, such as fainting over the control board, and so 17 forth. That is really not apparently a required 18, evaluation.
19 It is one thing to evaluate the effect on the 20 control room and plant to have faints in the middle of the 21 floor and nothing happens and the plant goes on its merry 22 way.
23 It is another thing if he faints over the control 24 board and sets off a relief valve and this or that. The 25 operator is going to be mighty busy.
(})
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0160 02 03 198 1 DAVbur 1 MR. WARD: A common cause?
\/ 2 MR. MICHELSON: Yes, it is a common cause really, 3 and I don't find that as any requirement in the regulatory 4 guide. I couldn't even find guidance to tell me that that 5 is something you ought to look at.
6 MS. SHANKMAN: So you think we should add that to 7 the regulatory guide?
8 MR. MICHELSON: I think you ought to think about 9 it and tell me why it isn't necessary.
10 MS. SHANKMAN: Okay.
11 MR. MICHELSON: It is all precipitated, of 12 course, by this little belt buckle incident the other day, 13 where a fellow just leaned over the control board. That is
(-)S 14 not that uncommon.
15 Another problem is people carrying coffee cups 16 around and accidentally spilling them on the control boards, l
17 and so forth.
I 18l There are various ways things can go wrong.
19 MR. WARD: Ten years ago, of course, a plant had 20 a serious incident when somebody leaned over and 21 accidentally opened a valve, a drain valve.
22 MR. MICHELSON: So it is not an incredible 23 scenario, I don't believe.
24 Now, whether that could occur concurrently with
{'; 25 fainting, well, that depends. I see people who have ACE-FEDERAL REPORTERS, INC.
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0160 02 04 199 1 DAVbur 1 fainting problems. They reach up high or something, and n
kJ 2 they faint. Or if you are reaching out over the board, 3 maybe that precipitates a fainting spell.
4 So I don't think it is just looking for a witch 5 somewhere.
6 MS. SHANKMAN: I understand.
7 In answer to your question before, the phrasing 8 in the standard says that the ANS standard prescribes 9 minimum requirements necessary to determine that the medical 10 condition and general health of nuclear reactor operators 11 will not cause operational errors.
12 It doesn't confine it to the control room.
7- 13 With reference to solo operation, it is to V
14l specify in the ANS standard, which talks about if the l
15 condition is not one in which you should operate alone, that 16 another qualified person should be there.
17 We are just saying that a qualified person for us 18 means licensed.
19 MR. MICHELSON: I am only saying that in 20 evaluating whether or not this is acceptable you have to 21 consider what the person that experiences the medical 22 dif ficulty might do that might make the operator pretty 23 busy.
24 MS. SHANKMAN: I VMerstand.
{} 25 MR. WARD: She was going back to the earlier l
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2 DR. REMICK: What is the most frequent reason for 3 conditioning the license?
4 Color blindness is one, I guess.
5 MS. SHANKMAN: Corrective lenses, which on the 6 new form -- that is just a gimmick, no offense -- it means 7 you can just check a box that says "needs corrective lenses" 8 when operating or in a licensed position. I forget the 9 phrasing.
10 But I think blood pressure is a very common one.
11 DR. REMICK: That would be a common one.
12 Where do you draw the line? Who makes the r3 13 decision on high blood pressure, where you draw the line U
14l that a person should not be licensed even if you have a 15' no-solo condition?
16 MR. BOGER: I think that is in the standard.
17 MS. SHANKMAN: And then if you don't need that, 18 the examining doctor will suggest, yes, they don't need it, 19 but they are taking this medication these many times a day.
20 And we often require them to be tested and the 21 results sent to us on a periodic basis. So we don't just 22 say, well, it is a condi . ion and then leave it alone. We 23 'ask for follow-up information to be sent in.
24 MR. WARD: What fraction -- what is a ballpark
(; 25 estimate for the fraction of licensed operators that have a K._)
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0160 02 06 201 1 DAVbur 1 no-solo restriction -- 1 percent, 10 percent?
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2 MS. SHANKMAN: It is not 1 percent.
3 MR. WARD: It is more than that?
4 MS. SHANKMAN: Yes.
5 Bruce, do you know?
6 MR. BOGER: I don't have a number for that.
7 MS. SHANKMANr I want to volunteer and say we 8 will get the information out of our operator license 9 tracking system. We can get an estimate because we do have 10 on there --
11 MR. WARD: Well, that is all. I mean, is this 12 some obscure, esoteric problem, or is it very real?
gm 13 MS. SHANKMAN: The medical condition license --
V 14 the problem is -- included in that system is corrective 15 lenses, and that is such a common one. So the answer is 16 that of course it is greater than 1 percent.
17 Now, you are asking about those conditions 18 greater than corrective lenses.
19 MR. WARD: But the corrective lense thing doesn't 20 get into the no-solo thing, does it? It doesn't get 21 involved?
22 MS. SHANKMAN: No, but what I am saying is in our l 23 system all we have is information about whether it is 24 medically conditioned or not.
/"N 25 MR. WARD: So a lot of them would be, okay. So U
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i I
0160 02 07 202 l DAVbur 1 you can get that? ,
2 MS. SHANKMAN: I can give you that, and then you 3 could imply from that how many of those would be greater 4 than corrective lenses. Other than that, it wouldn't be a 5 computerized count.
6 MR. WARD: You see, I guess what is bothering me 7 is whether this is really -- if it is necessary to have this 8 sort of restriction. It doesn't sound like it is a very 9 practical thing to do.
10 Does that mean -- first of all, it wouldn't apply 11 to auxiliary operators at all. This is just licensed 12 operators.
(~) 13 But I don't know, thinking about a reactor V
14 operator, shift supervisor functions in the plant, are they 15 likely to be off in the plant in the auxiliary building 16 somewhere performing some critical function on their own?
17 You don't think so?
18 MR. MICHELSON: It depends on what you call 19 critical.
20 MR. WYLIE: You have got more problems with 21 maintenance than you do with the operztors.
22 DR. REMICK: I can see where you could have 23 somebody certainly licensed on the refueling bridge, the 24 spent fuel pool, and you certainly might want to consider I'v ) 25 whether that person, if he is one that might be one subject ACE-FEDERAL REPORTERS, INC.
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0160 02 08 203 DAVbur 1 to occasional fainting, you would want that person to be 2 there. That might be more for safety, but they could be 3 moving fuel at the time in the refueling machine.
4 Not a major type of incident, but I think there 5 are certain times, and you would want to know that that 6 person had certain restrictions. You might not want that 7 person to be there and not have him perform that function.
8 I know of no case -- does anybody -- of an 9 operator so conditioned to fainting through the years that 10 this has existed. I am not aware of any incident that has 11 occurred. That is not to say they won't occur.
12 MR. WYLIE: But there are sure plenty of 13 incidents where maintenance personnel, painters and 14 sweepers, you name it, have caused problems.
15 MR. WARD: Because of fainting?
16 MR. WYLIE: No, but for other reasons, 17 cccidents.
18 DR. REMICK: I think you have to look at the 19 alternative. One thing would be to say, well, these people 20 shouldn't be licensed, but then in many cases they represent 21 a lot of experience.
22 MS. SHANKMAN: They are well-trained, and 23 they have --
24 MR. WARD: I guess the alternative is to just be
() 25 realistic. If a person has some condition, you know, that ACE-FEDERAL REPORTERS, INC.
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0160 02 09 204 1 DAVbur 1 is reasonably well-controlled and can function normally, O 2 then you just forget about it. But if it is a person who 3 really has fainting spells or something, then they probably 4 shouldn't be licensed at all.
5 DR. REMICK: Not if he has, but suppose he has 6 had, for some reason he has had them. He is taken off duty, 7 he comes back six months later, and it looks like they found 8 the problem and it is corrected. Chances are you are still 9 going to want to have maybe that person observed for some 10 period off duty, and you might want to condition it for a 11 while.
12 But that doesn't say that maybe he isn't healthy
(', 13 and can perform his job.
%J 14 I guess the alternative is saying people should 15 not be licensed. That worries me. I don't have any problem 16 if it is a severe case and the guy is routinely fainting. I 17 don't think he should be licensed.
18I MR. WYLIE: I guess as a matter of definition I 19 ask what is severe? There has to be some criterion.
20 I know of cases where people do have diabetes and 21 severe difficulty of control, and they are subject to 22 seizures. I would be concerned that that person that has a 23 severe case and is subject to seizures --
24 DR. REMICK: I don't think he would be licensed.
( ]; 25 I really don't think he would pass. That is my impression ACE-FEDERAL REPORTERS, INC.
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l
\
0160 02 10 205 DAVbur 1 from the past anyhow. He would not be licensed.
2 MR. WARD: It sort of seems to me this gray area 3 doesn' t make sense. There ought to be just black and white 4 decisions. But I don't know.
5 MS. SHANKMAN: I think the reason that we don't 6 just flat out say diabetes disqualifies you is because there 7 is that range, and there is dif ferent medical treatment for 8 different conditions, also new medical treatments to come 9 over time. So you can't in the abstract decide that a 10 condition is going to always disqualify.
11 MR. WARD: I don't think Charlie meant that 12 anyone with diabetes would be disqualified, but someone who
(~3 13 has the disease and it is very difficult to control and is U-14 experiencing, routinely experiencing problems. That person 15 ;
should be disqualified and not just given a condition on his 16 license.
17 MS. SHANKMAN: Since the NRC doctor consultant 18 reviews the evidence -- we just don't base it on the 19 examining physician -- they would have to send in supporting 20 evidence.
21 My understanding since I have been involved in 22 any of these is that often there is a lot of correspondence 23 back and forth from one doctor to another supporting their 24 request, and it isn't uncommon for it to be denied.
Where do you draw the line on f)
J 25 MR. MICHELSON:
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0160 02 11 206 1 DAVbur 1 people who have lost fingers or hands or arms? At what O 2 point is he considered not qualified to operate anymore?
3 Has there any thought been given?
4 You know, an operator may lose a finger at home 5 fiddling around in his workshop. Ia he now disqualified 6 from his job?
7 MR. BOGER: I think the standard addresses that 8 and considers whether somebody is able to manipulate the 9 controls.
10 MR. MICHELSON: So they test him in what he is 11 expected to do, and as long as he is able to perform it that 12 is acceptable?
MR. BOGER:
/3 13 Right.
V 14 MR. MICHELSON: There must be a limit, though.
15 Let's say I only have one hand or one eye, perfectly 16 correctable, no blindness or anything, just one eye.
17 Does that disqualify you?
18 MR. BOGER: I think that the only time that one 19 eye has really become an issue is in a fuel pool where you 20 had to judge depth. But typically one eye is not a 21 disqualifier.
22 MR. MICHELSON: In the control room it would 23 still be acceptable?
24 MR. BOGER: As far as I know.
f'j'; 25 DR. REMICK: But color blindness could disqualify g
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0160 02 12 207
} DAVbur 1 you if in that control room you needed to distinguish color e s
~
2 to operate, but if you did not need to distinguish color 3 then you could be color blind, is that correct?
4 MS. SHANKMAN: Color blindness is definitely one 5 of the items that is in the standard.
6 DR. REMICK: But it is dependent on whether that 7 can get you in trouble or not?
8 MR. BOGER: If he can't tell red from green, for 9 instance, that would be a problem that would disqualify 10 someono.
11 MR. MICHELSON: I guess you are saying a 12 one-handed operator could possibly be licensed?
13 MR. BOGER: I can only think of one time in the 14 control where an operator actually needs two hands.
15 MR. MICHELSON: There are indeed accidents where 16 you are supposed to use two hands at once. Would that 17 disqualify one?
18 DR. REMICK: I think if in that plant you needed 19 to do two things, I guess so.
20 MR. MICHELSON: Generally, those things are not 21 safety related. Generally, those are things you try to make 22 sure he doesn' t do accidentally.
23 MS. SHANKMAN: I think medical conditions 24 overall, not only in this industry, are more and more
/') 25 evaluated on whether you can perform the job.
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0160 02 13 208
,1 DAVbur 1 MR. MICHELSON: That should be the criterion of L' # 2 course.
3 MS. SHANKMAN: People do things that you might 4 not think they could, given their physical limitations. It 5 is whether they can do it, and it is an evaluation by the 6 plant as well as the medical practitioner.
7 MR. MICHELSON: It is entirely possible that what 8 with all the operators we have in the country somebody is 9 going to lose a hand or an arm in an accident.
10 DR. REMICK: See, the BWR is boron injected. You 11 have to do two things at once.
12 MR. MICHELSON: That is right.
13 MR. WARD: Wouldn' t red-green color blindness --
f3
\_)
14 isn't that the most common kind? Wouldn't that ba important 15 in any control room in the country?
16 MS. SHANKMAN: Yes.
17 MR. WARD: So we wouldn' t expect to find a 18 red-green color blind operator with a license anywhere in 19 the country?
20 MR. BOGER: That is correct.
21 MS. SHANKMAN: You wouldn' t expect it. I 22 wouldn't swear that that couldn't possibly happen.
23 MR. WARD: Well, the intent of your regulations 24 would be to preclude that?
/'T 25 MR. BOGER: Right. I am one of the ones that has b
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0160 02 14 209 DAvbur 1 a color blindness, and when I got my license -- basically, 2 when I fail the first test, they bring out the red pencil 3 and the green pencil and make sure you can tell the 4 difference between those.
5 First, you go through the subtle, and then they 6 go to where you really can't tell red from green. That is 7 one of the checks, and definitely that is required.
8 MR. GIMMY: I might bring up one other thing.
9 With all these physical limitations and one hand and one 10 finger, and so forth, that we are talking about, certainly a 11 more prevalent problem in older plants like Savannah River, 12 where at one time the average age of the operators was about
(~'T 13 53, or something like that --
's..)
14 MR. WARD: That is not so old.
15 MR. GIMMY: There is this topic that came up 16 yesterday about fitness for duty. You know, we never did 17 resolve that, but Charlie and I talked about it, and every 18 plant operator manager makes the decision quite often on 19 every shift as to whether or not you are fit for duty or 20 not, and as they get older and they get into more problems, 21 more financial problems, more alcohol problems, more 22 illnesses, really severe illnesses, not disabling, not 23 losing a finger but limping and not able to climb stairs and 24 things like this, and this fitness for duty thing comes up l (;
x_-
25 all the time.
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0160 02 15 210
- 1. DAVbur 1 Yesterday we were talking about this thing, where U 2 they should notify NRC if they think he has a thing that 3 might af fect his performance.
4 Well, there is a clear-cut decision made on that 5 on every shift, and it comes up all the time. Somebody 6 comes in and they say, you are not fit for duty, go home.
7 That leads to disciplinary action and stuff later, but when 8 they make that decision, I would contend there is a good 9 point to send your notification. That is black and white.
10 If you send him home, he is not fit for duty.
11 Every plant does this. Every plant has this 12 problem.
13 I am suggesting as commercial nuclear plants get 14 older and the operators get older you are going to get more 15 and more into this gray area, and the utility has to make 16 these decisions, sometimes on a day-to-day basis, and I know 17 they actually have trouble sometimes putting together a crew 18 that is fit enough to do the shutdown.
19 Fit enough. Not that they are drunk or anything 20 like that. But half of them can't climb the stairs, some of 21 them have high blood pressure and can't be on the scaffold.
22 Some of them have borderline emphysema from 30 years of 23 smoking and they look around and say, good night, we have 24 got 14 people here tonight and only two of them can do
() 25 anything.
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0160 02 16 211 DAVbur 1 You know, they can do paperwork. They can do 2 inventory balances. They can sit at a panel and run 3 pushbuttons. But they really can't go up and down stairs 4 and on scaffolds and stuff.
5 So this fitness for duty thing is much more than 6 these black and white things is. Does he have enough hands?
7 The utility makes these decisions, the company 8 makes these decisions all the time.
9 10 11 12 r~' , 13 V
14 15 16 17 18 19 20 21 22 23 24
()
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0160 03 01 212 DAVbur 1 MR. WARD: Thank you, Susan, Jerry.
2 The next topic is 1.149, the simulator.
3 (Slide.)
4 MR. WACHTEL: Good morning. I am Jerry Wachtel.
5 Reg Guide 1.149 is titled " Nuclear Power Plant 6 Simulation Facilities for Use in Operator License 7 Examinations," and although it is very similar in structure 8 and in approach to the version of the reg guide that was 9 issued in draf t form last year, there have been substantial 10 revisions to the document, based largely on public comment 11 and also upon the recently published version of the industry 12 standard that this reg guide endorses. That is ANS 3.5.
r~T 13 First, let me mention briefly about the standard V
14 itself.
15 The reg guide, when published as a draft, 16 endorsed the version of the standard that was current at 17 that time, which was dated 1981, although we knew when the 18 draft of the reg guide was published that a major revision 19 to the standard was underway, and in fact Bruce Boger served 20 on the committee that wrote the 1985 version of the 21 standard.
22 We were in a position when we issued the draft 23 reg guide of not being able to endorse the standard that we 24 knew was coming or even recognize it in our reg guide until
() 25 it was in fact a published document.
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0160 03 02 213 DAVbur 1 As you might expect, many of the public comments 2 we received to the reg guide were written by peoria who were 3 aware that the standard was undergoing revision, and we 4 received an awful lot of comments saying why don't you guys 5 just go ahead and endorse the new version of the standard?
6 Well, as timing would have it, the new version of 7 ANS 3.5 was published a month ago yesterday, October 25th, 8 and we have been over the last several months rewriting and 9 revising the reg guide to recognize the existence of the new 10 standard.
11 So the version of the reg guide that you see 12 before you as Enclosure E does in fact endorse the 1985
(~') 13 version of ANSI 3.5. ,
L,/
14 In our endorsement of the 1981 version of the 15 standard, we took certain exceptions to it, and we do 16 essentially the same thing in our endorsement of the 1985 17 standard, and I will explain the major exceptions that we 18 take to it in just a moment.
19 As I mentioned yesterday, the draft version of 20 the rule and the reg guide established a phased-in 21 implementation program of three years, which would give 22 everyone a three-year period essentially before they would 23 be required to have an acceptable simulation facility in 24 place ready for the conduct of operating tests.
(_)s 25 In response to public comments, particularly
(
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0160 03 03 214 1 DAVbur 1 about the length of time it takes to procure a full scope (1' 2 plant reference simulator, we have extended that three-year 3 period to be a four-year period.
4 The draft reg guide seemed to present one major 5 sore spot to the industry. That sore spot was that we 6 indicated as part of an acceptable program of performance 7 testing for a simulator or for a simulation facility that 8 the utility would have to be able to demonstrate the 9 fidelity of that simulation facility by conducting 10 performance tests essentially on every malfunction that the 11 simulation facility had been designed to perform.
12 The ANS 3.5 1981 standard requires a minimum of 13 75 malfunctions.
U<~s 14 It was our position that if a utility specified a 15 simulator with all the bells and whistles and it could 16 perform many more malfunctions, we believed that such 17 malfunctions should be testable and documented as to their 18 fidelity.
19 So we wrote the reg guide to indicate that every 20 malfunction would have to be tested. That, as I say caused 21 a lot of grief in the industry. They felt that unless we 22- could bound the number and the types of malfunction testing 23 that we had in mind, there were estimates that simulation 24 facilities could be tied up for weeks and weeks on end doing
() 25 nothing but satisfying the requirements of our rule and our ACE-FEDERAL REPORTERS, INC.
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0160 03 04 215 1 DAVbur 1 reg guide.
G 2 MR. WARD: That is because this was a periodic 3 test?
4 MR. WACHTEL: It was a periodic test, and it was 5 difficult to identify for any particular simulator just what 6 the extent of the malfunction test would have to be.
7 MR. MICHELSON: Was operator error included in 8 the nalfunction tests?
9 MR. WACHTEL: No. We are talking simply about 10 the physical simulator itself and what it was capable of 11 doing.
12 So essentially what we did in response to many 7w 13 comments about the limitations on performance testing V
14 malfunctions was that the staff, with the active 15 participation of our regional examination people, have 16 developed a list. It is a long list, but it is a 17 circumscribed list that is now includea in this final 18 version of the reg guide.
19 That list is separated by BWRs and PWRs, and it 20 is separated by abnormal and emergency types of events.
21 That now provides the bounding condition on what malfunction 22 testing we think needs to be performed.
23 If you want to have a look at the list, you will 24 find it in Enclosure E of your package on pages 5 through 8
/~) 25 of the reg guide.
C/
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0160 03 05 216
,1 DAVbur 1 One key aspect of the reg guide that is unchanged b 2 from the draft version that you saw a year or so ago is that 3 we provide guidelines for those utilities who intend to use 4 one simulator or one simulation facility at more than one 5 unit of a multi-unit plant.
6 These guidelines essentially parallel the 7 guidelines that are already in place in our examiner 8 standards for the issuance of multiple licenses at 9 multi-unit sites. The documentation of a simulator for use 10 at multi-unit sites are essentially the same.
11 MR. WARD: Jerry, are you going to talk about 12 that, the multi-unit sites?
13 MR. WACHTEL: No, I wasn't intending to.
14 MR. WARD: I guess I am having a little trouble 15 figuring out what the issue is there. My impression is that 16 the simulators that satisfy the requirements for all the 17 units on a multi-unit site -- I mean in those cases the 18 units are all really identical.
19 MR. WACHTEL: In the case where the units are I 20 identical or close to identical, then we fully expect that
! 21 one simulator will serve for all units.
22 MR. WARD: Browns Ferry or Palo Verde or 23 something?
24 MR. WACHTEL: There are some cases, I understand,
{} 25 where the units are not identical or in some cases where l
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l 0160 03 06 217 1 DAVbur 1 they are mirror images of one another in the control room.
O 2 And we are concerned. In fact, as you will see 3 in a moment, one of the exceptions that we take to the 4 standard is that when we define a reference plant for 5 purposes of a simulation facility, we are defining it down 6 to the unit level, not to the plant level, the purpose being 7 that in the event that there are multiple units and they are 8 not the same it will be the burden on the utility to 9 demonstrate to us that the differences between those units 10 are small enough that the one simulation facility can 11 adequately serve both or in fact all three.
12 There are other cases where we expect that more 13 than one utility will operate together to propose the use of 14 one simulator or one simulation facility for multiple sites 15 owned by more than one utility. There, too, even though 16 there may be remarkable similarities between the separate 17 plants or the separate units, we want to place the burden on 18 them to demonstrate that that simulation facility indeed is 19 a reference plant simulator for all the units that they 20 propose to use it again.
21 MR. WARD: Well, I can see this is going to get 22 kind of sticky. I mean, I guess there really are some 23 mirror image plant units, mirror image control rooms.
24 MR. WACHTEL: That is right.
() 25 MR. WARD: How are you going to deal with that?
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0160 03 07 218 1 DAVbur 1 MR. WACHTEL: We are in the process right now of 2 developing a methodology that will result in guidelines to 3 the NRC, under which we will go out and evaluate every 4 simulation facility. The same methodology that we will use 5 to perform the audits or performance tests, we will use to 6 be able to document when a particular simulation facility is 7 adequate to address more than one unit.
8 MR. WARD: That is how you are going to go about 9 it, but what is going to be the bottom line on a mirror 10 image plant?
11 MR. WACHTEL: I don't know the answer to that.
12 The clear -- the obvious answer is that wherever we give 13 multiple licenses now, we will obviously bless a 14 simulator. When one simulator is used for those plants if 15 we feel that the units are close enough that we can grant 16 multiple licenses to the operators, then obviously we are 17 satisfied with the training program and with the exams 18 conducted on the simulator now, and it would be foolish for 19 us to go out and require another simulator.
20 That is certain to be the case. Beyond that, 4
21 where we do not presently grant multiple licenses, we are 22 going to have to go and look at the simulator as it is 23 proposed for use.
24 MR. WARD: Okay. But are there plants now that
{} 25 have mirror image control rooms where you have multiple ACE-FEDERAL REPORTERS, INC.
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0160 03 08 219 DAvbur 1 licenses?
2 MR. WACHTEL: I would like to have Bruce address 3 that.
4 MR. BOGER: I think the closest one is Calvert 5 Cliffs. It has a mirror image control room.
6 The other --
7 MR. WARD: But tnere are some individuals who 8 hold a license on each of the units?
9 MR. BOGER: That is correct. At Calvert Cliffs 10 we issue multiple licenses. What we do in the examiner's 11 . standards is indicate to an operator that they take a 12 simulator exam on a simulator that is referenced to one 13 plant and that when we conduct the examinations we will (a')
14 emphasize the other plant in the oral portion, the 15 walk-through portion, to make sure that a candidate has an 16 understanding of both units.
17 MR. WARD: I guess there are some people in the 18 human factors community that think that mirror image plants 19 are terrible.
20 MR. WACHTEL: I am one of those.
21 MR. WARD: I don' t know enough to know whether it 22 is really a major problem or not. But I think what I am 23 hearing you say is you have already crossed the bridge in 24 operator licensing of saying it is not all that terrible a (y
r j 25 problem. So you are going to be consistent with that in the ACE-FEDERAL REPORTERS, INC.
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0160 03 09 220 DAVbur 1 simulator.
2 MR. WACHTEL: I think realistically that is the 3 only way we can proceed. Again, a simulation facility will 4 have to be documented to us.
5 In the case of an ANS 3.5 type simulator, it is 6 likely that the utility who wants to use it will certify to 7 the NRC that they have such an ANS 3.5 simulator that they 8 intend to use for operating tests and we will go ahead and 9 use that simulator.
10 There is still an area that we need to resolve if 11 they go ahead and certify to us that they intend to use that 12 simulator for multiple units when we know that those
(~} 13 multiple units are not identical.
LJ 14 MR. WARD: Yes, and that was the other question.
15 What about a plant like -- it doesn' t really matter --
16 Three Mile Island, I guess, similar units, but the controls 17; are very much different? There are other examples. How are l
18l you going to deal with that?
19 MR. WACHTEL: Bruce has a point to make here.
20 MR. BOGER: In the TMI case, we did not issue 21 dual licenses except to a few supervisors. So we treated 22 them as different units.
23 I think Beaver Valley may fall under that same 24 mistake, where you have a much older plant and a newer plant
()
v 25 on the same site, yet the control rooms in some of the plant i
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0160 03 10 221 DAVbur 1 systems are different.
2 MR. MICHELSON: How do you treat the use of the 3 B&W simulator, for instance, to train -- I think deaver 4 Valley operators are trained on the B&W simulator. There is 5 certainly not much similarity, is there, between the No. 2 6 control room?
7 DR. REMICK: Beaver Valley now has its own 8 simulator.
9 MR. MICHELSON: I think it is three years off, or 10 something.
11 DR. REMICK: No, it is functional.
12 MR. MICHELSON: Okay.
(~) 13 MR. WACHTEL: Yes, it is operational now.
w-14 MR. WARD: Is there a simulator for just one of 15 the units?
16 MR. MICHELSON: Oh, yes, probably Unit 2 at 17 Beaver Valley.
18 MR. WYLIE: The Beaver Valley simulator is for 19 Unit 1, but they have got a mockup Unit 2.
20 MR. WACHTEL: There is an example of where the 21 rules, as we are drafting them, may come into effect. When 22 we talk about simulation facilities, we are talking about 23 one category of simulators, which we will call the ANS 3.5 24 type plant reference, high fidelity simulators. There is a
() 25 whole host of othe:: simulation devices out there, part task ACE-FEDERAL REPORTERS, INC.
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0160 03 11 222 1 DAVbur 1 simulators, concept trainers, engineering trainers, mockups,
(/I
-2 and the like, that could well be proposed in some 3 combination by those plants that either don't have a full 4 scope ANS 3.5 simulator or will need to use a 3.5 simulator 5 in combination with something else to make up for the 6 differences between the control rooms simulated by that 3.5 7 simulator and the other control room that is not represented 8 by that simulator.
9 That may be a case where a plant like Beaver 10 Valley could come along and propose that to us in lieu of 11 getting two separate $10 million full-scope simulators.
12 MR. GIMMY: I would like to make a point on two 13 items.
f-)
\~)
14 One of them is how close is close enough to be 15 identical? Even plants where they try to make them 16 identical, they never come out 100 percent. They are 98, 17 97, and so forth percent.
18 One way to do that -- we have just been looking 19 at this because we have four reactors that are almost-20 identical. We are trying to do it with one simulator -- one i
21 way to do it is with an IO count.
22 Once you get the simulator, you do have a count
- 23 of all the inputs and outputs and the control room switches, l
24 bells, whistles, meters, and so forth, and you can come up
(} 25 with a number. You can say 75 percent of the IO is 4
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0160 03 12 223 1 equivalent with that reactor or is identical to that 7-)DAVbur
\_/
2 reactor; 25 percent is different; or 80 percent is the same 3 or something. And this gives you a line that you can draw.
4 or you could draw a finer line, but it takes more of a task 5 analysis, the frequently used controls.
6 But that is kind of dangerous because it is the 7 emergency ones you wanted to go to.
8 But one way to do it is on an IO count basis.
9 You can say this simulator on the input / output devices on 10 the panel is 73 percent identical to that one, and you can 11 draw some line. Like it is below 60 percent or below 70 12 percent. It is not good enough.
(~ 13 The second point I want to make is on mirror b}
14 images. There are mirror images and mirror images. One 15 kind is the most common kind, where they mirror image the 16 location, the panels.
17 But, for instance, once you get in front of the 18 ECS panel, whether it is this one or it is mirror image, 19 once you find it, when you approach it to where it controls, 20 the controls still read from left to right, and it looks 21 just like the other one, and it is no problem using it. You 22 can argue that it might five seconds longer to find it.
23 MR. WARD: It is just the location of the control 24 room?
1 () 25 MR. GIMMY: But I know of no control room -- I
\
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0160 03 13 224 1 DAVbur 1 may be wrong in this -- but I know of none which is a true 9 2 mirror image, where buttons that went left to right over hre 3 end up going right to left over there.
4 Do you see what I am saying?
5 The panels may be laid out like that, but once 6 you find the pane.1 it looks the same and should be no 7 trouble using it. The A pump is still on the left, and the 8 B pump is next to the C pump.
9 I don't know any that go totally --
10 MR. WARD: Jerry, have you looked at that?
11 MR. WACHTEL: We haven' t gotten to the point of 12 looking at that yet. It may be that our Human Factors
(-)
V' 13 Engineering Branch or former Human Factors Engineering 14 Branch would pick that up in their detailed control room 15 design reviews, and that is the sort of thing that would i
16l filter back to us.
17 But I don't know offhand of any. I suspect we 18 will start to get into those questions when we begin to look 19 at the certifications that start coming in in response to 20 the rulemaking.
21 Since there have been several questions about how 22 we intend to go about and study these simulators and how we 23 answer the question of how close is close enough, I will 24 spend a couple of minutes telling you about the contract
(')
a 25 that we have underway right now to try to put in place the ACE FEDERAL REPORTERS, INC.
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0160 03 14 225 1 DAVbur 1 answers to those questions and the program we will put into
/3 U 2 place at the completion of the contract.
3 4
5 6
7 8
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I 0160 04 01 226 1 DAV/bc 1 (Slide.)
2 Let me tell you now about the major exceptions 3 that Regulatory Guide 1149 takes to the ANSI 3.5 Standard.
4 The majority of the exceptions we take continue unchanged 5 from the 1981 version of the Standard, which was endorsed by 6 the draft regulatory guide.
7 The key exceptions are, number one, that the 8 rule, and, therefore, the regulatory guide which supports 9 the rule, applies to operating tests and not to training.
10 So, although it is a training standard, it is endorsed as it 11 applies to the conduct of operating tests.
12 secondly, as we were discussing a few moments 13 ago, although the standard itself is intended to apply only 14 to full scope simulators, because of our use of the term, 15 simulation facility, and our encouragement of those 16 facilities who might otherwise seek an outright exemption to 17 our rules to find some way to provide some simulator 18 capability, we are endorsing the standard also with regard 19 to simulation devices other than strictly full scope, high 20 f delity simulators, including the part task and limited 21 scope devices.
22 MR. WARD: But you could include in that the 23 older simulators that had perhaps been in the earlier ANSI 24 guide?
(} 25 MR. WACHTEL: That's right. A simulator that ACE-FEDERAL REPORTERS, INC.
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0160 04 02 227 1 DAV/bc A might have been in an earlier version of the ANS standard, O 2 the 1981 version, or I guess there was a 1978 version prior 3 to that, might very well not be in the 1985 version. And it 4 might be very time-consuming and costly to bring those 5 simulators up to date.
6 So they might fit into a category of something 7 other than an ANS 3.5 simulator today.
8 Next, the definition of " reference plant", as I 9 mentioned a moment ago, applies down to the unit level. To 10 address the question of those units in which there are 11 obvious differences, next, in the 1981 version of the 12 standard, there was one appendix.
C/
') 13 That appendix dealt with a discussion of how to 14 conduct performance tests to document the capability of the 15 simulator.
16 In the 1985 version of the standard, there are 17 two appendices. The first is essentially a continuation of 18l' the performance test appendix. The second one is an 19 appendix that deals with operability testing. That is 20 essentially a series of tests that exercise key components 21 of the simulator under both normal and transient conditions, 22 essentially to give people a warm feeling that the simulator 23 is capable of performing its task.
24 Basically, although we call it an exception, we 25 are endorsing both appendices to the standard and
(])
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l 0160 04 03 228 1 DAV/bc 1 considering them to be part of the standard. In the
-3 1_J 2 standard itself, they are considered optional. By our 3 endorsement, we are making them part of the standard itself.
4 MR..GIMMY: Are you also endorsing the part of 5 the standard that says the plant reference simulator has to 6 keep up to date with the plant, within a one-year -- I 7 believe it's a one-year window, isn't it? I forgot the 8 exact time intervals.
9 There's a thing in there about keeping it. If 10 you backfit the plant, you've got to backfit the simulator 11 quickly.
lL MR. BOGER: I think, in general, what the s 13 standard says is that you have about a year to identify
)
14 those changes. Then you have another year to actually 15 implement the changes.
16 MR. GIMMY: What if you have a multi-unit thing?
17 What if you have a three-unit plant? Or, in our case, a 18 four-unit plant? You can't backfit all four of them at 19 once. You have too many maintenance people. So you backfit 20 them one at a time and then get it half done.
21 What should the simulator be? Should it be like 22 the backfitted ones, or like the other half? I don't know.
23 That's a problem.
24 But, let me ask my blockbuster question. Having 25 studied this thing, simulators are my thing. And having
(~)
V ACE-FEDERAL REPORTERS, INC.
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0160 04 04 229 1 DAV/bc 1 studied your writeup, here's my question. I worked and 2 worked at wording this. Why would anyone call their 3 simulator a plant reference when they could just as well 4 call it a simulation facility and get a lot less flack?
5 In other words, let's say I had a perfect plant 6 reference simulator, but rather than go through all these 7 tests every year to meet all these requirements and all the 8 stuff to update it for every little piping change, and all 9 the fidelity tests, and so forth, why wouldn't I just call 10 it...well, this really isn't plant reference. This is a 11 partial core simulator. Even though I know in my heart it's 12 the other, because then I have a whole lot less paperwork to
,,, 13 do.
'~~'
14 It seems to me that that's a loophole in your 15 thing.
16 MR. WACHTEL: I think our intent is just the 17 opposite. If you look at the wording of Part 55 from the 18 draft version to the present version, we have made some 19 substartial changes to it, specifically to make it easier to 20 certify a plant reference simulator than would be the case 21 if you called it something else.
22 MR. GIMMY: Don't you have two sets of rules?
23 One for plant reference and one for the simulators for the 24 facility?
25 MR. WACHTEL: And the rules for the plant r'S V
l I
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0160 04 05 230 7 gDAV/bc 1 reference are, in our opinion, substantially simpler and I
v' 2 easier. While you still have to go ahead and document 3 performance tests, in a plant reference simulator, you can 4 send us one piece of paper which says that:
5 I certify this is a plant reference simulator.
6 And if you're telling us the truth, that's the end of it.
7 You are now able to conduct tests on that simulator as long 8 as you document the performance testing of it.
9 If you have something other than a plant 10 reference simulator, or if you call a plant reference 11 simulator something other than a plant reference simulator, 12 before you can even use it for testing, you have to go 3 13 through a long, fairly tedious process of applying to the
(~J w
14 NRC for our blessing to enable you to use it. You've got to 15 document all the performance tests as you would in the case 16 of the plant reference simulator.
17 But you also have to present to us an elaborate 18 justification for how it modelo the plant. In those cases 19 where it doesn' t model the plant, what you propose to use as 20 part of your simulation facility to achieve that, and we 21 have to come out and approve the thing and approve the 22 application before you can use it.
23 So we have written two parallel courses here and 24 it was our intent, and I hope we have succeeded to make it
() 25 far easier t'o go through the plant reference cimulator ACE-FEDERAL REPORTERS, INC.
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0160 04 06 231 1 DAV/bc 1 route.
)
/
2 We haven't made it any more difficult than in the 3 draft rules to go through the nonplant reference simulator 4 route, but we've made the plant reference much easier.
5 MR. GIMMY: Certainly, you want the people who 6 have gone to the trouble to get a plant reference simulator 7 to call it that, and who have abided by the rules of ANSI 8 3.5. But, ANSI 3.5, for multi-plant units and such is not 9 easy to live up to. There's a lot of work there to backfit 10 it.
11 You know, backfitting the plant maans we decide 12 to put cross-ties between A-header and B-header. And this e3 13 is a piece of pipe with a couple of flanges. To try and put i
14 that in a simulator is not so easy because now you have a 15 whole different hydraulic model for the system. You have 16 backflow through the cross-tie entering in either 17 direction. And it might be much harder to model that sucker 18 I than it was to put the pipe in.
19 MR. WARD: It's sad that people with the 3.5 will 20 have more work to do back at the plant, might be bothered 21 less by the NRC.
22 MR. GIMMY: That's what he was saying.
23 MR. WARD: That's called " regulation by 24 bitchiness".
25 (Laughter.)
(~')
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0160 04 07 232 DAV/bc 1 MR. GIMMY: It looked to me like they were trying 2 to make it easier to meet the plant reference thing. You 3 wish everybody had a good plant reference one and that they 4 kept it up to date. You have to accommodate those that are 5 only partial simulatoro.
6 But the point I was making is you don't want to 7 have a loophole where it's easier to call it a partial thing 8 and have everybody taking their good ones and calling them 9 partial ones just so they don't have to do paperwork.
10 MR. WARD: That's a good point.
11 MR. WACHTEL: I agree with that. We certainly 12 did not intend to make it easier to claim or, in fact, to 13 have a partial thing. In fact, that's one of the reasons
{])
14 why we take exception up here and say that parts task and 15 limited scope simulators are included in the 3.5 standard, 16 or in our endorsement of it.
17 MR. GIMMY: Perhaps this backfitting, ANSI 3.5, 18 doesn't really give you any room at all. It says you've got 19 to backfit it to be like the plant in one year, period.
20 Well, gee whiz, they're never like the plant. The minute 21 you finish it, it's probably 98 percent of what the plant 22 is. And I again would recommend a numerical thing there, 23 something like you've got to backfit.
24 In other words, when you fuss at them, when the
(,) 25 backfitting gets to where it's only 85 percent of the ACE FEDERAL REPORTERS, INC.
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-~
0160 04 08 233 1 DAV/bc 1 IO count or 90 percent or something, it's never 100. We're
()
\~ 2 having a simulator built right now by Singer-Link and, 3 because of the design freeze, you have to put changes in so 4 they can build it. And it's already dropped from 100 5 percent to where 1 3 16 percent like the reactor by the 6 time we get it.
7 It's probably going to be 94 percent like the 8 reactor.
9 MR. MICHELSON: It's also important that the 10 truly safety significant aspects be backfitted immediately; 11 the lesser ones can be done much later. I would only apply 12 your percentage to the lesser ones, certainly not to the key 13 safety.
(J) s.
14 If you had a key safety switch to your plant, it 4
15 had better be on the simulator right away.
16 MR. WARD: But you still can't do it instantly.
17 MR. MICHELSON: By right away, I mean you don't 18 wait around. And as long as it's in the 90 percent rule, 19 you don't fiddle with it. You fix that one right away.
20 MR. WARD: But, for e>:a".ple, at a plant where 21 there are multiple units and you're doing something like 22 that, you might phase even important changes like that in 23 each of the three units over a year or so.
24 MR. MICHELSON: That is a different problem.
(} 25 MR. WARD: Then what do you do to the simulator?
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0160 04 09 234 DAV/bc 1 MR. GIMMY: That's another problem.
2 MR. MICHELSON: That's different.
3 MR. WARD: Jerry, what have you done here about 4 the big gripe, about testing malfunctions?
5 MR. WACHTEL: If you take a look at the package 6 that was handed out, Enclosure E, I believe it is, pages 5 7 through 8, that is Reg Guide 1.149. That should be in 8 there.
9 DR. REMICK: Are you sure it's not attached in F?
10 MR. WACHTEL: I didn't assemble the package. It 11 should be in the middle of it there. If not, I'll get some 12 copies right now.
13 DR. REMICK: Is it the one entitled " Simulation
}
14 Facility"?
15 MR. WYLIE: It's Enclosure J.
16 MR. GIMMY: The very last thir, in the book.
17; MR. WACHTEL: Sorry about that. It's Enclosure E 18 in mine.
19 DR. REMICK: Are you talking about the guide?
20 MR. WACHTEL: The reg guide itself.
21 MR. WARD: What pages, Jerry?
22 MR. WACHTEL: Pages 5 through 8 of the reg 23 guide. You'll notice item number 12 begins a long, 24 three-page listing of events that we now consider to be the (o) 25 performance testing basis for documenting simulator ACE-FEDERAL REPORTERS, INC.
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0160 04 10 235 1 DAV/bc 1 performance.
! )
2 I suspect that people can question any one or any 3 of a number of those. They were developed by the staff with 4 our regional support with INPO participation. Obviously, 5 they would only be necessary to be performed to the extent 6 that they apply to the particular facility or to the 7 particular simulation facility involved.
8 MR. MICHELSON: One of the interesting questions, 9 I was looking at this list and I saw the loss of all 10 A.C. power as one of the things that the simulator has to 11 simulate. And it raised the question in my mind as to what 12 extent are you requiring that the simulators pre-predict all
<x 13 the unwanted actions caused by loss of A.C. power, for (v )
14 instance. Either partial or complete. Partial losses are 15 sometimes even worse, you know?
16 All the devices go to various states on loss of 17 power. Do you think the simulator simulates all those 18 possible states? I'd be surprised if it does.
19 MR. WACHTEL: So would I. I'm sure there's a 20 wide diversity.
21 MR. MICHELSON: Yet, you're simulating, say, 22 partial loss of A.C. power. You would expect the simulator 23 now to light up and ring and move around according to what 24 all these failure states are on loss of power. And I don't
(^)
v 25 think simulators necessarily do that.
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0160 04 11 236 ,
1
,1 DAV/bc 1 MR. WARD: I think they do, but they assume
(^~') 2 everything else works right, unless you've told them there's 3 a multiple malfunction.
4 MR. MICHELSON: I don't think a simulator 5 necessarily...it assumes a loss of function, not an unwanted 6 action. For instance, what is the control state of a 7 feedwater valve on loss of power? Does it go " valve wide 8 open, valve closed" or stay as is?
9 I don't think the simulator necessarily knows 10 this down to all the components. It may on a few keys, but 11 that's the question:
12 To what extent does the simulator understand the 13 phenomena associated with loss of power?
14 MR. GIMMY: The current set of specs, for 15 instance, if you're dealing with Singer-Link, the first 16 thing you do for each system, whether it be feedwater or 17 anything else, you'd draw a simulation diagram which shows 18 the major components, the pumps, the pipes, et cetera.
19 You put in pump head curves and pipe resistances, 20 valve-opening times, this sort of thing. Then, the next 21 thing you specify is what breaker this thing is fed from.
22 If it's electrical, what breaker is it fed from? And what 23 transfo rmer?
24 of course, total loss of power kills them all.
(} 25 If you just lose one transformer, it just takes out those ACE-FEDERAL REPORTERS, INC.
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0160 04 12 237 1 DAV/bc 1 associated with it.
k 2 Then you have to specify one of three things.
3 That's as far as they carry it. It stays where it is, 4 closes or goes down or opens or goes up to the max. You 5 specify one of those three things for each of those 6 components.
7 So, when it loses power, for instance, on a pump, 8 almost all pumps that I know of, they close down and there's 9 some curve for that. But, on valves, there are some valves 10 that stay where they are and some powered open valves that 11 if you lose power, they close. If that's the case, you do 12 specify that and it is modeled.
MR. MICHELSON: It gets a little more
") 13 14 complicated. It's pretty easy to do for valves perhaps. It 15 gets more complicated in control circuits where you have 16 partial loss of power on the control circuits, or if you get 17 into the air-operated systems where, if you lose the power 18 to the air, the air slowly bleeds off.
19 MR. GIMMY: The air system is modeled 20 separately. And when you lose the compressers, it has 21 assumed leakage or consumption rates which bring it down.
22 MR. MICHELSON: Now the response of all the 23 various components around the plant that are powered by air 24 to that loss of air varies according to the particular
() 25 component.
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0160 04 13 238 DAV/bc 1 MR. GIMMY: Again, they have the three-way 2 choice. It stays where it is and there are some air things 3 like that, like fan-dampers. It closes or opens.
4 What I'm saying is, this is all the choices you 5 get.
6 MR. MICHELSON: So you're saying a simulator does 7 go through then? It goes that far?
8 MR. GIMMY: The newer simulators, not the ones 9 they built five years ago, but the newer ones on every 10 energy-driven device; if it's electrical, it's assumed to 11 be lost immediately when you lose that transformer. You 12 have to specify for each one of them whether it goes open, 13 closed or stays where it is. Or, in the case of control
(~)'
G 14 rods, it's up, down or stay where they are.
15 On air-operated things or things that are driven 16 from other energy sources, like, for instance, hydraulic 17 valves from a hydraulic accumulator, there what you have to 18 do is assume in the design basis leakage rate or consumption 19 rate that will pull down your reservoirs.
20 MR. MICHELSON: Is that in the simulation?
21 MR. GIMMY: It sure is.
22 MR. MICHELSON: Even to see if the check valves 23 in the accumulators are on something?
24 MR. GIMMY: You say, for instance, if I lose my i ) 25 compressers, the plant air system will follow this curve ACE FEDERAL REPORTERS, INC.
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l 0160 04 14 239 1 DAV/bc 1 down. Air pressure will follow this curve down. It's 150 0 2 pounds now and it comes down lik.e this. Thirty minutes 3 later, you've got nothing.
4 And when it crosses down below some of the 5 regulators, you get to where you don't have 15 pounds to 6 work your zero to 15 air valves any more. They start going 7 whichever way you said they're going to go.
8 MR. MICHELSON: Do you do this on both the safety 9 and the nonsafety system?
10 MR. GIMMY: You do it on every system.
11 12 rm. 13 i )
v 14 15 16 17 l
18l 19 20 21 22 23 24
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0160 05 01 240 1 DAVbw 1 MR. MICHELSON: That's a fairly complete rm 2 simulation. One of the simulators I'm acquainted with 3 doesn't do quite that well, and it's not one of the
, 4 brand-new ones either.
5 MR. GIMMY: I'm talking about ones made in the 6 last five years.
7 MR. WYLIE: It has to be plant-specific. There 8 are a lot of them. In fact, most plants I'm familiar with, 9 even the loss of all AC power, you still have control power, 10 because you're on an up system.
11 MR. WARD: Oh, sure. But that would be modeled, 12 Charlie.
13 MR. WYLIE: That's what I mean. It's 14 plant-specific.
15 MR. WARD: I think one thing they don' t do is, if 16 you have voltage degradation or something, they don' t deal 17 with that, where you get all sorts of strange responses. I 18 don't think they do that very well. Or if a device responds 19 randomly to loss of power.
20 MR. MICHELSON: Another thing I'm pretty sure 21 they don' t do, for instance, is, you lose power, say, to the 22 air conditioning in the room, and the room starts warming 23 up, and the solid state control circuit which is still being 24 powered, starts responding in strange fashions, that just is
(} 25 lost.
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0160 05 02 241 DAVbw 1 MR. GIMMY: A ground rule of simulators is that 2 you assume that all of the equipment which wasn't 3 malfunctioning, you assume that all the rest of it works as 4 designed, and you assume, for instance, that there's a 5 diesel start, and that the diesels come on line, unless you l 6 want to declare a second valve function that some diesel 7 didn't start.
8 MR. MICHELSON: The simulation you describe is 9 about the reasonable upper limit, I think, on what you can 10 do.
11 If the new simulators can go that far, that's 12 great. I wasn't familiar, and that's why I asked the
(~ 13 question, can you go that far.
())
14 So I'm satisfied. Thank you.
15 MR. GIMMY: Is that your understanding too on 16 your inspections?
17 MR. WACHTEL: Yes, indeed, it is. Bruce?
18 MR. BOGER: I just want to add, it's obviously an 19 economic decision that a plant will have to make, deciding 20 on how far the want the simulation to go. The standard 21 really talks in terms of its training benefit. You know, 22 how often does the event occur? How important is it? Is it 23 worth training a person on a simulator, or should they go 24 over it in the classroom. So there's a determination right h 25 there, but certainly state of the art simulators, as
(~J w
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0160 05 03 242 2 DAVbw 1 Mr. Gimmy says, model quite a bit, and the old ones don't or
/ ^i 2 may not.
3 MR. WACHTEL: The last of the major exceptions.
4 MR. WARD: Could I go back to this question now 5 of abnornal events or malfunctions? You've got a list of I 6 don't know how many, 80 or 100, or something there, I 7 guess. But the original question, where you were insisting 8 that if a malfunction is modeled by the simulator, it has to 9 be confirmed. You've backed off from that.
10 MR. WACHTEL: That's right. This list is 11 essentially the replacement for that global statement that 12 says, if you've got a malfunction, you must test it and it
,e) 13 must be confirmed.
C/
14 MR. WARD: And I can see, you know, where the 15 Licensees were unhappy with the difficulty on that.
16 On the other hand, if they're going to be using 17 these other malfunctions, if they've got a simulator that's 18 got 500 malfunctions, and if they're going to be using those 19 to train their operators in dealing with those malfunctions, 20 you'd think somebody would be interested in confirming that 21 the simulation is correct.
22 MR. WACHTEL: That was my initial intent in 23 writing it that way two years ago. You know, if you're 24 dealing with the training benefit of the simulator, you are
/N 25 really developing these benefits, if you have a malfunction
(_)
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0160 05 04 243 l DAVbw 1 that does not mirror the plant.
2 That's why we wrote it the way we did. We 3 realized there were problems in pinning down the limits of 4 what tesing ought to be, and so we qualified it by saying, 5 you must test every malfunction to the extent that they may 6 be used in the conduct of operating tests.
7 Even so, that did not satisfy a large number of 8 our critics, who essentially said, depending on how I look 9 at this unending list of malfunctions versus depending on 10 how you, the NRC look at it, I could tie my simulator up 30 11 percent of the time for just satisfying your performance 12 testing requirements. And we came to the realization that 13 however we tried to define it, if we left it open in terms
(^)
LJ 14 of testing every malfunction, there really was not a very 15 good way that we could identify the balance of what those 16 tests were.
17 So we went back and developed this list that we 18 seemed to think will satisfy us, that ths is the limit of 19 what we may use on operating tests. Therefore, if the 20 simulator can do all of these tests, we'll be happy with 21 it.
22 MR. WARD: Well, what if you said any 23 malfunctions that they use in training they should have 24 confirmed, validated with tests. You know, not any
(} 25 malfunction that the simulator is capable of itself, but ACE-FEDERAL REPORTERS, INC.
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0160 05 05 244 1 DAVbw 1 any malfunction that the actually use in training should be O 2 tested.
1 3 Of course, your Reg Guide is written for i 4 examining, not training.
5 MR. WACHTEL: Of course, we've already entered it 6 entirely toward the exam side.
7 MR. MICHELSON: One more question on this list.
8 When you talk about loss, unless otherwise 9 specified, do you really mean just loss of one of two 10 trains, if it's an engineering safety feature, or do you 11 mean loss of both trains?.
12 MR. WACHTEL: Where are you looking?
13 MR. MICHELSON: I'm looking at your list under r~}
\~/
14 Items 12 and 13 in the Guide. You list losses of this and 15 that. We discuss loss of all AC power. I pointed out the 16 limitation, of course, is when you lose all AC power, you 17 also lose ventilation, and so forth, and it's difficult to 18 simulate all the possible effects of that.
19 MR. GIMMY: And understand, they're not simulated 20 from a menu of effects. The way it's simulated is, you lose 21 AC power. That turns off pumps, which perturbs the 22 hydraulic system. It turns off vans which perturbe the 23 ventilation system.
24 MR. MICHELSON: It's first order effects.
(~) 25 MR. GIMMY: That's right.
R./
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0160 05 06 245 1 DAVbw 1 MR. MICHELSON: But first order effects now have O 2 second order effects, and you don't necessarily simulate the 3 second order effects.
4 What I was asking, though is, in a case of dual 5 train systems, is the simulation designed, even though it's 6 not a design basis for the plant, are you sinulating the 7 possible effects of loss of both trainms?
8 MR. WACHTEL: My understanding would be that if 9 the simulator has that capability, then the malfunction 10 testing would exercise that capability.
11 MR. MICHELSON: Say that again?
12 MR. WACHTEL: If the simulator --
13 MR. MICHELSON: Okay. What I'm asking is, to
(^}
v 14 what extent does the simulator have to simulate these 15 events? Deos it have to simulate a two-train loss when the 16 design basis for the plant is a one-train loss?
17 MR. BOGER: I think, typically, what the standard 18 would require is probably one train, because that's what you 19 get training benefit from, one train.
20 As you get better and better simulation, you can 21 do both trains, but I think, typically, one train would be 22 all that would be required.
23 MR. MICHELSON: The simulator has the ability to
'24 take -- you can take either Train A or Train B and knock it l
(')
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25 out. It's when you knock out both trains that you start ACE FEDERAL REPORTERS, INC.
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0160 05 07 246 DAVbw 1 getting some strange things happening that I'm not sure are 2 included in the simulation. As long as one of the two 3 trains is there, then all right, but when two trains go out 4 -- !
5 MR. BOGER: Sometimes the push button simulation 6 doesn't do that. You may have to go back into the program 7 and defeat thingc.
8 MR. MICHELSON: Then the simulation will not be 9 correct, because it now involves the second order effects, 10 which become very important, like loss-of-cooling on solid 11 state equipment and things like causing a lot of strange 12 things to happen.
/ 's. 13 MR. GIMMY: Simulation stops pretty much at the k./
14 first order of things.
15 MR. MICHELSON: And I think it pretty well stops 16 at the loss of one train at a time.
17 MR. GIMMY: Simulation is only a simulation. ,
18 It's not an engineering calculation. The important thing 19 is, it has to be done in real time, so that it looks real to 20 the operator.
21 This alone limits you.
22 MR. MICHELSON: Loss of DC power is a good 23 example.
24 I think I can simulate the loss of one train of f] 25 DC power. The simulation will go through, but it won't be s_/
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0160 05 08 247 1 DAVbw 1 real.
O 2 MR. GIMMY: What the ANSI standard says on 3 testing a malfunction or an accident like this.
4 MR. WARD: Okay. He's not really talking about 5 testing maI5 unctions. Carl was changing the subject.
6 MR. MICHELSON: This is not testing. This is the 7 design basis for the simulator, and I think the design basis 8 is, it simulates loss of one train at a time.
9 MR. GIMMY: I'm addressing the design basis. The 10 design basis is designed to meet ANSI 35, and it says this, 11 when you put in a malfunction, you've only got to look for 12 three things: one, the important variables, critical r~) 13 variables go in the right direction. They don' t even have
(./
14 to go right around. They have to go in the right 15 direction, b) it must not violate the laws of physics, which 16 is hard to interpret sometimes, and c), if a scram would 17 have occurred or some automatic action would have occurred, 18 it must occur, and if it should have occurred, it should not 19 occur.
20 As I understand it, that's the only three things 21 that you're looking for is, critical variables go in the 22 right direction. As I say, don't violate the laws of 23 physics, and that's about as far as they can simulate these 24 trends, because you know, they can't do one of these great
(~4 ; 25 pipe code calculations.
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0160 05 09 248 1 DAVbw 1 MR. WARD: You don't have TRAC.
2 MR. MICHELSON: I wasn't trying to get that 3 sophisticated. I was just worrying, for instance, about the 4 loss of ventilation. I can understand how to simulate a 5 loss of one train, but I don't know how to simulate the loss 6 of both trains, because now I have to get into the effects 7 of air temperature on all the components involved, and I 8 don't think it does that.
9 MR. WYLIE: I don't see on here -- or maybe it's 10 here and I just missed it -- the loss of all feedwater. It I
11 says main feedwater, but it doesn't say all.
12 This is something that's happened several times r- 13 for various reasons.
b) 14 MR. BOGER: I think it speaks to auxiliary 15 feedwater malfunction system.
16 MR. WARD: Page 6, the fourth line down from the 17 top.
18 MR. WYLIE: Okay. I assumed all feedwater.
19 MR.-WACHTEL: The final major exception that we l
20 take for the standard is something that we have been 21 discussing, and we talked about briefly yesterday. That is, 22 that the performance testing of the simulator, and this is 23 now changed from the draft version of the rule, the tesing 24 should be performed over a four-year cycle, 25 percent of
{} 25 those per year, in accordance with the list of tests in the l
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0160 05 10 249 DAVbw 1 Reg Guide that we have just been talking about.
2 MR. MICHELSON: How do you know that you've 3 passed the test when you perform it? What do you compare it 4 to?
5 MR. WACHTEL: That will be addressed with the 6 evaluation program that we are developing that I'll talk 7 about in a few minutes.
8 (Slide.)
9 We have a phased implementation program, 10 essentially a grace period, in which we give every utility 11 four years before they will be required to have their 12 simulation facility in place for the conduct of operating 7 's 13 tests. As I mentioned yesterday, this had been a V
14 three-year program in the draft version of rules, and we 15 received a lot of comments that that time schedule was 16 simply too tight, particularly for those utilities who 17 wanted to procurc a plant reference simulator, which may 18 take perhaps as long as 36 months from the time you sign the 19 contract until you get delivery.
20 So we have extended that period to be a four-year 21 period, and as you see, it is a phased-in program, 22 culminating at the end of the fourth year after the 23 effective date of the rule, when we say, in Part 55, that 24 from that day forward, all operating tests must be conducted
(~T 25 on either a certified or an approved plant reference
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0160 05 11 250 l_ DAVbw 1 simulator or simulation facility.
(*1 2 (Slide.)
3 I just want to give you a status report. This is 4 a fluid number. The last time that I reported these numbers 5 to you a year or so ago, there were 26 existing simulators.
6 Now there are 38. There were 33 under construction, and 7 there are now 28. There were 16 being considered, and now 8 there are 8. And the reason those numbers are small is, of 9 course, those that were in the construction pipeline or 10 under consideration have now moved up into being operational 11 or being under construction. And for those facilities that 12 have no plans for simulators, that number had been 19 13 reactors. It is now down to 13.
14 So whether it is that utilities have seen the 15 lightr on their own, or whether they have been swayed by the 16 threat or the promise of rulemaking in this area, I don't 17 know, but more utilities have obtained simulators and are in l
! 18 the process of obtaining simulators that was the case about l
i 19 a year ago.
20 MR. WARD: When you say simulator here, you can't l-l 21 mean they're all ANSI 3.5 1985, but you must mean almost 22 that.
23 MR. WACHTEL: The words we used in the document 24 that I've tried to keep up-to-date is, that these are
(} 25 simulators that purport to meet ANSI 3.5, and at that time, l
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0160 05 12 251 DAVbw 1 it was 1981.
2 The 1985 standard has just been published. It 3 might be fair to say that none of them meet it, although the 4 requirements may not be difficult to meet.
5 MR. WARD: But included in the 13 there at the 6 bottom, those wouldn't be plants that have old 3.5 7 simulators.
8 MR. WACHTEL: That's correct. Those are plants 9 without simulators of any kind, as far as we know.
10 MR. WARD: And they might be going with the parts 11 task or something else.
12 We haven't heard from them.
r; 13 MR. WACHTEL: We hope so. We have not heard from
\~J 14 them yet. Of course, many of those are on the list that we 15 would expect to seek an exemption from the rules.
16 MR. WARD: Where do you have Dresden? That's a 17 pretty old simulator, which probably isn't anywhere c'ase to .
18 1978 even.
i 19 MR. WACHTEL: Dresden 2 and 3 is listed under 20 existing simulators, and I am sure we don't want to take the 21 time now, but I have available the names of those that fit 22 into each category, if anyone would like to talk about 23 that.
24 I mentioned briefly about a contract that we 1
() 25 recently signed and have under way. You don't have this in ACE-FEDERAL REPORTERS, INC.
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0160 05 13 252 1 UAVbw 1 your handout. But let me tell you briefly what we're O 2 doing.
3 (Slide.)
4 The contract is titled "The Development of an NRC 5 Simulation Facility Evaluation Program." The contractor is 6 a small firm in Boulder, Colorado, by the name of 7 Microanalysis and Design. The president of the company, who 8 is also the principal investigator on this contract, is a 9 fellow named Ron Laughery, who used to work with Calspan and 10 with the Air Force.
11 He developed the simulator evaluation methodology 12 used for the Air Force and for the Strategic Air Company and
- 13 had an earlier subcontract with Oak Ridge National Labs, i
14 when they developed a simulator evaluation handbook for the 15 NRC Office of Research.
16 Battelle Pacific Northwest Labs is a 17 subcontractor to Microanalysis and Design, and it is a l 18 one-year basic contarct with a six-month optional 19 extension. That optional extension is at the NRC's 20 option. The basic one-year effort which began in September 21 of this year is for the development of an evaluation program 22 for ANS 3.5 type simulators.
l 23 The optional extension will be invoked in the 24 event that utilities come forward and propose to use other
~T 25 than ANS 3.5 simulators, at which time, we will modify or (V
I i
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0160 05 14 253 DAVbw 1 further develop the methodology so that it can be applied to 2 these other devices, as they may be proposed to us.
3 Basically, the tasks consist of the selection and 4 convening of a steering committee.
5 In the next slide, I'll show you who was on the 6 steering committee, a literature review, the development of 7 a test case or a strawman evaluation plan applicable to ANS 8 3.5 simulators, the conduct of a review to test the plan on 9 an actual simulator that is volunteered to our use, as part 10 of this contract. And the steering committee is involved at 11 all phases of the contract providing guidance to the 12 contractor, critiquing the evaluation plan, helping him to
() 13 develop his application to the test and then critiquing it 14 again.
15 The tasks that talk about performing the review 16 to test the plan for the optional phase, as I mentioned, 17 addressed the non-3.5 simulators.
18 And the final task is the preparation of the l 19 final evaluation plan and recommendations.
20 The ultimate use of what is developed will 21 probably find its way into our Examiners Standards.
22 Part of what the contractor is required to tell 23 us is what the makeup of the team should be that will be 24 charged with the review and evaluation of simulators, what l () 25 technical skills those people need to have, how many of c #
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0160 05 15 254 DAVbw 1 them there need to be, whether they should be NRC Staffers 2 or contract staffers or National Lab personnel, or what 3 have.
4 5
6 7
8 9
10 11 12
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13 14 15 16 17 i
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20 21 22 i
23 l
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[3 DAVbur 1 (Slide.)
(_)
2 The Steering Committee has been formed and had 3 its first meeting the beg'.aning of November at Columbia, 4 Maryland.
5 We tried to strike a balance between keeping it 6 down to a manageable size and yet reflecting the wide 7 diversity of capability and interest, and as you can see, 8 the committee consists of:
9 Malcolm Black from Northeast Utilities, who is a 10 member of the ANS 3.5 Committee.
11 Ed Boothe, who is the top man for the FAA in 12 their simulator program. That is a national program where
() 13 they evaluate all simulators used in commercial aviation.
14 Julian Christensen, who is our Human Factors 15 representative. He is Chief Scientist at Universal Energy 16 Systems, and he is the President Elect of the Human Factors 17 Society.
18 Israel Ganz, Program Manager for Simulator 19 Projects at GE.
20 Bill Gardner, the Supervisor of Simulation i
21 Systems at Combustion Engineering.
22 Bob Koehler, the Manager of Production Training l
23 Services for Duke Power.
24 And Gus Wanner, also a member of the ANS 3.5 O 25 Committee, a former Singer-Link employee, now Vice
( ,/
l l
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0160 06 02 256 J'3 t DAVbur 1 President at Exitech Corporation in Columbia, Maryland.
\.s 2 As I mentioned, the committee had its first 3 meeting earlier this month. Its next meeting will be in 4 January, and at that time the contractor will present to the 5 committee its straw man evaluation program for their 6 critique and evaluation.
7 We are now in the process of making contact with 8 several utilities, trying to identify potential candidate 9 simulators to be used, against which to test this 10 methodology. We have a number of candidates in mind that 11 have not yet been selected.
12 MR. WARD: Any other questions for Jerry?
13 (No response.)
14 MR. WACHTEL: Thank "ou.
15 MR. WARD: We have a question for Susan.
16 DR. REMICK: Two questions. I am sorry, I am 17 just getting awake.
18 I was interested in the Staff's philosophy on two 19 things: one, requiring licensees to certify medical exams 20 every two years versus doing it on a six-year interval.
21 That is the first question.
22 MS. SHANKMAN: I don't think we are asking them 23 to certify it every two years. We are asking them to have a 24 biennial exam.
() 25 DR. REMICK: Bruce, you indicated to me it'was*
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0160 06 03 257 1_ DAVbur 1 after being asked the question.
2 MS. SHANKMAN: No, they just have to maintain the 3 documentation, and the medical documentation if we audit it 4 and it is more than two years old.
5 DR. REMICK: Okay, we don't have to certify it?
6 MS. SHANKMAN: No. And in any instance where we 7 say they have to certify it, where things are current, like 8 in coming back from inactive status, they have to certify to 9 us that it is current. Part of that is the medical exam.
10 They have to maintain their medical status and not have an 11 inactive license that could be easily activated -- well, as 12 easily as the requirement.
13 DR. REMICK: The other question: what is the r~-)
(_/
14 philosophy on nonpower reactors of not having to follow 15 this; in other words, certify continuously, as they have in 16 the past? Is it because power reactors should not have the 17 medical backup to make judgments?
18 MS. SHANKMAN: I think we are redoing the reg 19 guide. It applies to power reactors. We didn't think it 20 applies to nonpower reactors because in the public comments, 11 the head of the ANSI 15.1 Committee said they were reviewing 22 their standards and they were going to consider medical, and i
l 23 would it be appropriate to continue things as the status quo i 24 until they had completed their evaluation?
25 We agreed that that would be a good idea.
(O~)
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0160 06 04 258 1 DR. REMICK: I see.
(l_)DAVbur 2 MS. SHANKMAN: Because with the medical we are 3 endorsing an industry standard on the, assumption that that 4 was done with medical advice, and we are not in the medical 5 business.
6 I wanted to call to your attention the solo 7 operation, which is in the standard at page 1, where they 8 have their glossary of terms. That may clarify a bit what 9 we were talking about, the issue of what does solo operation 10 mean.
11 DR. REMICK: Page l?
12 MS. SHANKMAN: Yes, page 1. It says " Solo 13 operation."
14 MR. WARD: It is actually about page 6 or so.
15 MS. SHANKMAN: It is numbered 1 on the bottom.
16 It says " Glossary of Terms, 2.2."
17 It includes control room or other specified i
18 control areas.
19 So what we have done in our endorsement of the 20 standard is to say that where the standard says no solo i
21 operation and says a qualified person has to be there, we l
22 are agreeing that their definition of solo operation is 23 correct, but we are saying where a qualified person -- that 24 person has to be licensed.
() 25 If you look further down on that page, under l
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0160 06 05 259 DAVbur 1 " Health Evaluation Responsibility," it says the designated 2 medical examiner shall be conversant with this standard and 3 should have a general understanding of activities required 4 of a nuclear reactor operator.
5 I don't know if that clarifies it or not.
6 MR. MICHELSON: The point that it doesn' t 7 address, of course, is it should have said also -- not only 8 general understanding of the activities, but also the 9 possible effects of disabilit3 That part is not being 10 evaluated apparently, 11 MS. SHANKMAN: If you also look on page 5, it 12 speaks to color vision adequate to distinguish among red, f^; 13 green, and orange-yellow signal lights and any other coding (J
14 required for safe operation by the facility operator.
15 Again, it is expected that the facility would 16 identify for their examining physician what color issues are 17 in their control room.
18 Again, Item 4 under that speaks to depth 19 perception. So that would speak to the one-eye issue.
20 MR. WARD: 7t gives you a number for untreated 21 hypertension, too. 160 over 100.
22 Okay, let's take a break and come back at 10:30.
23 (Recess.)
24 MR. WARD: Let's reconvene.
lqj 25 Our next speaker is Mr. Persensky, who wi11'.. talk ACE FEDERAL REPORTERS, INC.
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0160 06 06 260 1 DAVbur 1 about Reg Guide 1.8.
O 2 Jay.
3 (Slide.)
4 MR. PERSENSKY: I would like to start off by 5 saying that the reg guide which is now in the package is 6 considerably different than the one which went out for
/ public comment, primarily because we have broken it into two 8 sections.
9 Originally, we had endorsed in its entirety ANS 10 3.1, 1981. We have now decided that based on the policy 11 statement that limits us pretty much to regulations 12 regarding the licensed operators to endorse ANS 3.1, 1981
,r~T 13 only for the ROs, SROs, and shift supervisors. We are going V
14 to maintain the endorsement of ANS 18.1, 1971 for all other 15 positions.
16 There is a little sneaky one in there. That is 17 the STA because the STA wasn't even mentioned in the 1971 18 standard. But we have broken it into two sections, one for 19 licensed operators and one for the other positions.
20 It does support the proposed changes to Part 55, 21 which you have heard about over the last two days.
22 It does provide clarification for the STA 23 position, including the recently published policy statement 24 on engineering expertise on shift, which allows the dual
() 25 role position, given certain educational and training ACE-FEDERAL REPORTERS, INC.
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.0160 06 07 261 l
DAVbur 1 requirements, and it is of course limited by the policy 2 statement on training and qualifications.
3 There is no intent here to add any new 4 requirements that aren' t already in some other documents.
5 What we are trying to do is pull together things from the 6 March 28th letter, 07-37, anything new that might have been 7 in Part 55, all in one place so that we don' t have a bunch 8 of different documents to be looking at.
9 Part of it is also OL practice and some of these 10 definitions which have again been updated through Part 55.
11 (Slide.)
12 The implementation aspect of this is that we
'( ) 13 expect it to be used one year after publication for new 14 licensees for all personnel, for the qualifications and 15 training requirements, for applications for SROs and ROs, 16 and for replacement personnel that are not covered by 1
17 accreditation in the positions covered by accreditation.
18 (Slide.)
19 MR. WARD: I don't understand what replacement 20 personnel means.
21 MR. PERSENSKY: It is essentially a 22 grandfathering clause. If someone is in the job right now 23 as operations manager, or comething like that, and doesn't 24 meet the new requirements, then whoever replaces him or her
() 25 would have to meet the new requirements.
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0160 06 08 262 DAVbur 1 Since we are going back to the 18.1 for most of 2 those positions, it shouldn't be a real problem.
3 MR. WARD: All right.
4 MR. PERSENSKY: The regulatory positions --
5 there's only two regulatory positions with a lot of 6 subelements to them now.
7 The first regulatory position is dealing with the 8 licensed operators. This again, as I indicated, endorses 9 the 1981 standard. It does indicate that the code license 10 applicants must meet all the training objectives in an 11 NRC-approved program.
12 Now, for new utilities, since accreditation
(~) 13 generally doesn't take place until two years after the plant V
14 has been operating, we are still approving training programs 15 for new facilities.
16 A second issue is that the educational 17 requirement, which has received a lot of discussion over the 18 last five years in the '81 standard, it did include the 60 19 hours for the shift supervisor and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> for the senior 20 reactor operators, college credit hours. We are taking 21 exception to that, so there will be no such requirement by 22 this regulatory guide.
23 The standard still calls for a power plant 24 experience for an SRO of three years. We have increased 25 that to four years. Again, this is based on things that
(])
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0160 06 09 263 DAVbur 1 were in the March 28th letter and 07-37. We have been using 2 that as our standard for some time.
3 The two years nuclear power plant experience that 4 is required by the standard, we want at least six months of 5 that to be at the facility for which the individual is 6 seeking the license. For those SRO applicants that do not 7 have a deg.ee, they will need to have one year experience as 8 a licensed reactor operator and performing duties, not just 9 holding the license.
10 That is the question.
11 DR. REMICK: Jay, before you take that slide off, 12 may I interrupt you a minute?
13 I get confused when I look at the guide. On page
(~)
%/
14 3, it talks about shift supervisors, senior operators, and 15 in caps licensed operators.
16 Now, on the top of your slide you say licensed 17 operators are ROs, SROs, and SSs. I agree.
18 And then I look at definitions somewhere else.
19 It seems like this bit of what is an RO, what is an SRO --
l l 20 we throw these terms around very loosely. I have always l
21 found it a little confusing that Part 55, instead of saying 22 senior reactor operator, it talks about senior operator.
l
^'
25 And it seems here -- I realize this is just a
('_-)
l 1
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0160 06 10 264 DAVbur 1 slide -- but as I go from the guide, I go to the ANSI 2 standard, it seems that everybody is using slightly 3 different definitions.
4 In the guide you have something called Licensed 5 Operator, capital L, capital O. Up here you are saying 6 licensed operator means reactor operators, senior operators, 7 shift supervisors.
8 My point is: are we adding to the confusion by 9 not being careful?
10 MR. PERSENSKY: I would have to go back to the 11 standard and see how they refer to them, and I gave my copy 12 of the standard for copying.
(~~j 13 Licensed operators, I think, has been the more
\m/
14 generic t'rm.
15 DR. REMICK: It should oe generic, I agree.
16 MR. PERSENSKY: That they have a license.
17 DR. REMICK: But that is not what you have in the
! 18 guide.
19 MR. PERSENSKY: I believe in the standard, the 20 standard refers to what we consider mostly the control room 21 operator, the RO, as a licensed operator.
22 23 24
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0160 07 01 265
, /~sDAV/bc 1 DR. REMICK: A licensed operator.
V 2 MS. SHANKMAN: Jay, I can speak to why it's an 3 operator and a senior operator.
4 MR. PERSENSKY: Speak to it, Susan.
5 MS. SI@.SEMAN : When we were changing this as a 6 proposed rule, we changed it to reactor operators and senior 7 reactor operators. When it got to the attorneys there was 8 some concern that this is referencing so many parts of 9 Chapter X, that it would oe just an out of reason job to 10 change all the regulations to the new reactor operator and 11 senior reactor operator.
12 Since we've been using operator and senior
() 13 operator in our rules since we started writing them, they 14 felt that we should just leave it the way it was, even 15 though the common terminology when people talk about it, 16 when we talk about it, we talked about RO's and SRO's, it 17 was just simply not to have to redo all of Chapter X.
18 DR. REMICK: Are you saying Chapter X refers to 19 operator as senior operator?
20 MS. SHANKMAN: Yes, they refer to them in many 21 places in terms of staffing, in terms of what they do. It's 22 peppered throughout the regulations. And the attorneys felt 23 that it was just a matter of convenience, since we had 24 always used " operator" and " senior operator" when we wrote n
(_) 25 the regulations, that we should continue that as the ACE-FEDERAL REPORTERS, INC.
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0160 07 02 266 DAV/bc 1 convention for the regulations.
2 DR. REMICK: I can understand that. I think it's 3 unfortunate that they're not willing to change it. That I 4 can understand, but you're compounding it now in your 5 guide. This is an NRC guide, but you're saying " Licensed 6 Operator" with a capital "L". So you're adding an 7 additional step.
8 That's because the standard refers to it, but 9 we're compounding the folly by the NRC's now, whatever the 10 lawyers are telling you, using these standards. That's the 11 point I'm trying to make.
12 MR. PERSENSKY: The other confusing factor with T 13 respect to the two reg guides is that there is no regulatory
(~/
(_ '
14 position called " shift supervisor".
15 MR. WARD: ,That's another problem. What's that?
16 MR. PERSENSKY: But the ANSI standard does have a 17 separate group called " shift supervisor"' since they're 18I licensed, we're trying to make sure that they're covered in l
19 this regulatory guide.
20 I agree with you, there's a lot of confusion. In 21 fact, there are a lot of plants that have two categories of 22 licensed operators and two or three categories of senior 23 reactor operators.
24 Not all of them refer to them just as RO or CRO.
() 25 MR. WARD: But you only have two licenses.
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r 0160 07 03 267 DAV/bc 1 MR. PERSENSKY: Correct. There are only two 2 licenses -- operator and Senior operator. I'm not sure how 3 to handle that. We can talk with lawyers about using the 4 terminology. We try to be consistent with the standard as 5 opposed...Unfortunately, in making up our slides, we often 6 slip back into the vernacular.
7 DR. REMICK: I think you should see if there's 8 something that can be done to try to reduce the confusion 9 anyhow.
10 (Slide.)
11 MR. PERSENSKY: To continue the regulatory 12 position with regard to those people who are licensed to
{} 13 operate, we have added in here the training to mitigate core 14 damage, control to mitigate core damage, the three months on 15 shift as an extra person in the position for which the 16 license is sought, either three months following an RO 17 around, or three months following an SRO around.
18 For those people that are hot license applicants, 19 so that the plant has been operating, there was a question 20 with regard to the significance reactivity changes. We have 21 added some clarifications in there to indicate that it has 22 to be a 10 percent or greater power change, and that there 23 should be some diversity amongst these five reactivity i
24 changes.
() 25 The six months of practical work experience for ACE-FEDERAL REPORTERS, INC.
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1 l
1 0160 07 04 268 DAV/bc 1 cold license applicants, in the standard, it only talks 2 about practical work experience; it does not give a 3 timeframe. We have indicated that six months if the 4 appropriate time.
5 And this is something that has been, I believe, l
6 in 07.37. The other aspect here is refresher training. As 7 Susan indicated yesterday, if someone has not been actively 8 performing there is a need for them to get certain refresher 9 training. We have a regulatory position here that 10 indicaties that training should be performance-based, and 11 that they should look at items like new procedures or 12 changes to procedures, plant modifications or changes in
(~;) 13 status of various functional units.
x 14 It's an upgrade training for those people who 15 have not been actively performing.
16 Also, to follow that through, there has to be a 17 certification by a plant manager or his designee to assure 18 that the qualifications are current and valid if those 19 people are returning to duty.
20 It also gives some criteria as to how we make the 21 judgment on that certification, including items like the 22 time requalification, they've been involved with 23 requalification programs, what additional training has been 24 carried out and the total training and involvement in plant o) s 25 activities.
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l 0160 07 05 269 gL DAV/bc 1 (Slide.)
For those positions...
2 3 DR. REMICK: Can I ask another question before 4 you go on to the other positions?
5 Going back to the second slide, item D...
6 MR. PERSENSKY: I have three "D"'s there. I 7 tried to keep the bullets.
8 DR. REMICK: You're right. The last "D". The 9 SRO applicants without a degree in engineering. You 10 indicate they should have been an RO for at least one year.
1.1 How about if they have a degree?
12 MR, PERSENSKY: They are not required to hold an
(' 13 RO license prior to --
U 14 DR. REMICK: So you could not have an SRO if he 15 did not have a degree?
16 MR. PERSENSKY: Correct.
17 DR. REMICK: Isn't that a change?
18 MR. PERSENSKY: That's 0737.
19 DR. REMICK: 737 required a degree for an SRO?
20 MR. PERSENSKY: I believe so.
21 DR. REMICK: I wasn't aware of that.
22 MR. PERSENSKY: We copied these words verbatim 23 from 0737 as in the regulatory guide.
24 DR. REMICK: Is there a reason for that? Why, if (n) 25 you have a degree, you become an SRO? Is this for tech ACE-FEDERAL REPORTERS, INC.
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0160 07 06 270 DAV/bc 1 support people?
2 MR. PERSENSKY: I believe the primary reason for 3 that was the backup licenses. As you say tech support, 4 engineering support. Again, what we're trying to do is not 5 make any new regulations requirement.s but go back to what 6 has been practiced.
7 DR. REMICK: Okay.
8 MR. PERSENSKY: For those positions other than 9 licensed operators, in general, we are endorsing ANSI 10 N-18.1, 1971, which is currently endorsed by reg guide 11 1.8, 1975. But, in addition, we have the STA in here, since 12 that's not covered at all in the 1971 standard.
(~} 13 But, in the 1981 standard, it allows replacement
- J 14 of the STA or elimination of the STA position if the shift 15 supervisor has 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of college credit. We are taking 16 exception to that because of the engineering policy 17 statement, the engineering expertise policy statement.
18 MR. WARD: Wait a minute, Jay. The STA is 19 required on all shifts and should assume an active role on 20 shift activities. Is that it?
21 MR. PERSENSKY: That's part of the policy 22 statement.
23 MR. WARD: The new policy statement? Okay.
24 MR. PERSENSKY: The new policy statement.
() 25 MR. WARD: Asleep in the bunkhouse doesn't count ACE FEDERAL REPORTERS, INC.
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0160 07 07 271 DAV/bc 1 any more.
2 MR. PERSENSKY: That's the direction that the 3 Commission would like the utilities to go for, since the 4 policy statement is not a requirement.
5 MR. WARD: The reg guide's not either.
6 MR. PERSENSKY: And neither is the reg guide.
1 7 But the direction that the Commission indicated in the 8 policy statement is to have them essentially serve on 9 shift.
10 DR. REMICK: Does that mean that somebody can 11 come in and say, "We don't want our people to be actively 12 enrolled in shift activities", and staff will accept it?
13' Under what conditions will they accept it?
(ON 14 MR. PERSENSKY: Given the policy statement as 15 it's currently written, if the utility has an STA program 16 which is approved and all of them are at this point, because 17 we approved them back in '82 and '83, they don' t have to do 18 anything. They can just go on the way they are going.
19 As a policy statement, the Commissioners are only 20 trying to make a statement as to the direction they would 21 like to go.
22 They also made in the same policy statement the 23 comment that they would like them to go towards dual role as 24 an ultimate goal. So there's no enforcement available to us 25 under a policy statement, just a statement of the
( })
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0160 07 08 272 1 DAV/bc 1 Commission's ultimate objective.
()
2 MR. WARD: What about a plant just getting its 3 license? Just an oil plant?
4 MR. PERSENSKY: They have an option of coming in 5 with either one of the plans, under 0737 for STA, they could 6 come in with the traditional STA program. Most of them are 7 not. Most of them are coming toward the dual role.
8 MR. WARD: But you're saying that, right now, the 9 staff might buy off into the old NTOL plan. STA in the 10 bunkhouse?
1 11 MR. PERSENSKY: Yes. The standard also indicates 12 that 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />, 60 college credit hours is sufficient for an 13 STA credit program; 0737 indicates a bachelor's degree or 14 equivalent for maintaining the 0737 requirement. There was 15 some public comment about actively performing the STA
, 16 function. We have defined this as three shifts per quarter 17 in this regulatory guide. They have to at least spend three 18 shifts per quarter, similar to the licensed operator.
19 MR. WARD: I'm not getting picky but, if being in 20 the bunkhouse, does that qualify one? Does three nights in 21 the bunkhouse count?
22 MR. PERSENSKY: If they're under a traditional 23 STA program, it would have to. We did not make any changes 24 to the traditional STA program.
() 25 The next bullet really is that you can combine 1
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0160 07 09 273 DAV/bc 1 the two functions, which is the policy statement, as long as 2 you have the education and training requirements in that 3 policy statement.
4 MR. WARD: Which are not the 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />, not their 5 equivalent.
6 MR. PERSENSKY: An acceptable alternative, and I 7 think since you saw it last, the Commissioners have taken a 8 harder line on the definition of " acceptable alternative".
9 MR. WARD: Yes, we've seen the policy statement.
10 MR. PERSENSKY: I mean, as far as our 11 presentation to you, the Commissioners have taken a much 12 harder line as to the degree requirement. We've also given
,r3 13 a little more specific definition or description of the V
14 training for STA's, which is in the 0737.
15l The next position, B, is actually a carryover 16 from the reg guide 1.8, 1975, which was the radiation 17 protection manager. That was something that was in that reg 18 guide. So we're just carrying it over into this new l
i
! 19 document. And it gives certain qualification and training l
20 programs for that position.
l 21 The final one is that contractor personnel that 22 are filling positions that are described in the standards, 23 if you have a contract trainer on board all the time or a 24 contract operations manager that are filling positions
(')
\..
25 usually held by a utility person, that they must meet ACE-FEDERAL REPORTERS, INC.
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r 0160 07 10 274 DAV/bc 1 those qualifications and training requirements also.
2 MR. WARD: If they're actually filling the 3 position. Let's see. Some NTOL plants have had 4 requirements for advisers on shift for X-months or 5 something. Are there any requirements for those advisers?
6 MR. PERSENSKY: They're not in the standard.
7 Those requirements have been established through generic 8 letter. It's really, at this point, they should have all 9 been phased out. They have not been but, at this point, 10 according to the policy statement -- not policy statement, 11 I'm sorry, the generic letter that was developed in March of 12 1984. In March of '85, there was supposed to be no more 13 shift advisers. But we're finding that the experience (v~~')
14 requirements that that generic letter had have not been met 15 by the industry.
16 MR. WARD: But you're not touching that issue?
17 MR. PERSENSKY: We're not touching that issue 18 because it is in fact a temporary position.
19 The next slide is just a summary of comments. If 20 anybody wants to go into those, I'll be glad to. There was i
l 21 considerable public comment on this issue, and we have 22 taken, I think, the necessary steps to clarify the problems 23 that were laid out by the public in their comment period.
l 24 (Slide.)
() 25 MR. WARD: Where did most of these comments come i
l l
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0160 07 11 275 DAV/bc 1 from?
2 MR. PERSENSKY: Socs of them came directly from 3 reactor operators. They came from a lot of utilities.
4 Susan has her hand up; she knows right off the top of her 5 head.
6 MS. SHANKMAN: Right. I can list all 135 7 letters, but you have a list in the front of Enclosure B and 8 Enclosure C of our packet. So if you're really curious, 9 most of them come from utilities and licensed operators.
10 MR. WARD: Licensed operators as individuals?
11 MS. SHANKMAN: Yes.
12 DR. REMICK: Jay, where in the guide do you give r3 13 the additional information on STA training? Once again, I'm
.L) 14 one slide behind you.
15 MR. PERSENSKY: Page 7.
16 DR. REMICK: The next to the last paragraph?
17 Okay.
18 MR. PERSENSKY: It's not a lot of information.
19 DR. REMICK: I was looking for a big list and 20 couldn't find it. Incidentally, as I look through that 21 guide, almost everywhere, you say " senior operator" and 22 " operator", except when you first start to talk about 23 regulatory positions. In the first sentence, you use 24 " licensed operators". I think if you scratch it there, f')
x.y 25 you're probably okay.
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1 l
l l
0160 07 12 276 DAV/bc 1 MR. PERSENSKY: That's probably my fault. The 2 individual that had bee ~n working on this for the last two or !
3 three years got sick and was not available to do some of 4 these final cleanup things. I ended up doing it my.self.
5 DR. REMICK: Almost all of those paragraphs you 6 say an " operator" or " senior operator". That, I think, is 7 consistent except on page 3 under Licensed Operators, where 8 you define something in the very first sentence.
9 MR. PERSENSKY: I think there it might be 10 appropriate though in that we are specifically calling out 11 the standard. It's the sections of the standard that refer 12 to those positions. I don't know. We'll look at it.
13 DR. REMICK: Okay.
(^;)
x 14 MR. PERSENSKY: Any more questions?
15 MR. WARD: The public comments. Did you get 16 comments from STA's as individuals?
17 MS. SHANKMAN: Unless they identified themselves 18 as such, we really didn't. A lot of them signed the letter 19 just their name and their facility.
20 21 22 23 24
('S 25 U
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0160 08 01 277 DAVbur 1 MR. WARD: I am not really asking if you got one 2 or two.
3 MS. SHANKMAN: We didn't say STAS. They were all 4 sent to licensed operators unless they saw it at their 5 facility or had other communication.
6 MR. WARD: Why was that? Because it talks about 7 requirements for STAS?
8 MS. SHANKMAN: Right. But the licensing package 9 was operator licenses. We just sent it to those that are in 10 our docket. We don't have a listing of the names and 11 addresses of STAS.
12 MR. PERSENSKY: No further questions?
13 Thank you.
(]
v 14 MR. WARD: Anything more?
15 I guess there isn't anything more on the reg 16 guide.
17 Now, you are going to tell us about the next 18 topic, Jay?
19 MR. PERSENSKY: I think Bruce and I . sill sort of 20 be available here to work together on answering questions.
21 Bruce has a brief description of how accreditation 22 interfaces with the rule, and I think you have had some of 23 that already.
24 MR. BOGER: I think we have tried to indicate as i
() 25 we went through the various rules and reg guides that we 1
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0160 08 02 278 DAVbur 1 tried to consider industry initiatives, particularly 2 standards that were endorsed by the community, and also INPO 3 type accreditation.
4 In particular, it is our intent to approve l
5 programs that have been accredited by INPO. That is kind of 6 the baseline for the whole rule package. That is an 7 underlying understanding that we intend on approving 8 INPO-accredited programs.
9 That does not mean that we would not unapprove 10 programs if sometime later during the course of evaluation 11 of the programs we thought that that particular program was 12 not being implemented in accordance with the guidelines of
(~) 13 the accredited program. But it is our intent to accept that V
14 program as the NRC-approved program for licensed operators.
15 DR. REMICK: Is that in the statement of 16 considerations at all?
17 MR. BOGER: Yes.
18 DR. REMICK: It is.
19 MR. WARD: You mean you will double-check, I 20 guess. You will audit it, but you will accept INPO 21 accreditation as prima facie evidence that you ought to 22 approve the program?
23 MR. BOGER: Yes, sir, that is correct.
24 Along with that, of course, we accept the fl 25 requalification program that is part of that accredited a
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0160 08 03 279 DAVbur 1 program. This is reflected in Part 55, where we say you 2 either have an NRC-approved program based on a systems 3 approach to training or you go through the list of elements 4 that used to be in Part 55, Appendix A.
5 In addition to that, we have changed the primary 6 source of examination and information to be the learning 7 objectives that were derived from the accredited training 8 program. So that is another point back to the accredited 9 program. We will base our examinations on those learning 10 objectives.
11 One of the big issues is eligibility. If an 12 accredited program truly is performance based, then the 13 output from that program should be someone that is qualified
{])
14 to hold the job. In recognition of that, we propose to 15 eliminate our eligibility requirements to sit for an NRC 16 exam.
17 You may have noticed up on the slide, a good 18 example of that was the four years of responsible power 19 plant experience. That particular element will go away if 20 someone certifies to us that they have completed an 21 INPO-accredited program that makes use of a simulation 22 facility approved by the NRC.
23 So that is a major concession, in our eyes.
24 License renewal, I think we indicated that the rm
() 25 method by which we will renew someone's license is solely ACE-FEDERAL REPORTERS, INC.
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0160 08 04 280 1 DAVbur 1 dependent upon their cer'tification to us that they have O 2 successfully completed their approved training program.
3 Again, this is what we intended to be the 4 INPO-accredited training program. So we are not going to be 5 looking at particularly the number of hours that someone had 6 to be in training in accordance with Appendix 8. We will be 7 looking at something at the end of the program that said 8 they had met the objectives of their accredited training 9 program, and we will renew the license based on that and 10 satisfactory medical evidence.
11 So that is the major areas where we have tried to 12 accommodate the industry initiatives, in particular in the rm 13 rule change, and some of those are reflected back in the reg O
14 guides, also, particularly the ANS 3.5 standard and the 15 simulator work and the medical standard in Reg Guide 1134.
16 MR. PERSENSKY: With regard to Reg Guide 1.8, as 17 are all reg guides, that is one way of meeting a 18 requirement. What we are saying in the statement of 19 considerations is the other way in many of these issues is 20 through the accredited program.
21 MR. MICHELSON: If you go the route of the 22 accredited program, to what extent would the NRC then audit 23 the results of the accredited program?
24 Right now you are auditing the requalification f~S, 25 process. Presently, you audit the requalifications.
G l
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0160 08 05 281 DAVbur 1 Would you continue to audit the requalification 2 process?
3 MR. BOGER: We are going to have two people talk 4 about this.
5 One way of auditing is, of course, examinations.
6 We are looking at the end products, and our examinations 7 would be some clue as to how well that program was doing.
8 MR. MICHELSON: Would you continue to use NRC 9 examinations, even though the program is accredited by INPO?
10 MR. BOGER: Yes, sir. Our present plans point to 11 *that.
12 MR. PERSENSKY: In fact, the policy statement r')
\ ../
13 calls that out specifically as'a means of monitoring the 14 accreditation program.
15 With regard to the second part of that answer, we 16 are evaluating and monitoring accreditation currently 17 through several different means, one of which is a sampling 18 I of accredited programs where our staff as well as the 19 regions go out and do a post-accreditation review at a 20 utility that has been accredited.
21 There are also other aspects included in the new 22 inspection modules, put out by Inspection and Enforcement, 23 that are done on a regular basis for review of training 24 programs.
f~)
v 25 MR. MICHELSON: Thus far, have you run into what l
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0160 08 06 282 1 DAVbur 1 appear perhaps to be areas of difficulty with the accredited 1
'* 2 programs?
3 MR. PERSENSKY: I would say at this point we 4 haven't gathered enough data.
5 MR. MICHELSON: Thank you.
6 MR. WARD: Could we go back? I just want to 7 check on something we talked about yesterday, the 8 requalification examination schedule, which is going to be 9 the written exam every two years and the oral exam each 10 year.
11 Where does the simulator exam fit in?
12 MR. BOGER: That would be part of the operating p 13 test.
O 14 MR. WARD: That is part of the operating oral?
15 MR. BOGER: Yes.
16 MR. WARD: All right.
17 DR. REMICK: I am sorry, I should have thought of 18 this yesterday. The written and oral exam, is that a 19 requirement for everybody or only those that are under 20 55.59(c)?
21 MS. SHANKMAN: Everybody is under 55.59(c).
22 MR. BOGER: Everyone who holds an NRC license 23 would come under the requirements of the requalificatior.
24 program.
25 DR. REMICK: But you will accept the full ACE-FEDERAL REPORTERS, INC.
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0160 08 07 283 DAVbur 1 accredited requalification program?
2 MR. BOGER: For the content of the program. I 3 think what it says is -- the first two bullets address the 4 verification of competency through examinations.
5 DR. REMICK: I assumed that yesterday, but I just 6 got to thinking today if you are going to accept either/or.
7 But the intent is everybody would have the 8 written exam every two years and the oral every year 9 regardless of whether they are accredited.
10 MR. WARD: Any other questions on the 11 relationship here?
12 Let me ask you here on the relationship with the
{} 13 INPO-accreditation. I hear what you are saying, but has the 14 revision to the rules for ANSI 50 and 55 been influenced by 15 the fact that INPO has developed this accreditation program?
16 Would those rules be different if we were back where things I
17 were three years ago?
18 MR. BOGER: I think when we started off doing the 19 rule change we indicated that the method to be employed 20 should be the systematic approach to training. Those 21 elements should be used in developing training programs.
22 INPO happened to come along at a time that 23 embodied those particular elements, so we saw that as one 24 way for us to address a training program up front. But it
() 25 was always our intent to have that systematic approach to ACE-FEDERAL REPORTERS, INC.
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0160 08 08 284 1 DAVbur 1 training.
k 2 MR. PERSENSKY: If you go back to the original 3 306 response, that is the direction we are going.
4 The actual wording of the rule still requires an 5 NRC-approved program, and we have to get back to the 6 statement of considerations to actually indicate that we are 7 intending to improve the program.
8 Since we are still in this two-year evaluation 9 program, we can't outright say that it is going to be this 10 way completely. That is where we need to retain our 11 approval authority.
12 In addition, it would be inappropriate for us to 13 put in the rulemaking INPO accreditation because that begins 14 to put them in the shoes of the regulator.
15 MR. WARD: Right.
16 Any other questions on this?
17 (No response.)
18 MR. WARD: It looks like that ends the meeting 19 except for our executive session. So we can excuse our 20 reporter at this point and excuse the staff.
21 (Whereupon, at 11:15 a.m., the meeting was 22 adjourned, to reconvene in executive session.)
23 24 25 C)
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CERTIFICATE OF OFFICIAL REPORTER
[v}
This is to certify that the attached proceedings before the UNITED STATES NUCLEAR REGULATORY COMMISSION in the matter of:
NAME OF PROCEEDING: ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEE ON HUMAN FACTORS DOCKET NO.:
PLACE: Washington, D. C.
DATE: Tuesday, November 26, 1985 were held as herein appears, and that this is the original transcript thereof for the file of the United States Nuclear Regulatory Commission.
i s ;
(sigt) mu .
(TYPEDf David L. Hoffman Official Reporter l Ace-Federal Reporters Reporter's Af filiation, Inc. I l
NRR STAFF PRESENTATION TO THE ACRS O
SUBJECT:
REGULATORY GUIDE 1.149 DATE: flovember 26, 1985 PRESENTER: Jerry Wachtel ~
O PR ESENTER'S TITLE / BRANCH /DIV:
Training and Assessment Specialist Operator Licensing Branch Human Factors Safety PRESENTER'S NRC TEL. NO.:
~
492-9695 SUBCOMMITTEE: Human Factors O
O REGULATORY GUIDE 1.149
" NUCLEAR POWER PLANT SIMULATION FACILITIES FOR USE IN OPERATOR LICENSE EXAMINATIONS" ENDORSES ANS 3.5, 1985 WITH EXCEPTIONS PROVIDES 4-YEAR PHASED IMPLEMENTATION PROVIDES SPECIFIC LISTING 0F ABNORMAL / EMERGENCY EVENTS TO BE TESTED TO VERIFY PERFORMANCE PROVIDES GUIDELINES FOR FACILITY LICENSEES WHO WISH TO USE ONE SIMULATION FACILITY FOR MORE THAN ONE UNIT 11/26/85
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v- w w - ?vw-,-ert-- -m- e-M** ** - - - "T'- '--'-N'---- ' ' ' ' " " ' " -- - "-- *-
O REGULATORY GUIDE 1,149 -
MAJOR EXCEPTIONS TO ANS 3.5, 1985 APPLIES TO OPERATING TESTS
-PART-TASK / LIMITED-SCOPE SIMULATORS INCLUDED DEFINITION OF " REFERENCE PLANT" ALSO APPLIES TO UNIT (R.G. INCLUDES PROVISIONS FOR APPLICATION OF A SIMULATION FACILITY TO MULTIPLE UNITS),
SIMULATION FACILITY PERFORMANCE AND OPERABILITY TESTS SHOULD
({}
INCLUDE ALL PROVISIONS OF APPENDICES PERFORMANCE TESTING SHOULD BE PERFORMED 25% PER YEAR OVER A 4-YEAR CYCLE, IN ACCORDANCE WITH A LIST OF TESTS IN THE R.G.
i 4
11/26/85 0
O
O REGULATORY GUIDE 1,149 FOUR-YEAR IMPLEMENTATION PHASE-IN PROVIDE " SIMULATOR INFORMATION" AND " SIMULATOR DESIGN DATA" WITHIN 2 YEARS AFTER E D.R.
CONDUCT AND DOCUMENT " SIMULATOR TESTS" WITHIN 3 YEARS AFTER E.D.R.
- SIMULATION FACILITY TO BE IN FULL COMPLIANCE WITH ANS 3,5 AS MODIFIED BY R.G. 1.149 WITHIN 4 YEARS AFTER E.D.R.
(])
4 0
11/26/85
(])
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.,n.-. -s. . . - - . . - , - , , . , - . - , , , . , , , , - .,-----------.a--, - -,- - - --,-, ,, - - , - -,- - .- ,- ,- - - - , - - -, ,--.m.-,- - ,-
3 0
SIMULATOR STATUS EXISTING 38 (68 REACTORS)
UNDER CONSTRUCTION 28 (37 REACTORS)
BEING CONSIDERED 8 (8 REACTORS)
O
- NO PRESENT PLANS 13 REACTORS 11/26/85 0
e
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TECHNICAL ASSISTANCE CONTRACT IN SUPPORT OF RULEMAKING FOR SIMULATION FACILITIES TITLE: DEVELOPMENT OF AN NRC SIMULATION FACILITY EVALUATION PROGRAM CONTRACTOR: MICR0 ANALYSIS AND DESIGN K. RONALD LAUGHERY, JR. PH.D -
SUBCONTRACTOR: BATTELLE PACIFIC NORTHWEST LABORATORIES PERIOD OF PERFORMANCE:
1 YEAR (BEGAN 9/85) FOR "3.5" PROGRAM OPTIONAL 6 MONTH EXTENSION FOR "NON 3.5" O
- TASKS:
SELECT AND CONVENE STEERING COMMITTEE LITERATURE REVIEW PREPARE STRAWMAN EVALUATION PLAN APPLICABLE T0 "ANS 3.5 - TYPE" SIMULATORS PERFORM SIMULATOR REVIEW TO TEST THC PLAN ,
(OPTIONAL) PREPARE STRAWMAN EVALUATION PLAN FOR "NON-ANS 3.5 TYPE" SIMULATORS (0PTIONAL) PERFORM SIMULATOR REVIEW TO TEST THE PLAN PREPARE FINAL PLAN AND RECOMMENDATIONS 11/26/85
- o
\.
O CONTRACT STEERING COMMITTEE J. MALCOLM BLACK (ANS 3,5 COMMITTEE)
DIRECTOR, NUCLEAR TRAINING NORTHEAST UTILITIES EDWARD M. BOOTHE MANAGER, NATIONAL SIMULATOR EVALUATION PROGRAM FEDERAL AVIATION ADMINISTRATION JULIEN M CHRISTENSEN CHIEF SCIENTIST, HUMAN FACTORS UNIVERSAL ENERGY SYSTEMS O
- ISRAEL GANZ PROGRAM MANAGER, SIMULATOR PROJECTS GENERAL ELECTRIC COMPANY WILLIAM N. GARDNER SUPERVISOR, SIMULATION SYSTEMS COMBUSTION ENGINEERING R. M K0EHLER MANAGER, PRODUCTION TRAINING SERVICES DUKE POWER COMPANY GUS WANNER (ANS 3,5 COMMITTEE) .
VICE PRESIDENT EXITECH CORPORATION 11/26/85 I-
3-//47)K4)hl ANSIIANS 3.41983 4
American National Standard .
Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants "I
a.
Secretariat American Nuclear Society
~
Prepared by the American Nuclear Society Standards Committee Working Group ANS 3.4 l
! Published by the American Nuclear Society i
Approved April 29,1983
- r. by the
\
American An American National Standard implies a consensus of those
' Natimal substantially concerned with its scope and provisions. An Standard American National Standard is intended as a guide to aid the manufacturer, the consumer, and the general public.
The existence of an American National Standard does not in any respect preclude anyone, whether he has approved the standard or not, from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standard. American National Standards are subject to periodic review and users are cautioned to obtain the latest editions.
CAUTION NOTICE: This American National Standard may
- be revised or withdrawn at any time. The procedures of the American National Standards Institute require that action be taken to reaffirm, revise, or withdraw this standard no later than five years from the date of publication. Purchasers of this standard may receive current information, including interpretations, on all standards published by the American
, Nuclear Society by calling or writing to the Society.
(
O Published by
/
American Nuclear Society
, 555 North Kensington Avenue, La Grange Park, Illinois 60525 USA Price: $10.00 Copyright # 1983 by American Nuclear Society.
Any part of this standard may be quoted. Credit !!nes should read " Extracted from American National Standard, ANSI /
ANS-3.4-1983, with permission of the publisher, the Americar-Nuclear Society." Reproduction prohibited under copyrie).t convention unless written permission is granted by the American Nuclear Society.
O Printed ie t8e united States of America \'
C
F
)
T Foreword (This Foreword is not a part of American Natinnal Standard Medical 3
Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants, ANSI /ANS-3.4-1983.)
The organization which operates a nuclear power plant has the responsi-bility for safe and efficient operation of the plant. Inherent in this overall responsibility is the responsibility to select and retain operators and senior operators that are physically capable of such operations.
I The selection of operators and senior operators is of great importance since they perform and direct the manipulations of mechanisms and controls that affect the safe operation of the reactor. This standard provides the minimum requirements necessary for an examining physician
, to determine that the physical condition and general health of the opera-tors are not such as might cause operational errors.
This standard was developed by Working Group ANS-3.4 of the American Nuclear Society Standards Committee which had the participation of the following members during the period it prepared and approved the standard:
R. L. Craig, M.D., Chairman J. L. Craig, M.D.
Tennessee Valley Authority General Mills, Inc.
W. R. Albers, M.D. T. J. Doyle, M.D.
U.S. Department of Energy Consolidated Edison Company P. F. Collins G. A. Poda, M.D.
U.S. Nuclear Regulatory E. I. duPont deNcmours and Commission Company t>
] M. J. Cooney Philadelphia Electric Company The membership of Subcommittee ANS-3, Reactor Operations, at the time of its approval of this standard was:
J. E. Smith, Chairman R. J. Rodriquez
- e Duke Power Company Sacramento Municipal Utility S. E. Br'yan District U.S. Nuclear Regulatory J. D. Shiffer Commission Pacific Gas and Electric F. A. Dougherty D. J. Skovholt Tera Corporation U.S. Nuclear Regulatory N. S. EIIiott Commission Babcock & Wilcox Company E. L. Thomas T. W. Fitzgeraid Institute of Nuclear Power American Nuclear Insurers Operations H. J. Green W. T. Ullrich Tennessee Valley Authority Peach Gottom Atomic Power F. L. Kei1y Station PGA Corporation ~ P. F. Walzer R. L. Ottason Washington Public Power Southern California Edison Supply S> stem r ^ e i- r O Commor vealth Edison Carr any o x w"it" =
Argonne National Laboratory s~
C
l I
s 3
The American Nuclear Society's Nuclear Power Plant Standards Committec (NUPPSCO) had the following mcmbership at the time of its approval of this O standard. k L. J. Cooper, Chairman M. D. Weber, Secretary .
Name of Representative Organization Reprccented R. G. B'enham . . . . . . . . . . . . . . . . General Atomic Company (for the Institute of Electrical and Electronics Engineers, Inc.)
- 8. M. Rice (Alt.) . . . . . . . . . . . . . . . . Duke Power Company (for the Institute of Electrical and Electronics Engineers, Inc.)
- R. V. Bettinger . . . . . . . . . . . Pacific Gas and Electric Company P. Bradbury . . . . . . . . . . . Westinghouse Advanced Reactor Division D. A. Campbell . . . . . . . . . . . Westinghouse Electric Corporation C. O. Cof fer . . . . . . . . . . . . Pacific Gas and Electric Company L. J.* Cooper . . . . . . . . . . . . . Nebraska Public Power District (for the American Nuclear Society)
W. H. D'Ardenne . . . . . . . . . . . . . . General Electric Company
- 5. G. Gorges . . . ,. . . . . . . . . . . . . . . . NUS Corporation C. J. Gili. . . . . . . . . . . . . . . . . . . Bechtel National, Inc.
C. E. Johnson . . . . . . . . . . . U.S. Nuclear Regulatory Commission R. W. Keaten . . . . . . . . . . . . . . . GPU Services Corporation J. W. Lentsch . . . . . . . . . . . . Portland General Electric Company J. F. Mallay . . . . . . . . . . . . . . . . . . NUTECH Engineers * -
(Q L. M. Mills . . . . . . . . . . . . . . .
A. T. Molin . . . . . . . . . . .
. Tennessee Valley Authority United Engineers and Constructors, Inc.
T. J. Pashes . . . . . . . . . . . . . . . . . . . . . . Individual l
, P. T. Reichert . . . . . . . . . . . . . . . . . . . Catalytic, Inc.
S. L. Rosen . . . . . . . . . . . . Institute of Nuclear Power Operations J. E. Smith . . . . . . . . . . . . . . . . . . Duke Power Company J. W. Stacey . . . . . . . . . . . . Yankee Atomic Electric Company S. L. Stamm . . . . . . . . . . Stone & Webster Engineering Corporation l L. Stanley .. . . . . . . . . . . Quadrex/ Nuclear Services Corporation J. D. Stevenson . . . . . . . . . . . . Structural Mechanics Associates
, (for the American Society of Civil Engineers)
C. D. Thomar, Jr. . . . . . . . . . . Yankee Atomic Electric Company G. P. Wagner . . . . . . . . . . . . . Commonwealth Edison Company G. L. Wessman . . . . . . . . . . . . . . . . Torrey Pines Technology J. E. Windhorst. . . . . . . . . . . . . Southern Company Services, Inc.
t
- Formerly with Babcock & Wilcox Company I
l O s.
(
3 CONil'N15 Section Page
+
- 1. Scope . . . . . . . . . . . . . . . . . . . . .
O .
.I
- 2. Definitions . . . . . . . . . . . . . . . . . . . .I 2.1 Limitations . . . . . . . . . . . . . . . . . .1 2.2 Glossary of Terms. . . . . . . . . . . . . . . 1
- 3. Health Evaluation Responsibility . . . . . . . . . . . .I 3.1 General Aspects . . . . . . . . . . . . . . . .I . ,
3.2 Facility Operator's Report to the Designated Medical Examiner . . , . . . . . . . . . . . . . .1
- 4. Medical Examination Frequency . . . . . . . . . . . .2
- 5. Health Requirements and Disqualifying Conditions . . . . *
.2 5.1 Basis of Requirements . . . . . . . . . . . . . .2 5.2 General Requirements . . . . . . . . . . . . . .2 5.3 Di:; qualifying Conditions . . . . . . . . . . . . .2 q 5.4 Specific Minimum Capacities Required for Medical FV Qualifications . . . . . . . . . . . . . . . . .4
- 6. Waiver or Specifically Limited Approval . . . . . . . . .6 6.1 Application Requirements and Criteria . . . . . . . 6 6.2. Specifically Limited Approval . . . . . . . . . . 6 4
- 7. References . . . . . . . . . . . . . . . . . . . .6 e
pO s.
e
Mediccl Certification and Monitoring cf Persnnnel Requiring Operator Licenses 3 for PtcIcar Power Plants I. Scope nucicar reactor. Any assembly of fission-f This standard defines the physical able material which is designed to and mental requirements for licensure * *** ' """ ' '
- '"'"9 as a nuclear reactor operator, m n cha.m mahn.
it also addresses the content, extent, nuclear reactor operator. An individual and methods of examination, who manipulates the controls or directs others to manipulate the controls.
shall, should and may. The word "shall" 2.1 Limitations. The definitions given is used to denote a requirement; the below are of a restricted nature w rd "should" to denote a recommenda-for the purpose of this standard. Li n; and the word "ma y" to denote permission, neither a requirement nor 2.2 Glossary of Terms a recommendation. -
controls. Apparatus and mechanisms 8I pera h n. @ era &n M me cond, the manipulation of which directly #9 *" 9 ** * "
affect the reactivity, power level during steady station operations, with cooling, containment, and other m er quaMed persm b me cmkd requirements for safe operation r m r other specified control areas, of the nuclear reactor. such as the refueling console.
designated medical examiner. A 11- 3. Health Evaluation Responsibility censed medical practitioner designated by the facility operator to perform 3.1 General Aspects. The primary nuclear reactor operator medical responsibility for assuring that qualified examinations. personnel are on duty rests with the
'( disqualifying or disqualifying condition. acility operator. The health require-Something that precludes medical
- approval for nuclear reactor operator * * " * " * * ****'Y * ' "
g'"""* that the phys.ical condit. ion and general health of the individual are not such facility operator. An authorized as might cause operational errors en-representative of a holder of a license dangering public health and safety.
pursuant to Title 10, Code of Federal Regulations, Part 50, " Licensing The designated medical examiner shall of Productipn and Utilization Facil- be conversant with this standard and ities" [1]l, or any government, public, should have a general understanding
. or private organization which is of activities required of a nuclear reactor the owner and operator or is the operator.
designated responsible operator of a nuclear reactor facility. 3.2 Facility Operator's Report to the multi-person facility. A facility where
- 9"* * "'#*
- it is mandatory that more than one facility operator shall forward to the qualified individual be present in the designated medcal exad ner a npM
)
control room or other specified control n each employee referred for sa nuclear areas when the reactor is operating. reactor operator medical examination ,
prior to the examination. This report nuclear power plant. A nuclear shall include information specified power plant is any plant using a by the designated medical examiner nuclear reactor to produce electric and should address areas such as work power, process heat, or space heating. performance, attendance, and behavioral Og Numbers in brackets refer to corre- changes noted since the previous review.
incidents of ineptness, poor judgment, t, spending numbers in Section 7, Refer- and lack of physical or emotional stamina ences. should be noted. Unusual absence or d
y- _ _ , - . - .- -
American National Stendard ANSI /ANS.3.41983 lateness and accident experience should be recorded, individual in question is performing i his assigned duties.
Potential psychological or medical problems that could impair judgment 5.2 General Requirements or ability to perform assignments are more likely to be identified 5.2J Capacity. The examinee shall by the designated medical examiner demonstrate stability and capacity if he is provided with this background for all of the following:
Information. (1) Mental alertness and emotional stabi!ity; -
3 4. Medical Examination Frequency (2) Acuity of senses and ability of express, ion to allow rapid, accurate
) Nuclear reactor operators shall be communication by spoken, written, examined biennially for continued and other audible, visible, or tactile medical qualification. signals; (3) Physique, stamina, motor power,
- 5. Health Requirements and Dis- range of motion, and dexterity to allow qualifying Conditions ready access to and safe execution of ass,igned duties.
5.I Basis of Requirements. The physical condition and the. general 5.2.2 Freedom from Incapacity.
health of nuclear reactor operators The examiriee shall be free of any who have the responsibility for the of the following conditions that are (O safe operation of a nuclear reactor shall be such that they are capable considered by the designated medical examiner as significantly predisposing of properly operating under normal, to incapacity for duty:
abnormal and emergency conditions (1) Mental or physical impairments; and able to perform the associated (2) Any medical, surgical, or other tasks. Consequently, any physical Professional treatment; condition or corrective device that (3) Any . other source or use of restricts the mobility of the individual treatment, drugs, chemicals, diets, or precludes the wearing of protective or other agents; clothing and equifment is a liability (4) Any condition, habit, or practice to safe pperation. Any condition which might result in sudden or u:.ex-that can cause sudden incapacitation pected incapacitat,on. i
' such as epilepsy, mental disorder, diabetes, hypertension, cardiovascular 5.3 Disqualifying Conditions. A history disease, fainting spells and defective or other indication of any disqualifying hearing or vision is also a liability condition shall be considered disqualifying to safe operation. The potential unless adequate supplemental findings consequences of insidious incapacitation demonstrate that no disqualifying con-are most serious in solo operation, - dition exists. Such demonstration shall but shall be considered at any facility. include at least the specific narrative Many of the conditions indicated entries by the designated medical exam-above may be accommodated iner and relevant aspects of medical by history and physical examination. The restricting the activities of the indi- designated medical examiner shall vidual, requirin close surveillance of the condition,gimposing a temporary determine the need for additional exam-O' medical regime, or requiring another ination procedures or specialty evaluations.
The presence of any of the follov.ing individual to be present when the conditions, unless adequately compens:. ed C.
American National Str ndtird AN51/ANS-3.4-1983 by the methods specified in subsections such dutics are within their physical 5.3.1 through 5.3.9, shall disqualify capacity and that such duties and sched-the individual. uling do not interfere with control measures for their diabetes.
5.3.1 Respiratory (b) Stable diabetics adequately (1) Frequent severe attacks e ntr lied by diet or oral medication of asthma within the previous two may be qualified for solo operation.
years or a history that indicates .
Other conditions requ, iring a need for continued or prolonged the continued or frequent use of steroids.
use of medication for relief, preven-tion, or control of attacks; 5.3.4 Integumentary. Recurrent (2) Tracheostomy or laryngectomy; dermatit.is or hypersens.tivity i
(3) Incapacitating chronic pulmo- I****'".tants irri or sensitizers sufficient, nary disease. to in . terfere with wearing of personal protective equipment or likely to be 5.3.2 Cardiovascular aggravated by personal decontamination procedures.
(1) Ischemic heart disease,
% myoc'ardial infarction, coronary insu f- 5.3.5 Hcmatopoletic Dysfunction.
ficiency dr angina pectoris shall disqualify for solo operation. if (1) Polycythemia.
thorough history, phys,ipal examinat,on, i (2) Agranulocytosis.
electrocardiogram (ECG), and other (3) Leukemia and Lymphoma, test procedures in , dicate satisfactory (4) Other significant hematopoietic cardiac function and reserve, the dyscrasia.
(
examinee may be considered for qualification as an operator in a 5.3.6 Malignant Neoplasms. Malignant multi-person f a cility provided ,t i neoplasm shall disqualify unless review is demonstrated that all dutses of of medical history and current medical such an assignment are with,in the evaluation indicate clinical remission phys, i cal capabilities of the examinee. that renders the examinee capable (2) Heart failure. of meeting all other requirements of (3) A r r h y th mia other than this standard.
benign extrasystoles.
(4) Prosthet,c i valve. 5.3.7 Neurological (5) Artificial pacemaker.
(6) Peripheral vascular .insuf- (1) History of epilepsy shall dis-fa,ciency. qualify for solo operation. Examinee (7) Artern.a l aneurysm. may be considered for qualification for a multi-person facility if he has 5.3.3 Endocrine, Nu t ritional, remained seizure free for at least ge previ us Metabolic five years with medication or has remained seizure free during (1) Diabetes mellitus. Uncon- the previous two years without medica-trolled diabetes, ketoacidosis, diabetic tion. Before considering such qualifi-coma, or insulin shock within the cation, history and examination findings previous two years. must document the fact that the residuals (a) Requirements for use of of, or medication to control the seizure insulin shall disqualify for solo oper- disorder do not impair the examinee's ation. Well-controlled stable diabetics capacity to perform all required duties.
who require insulin may qualify for Evaluation at d prognosis by a neurologist C pd a multi-person facility if history should La co: idered.- '
and e xamina tion findings indicate (2) Hist ory of a disturbance of .
American Nation:] Standard ANSl/ANS-3.4-1983 consciousacss within the past five charact er, behavior or personality dis-years without satisfactory medical order including anxiety, obsessive-explanation of the cause shall dis- compulsive, conversion, disassociative, qualify for solo operation. depressive, or phobic reactions shall (3) Organic brain syndrome. disqualify if the designated medical (4) Any other convulsive dis- examiner finds that the condition or order, disturbance of consciousness any treatment thereof makes the exam-or neurologic condition that the inee potentially unable to safely perform designated medical examiner finds all operator duties.
makes the examinee unable to safely perform all operator duties. 5.3.9 Medication. Any m :dication taken in st'ch a dosage that the taking 5.3.8 Mental. An established or temporary delay of taking might history or clinical diagnosis of any be expected to result in incapacity, of the following: for example, certain dosages or require-(1) Any psychological or mental ments for steriods, anticoagulants, condition that could cause impaired antiarrhythmics, sedatives, tranquilizers, alertness, judgment or motor ability or insulin.
shall constitute su f ficient cause for disqualification. A history of 5.4 Specific Minimum Capacities Re-clinically significant emotional or quired for Medical Qualification behavioral problems shall require, thorough clinical evaluation that
, 5.4.1 Head, Face, Neck, Scalp.
f may include, but not necessarily Configuration suitable for fitting and ef fectis e use of g be l,m,iti ed to, psycholog,ical test,ng and psychiatric evaluation.
i equipment.
personal protective (2) A personality disorder that 5.4.2 Nose. Ability to detect odor is severe enough to have repeatedly of goducts of combustion and of tracer manifested itself by overt acts. , or market gases.
(3) History or threat of suicide attempt.
(4) History ,of a psychotic
. 5.4.3 Mouth and Throat. Capacity d,sorder.
i for clear speech.
(5) Alpoholism is used ir' this section to rnean a condit,on ,n which 5.4.4 Ears. Puretone audiometric i i a person's intake of alcohol is great threshold average better than 30 dB enough to damage his physical health, (American National Standard Specifi-cations for Audiometers, ANSI S3.6-1973 and personal or social functioning; [2] or International Organization for or a condit, ion when alcohol has become a prerequisite to his normal Standardization, Standard lieference functioning.
0 for Calibration of Pure Tone Audio-(6) Drug dependence is used meters, ISO 389-1975 [3], for speech in this section to mean a condition frequencies 500, 1000, 2000 Hz in better ear. If audiometric scores are unaccept-in which a person is addicted to, or dependent on, drugs other than able, qualification may be based upon alcohol, tobacco, or ordinary caffeine- onsite demonstration to the satisfaction containing beverages, as evidenced of the facility operator of the examinee's by non-prescribed habitual use of ability to safely detect, interpret, the drug. and respond to speech and other auditory l signals.
p (7) History or presence of I l
v any other clinically significant n ntal, Qualification should be considered if L l
3 American Nations! Standard ANSI /ANS-3.41983 s
c hearing aid is required to meet abnormality, a report of an evaluation hearing requirements.
by a physician proficient in cardiovascular 5.4.5 Eyes.
evaluations shall accompany the medical examination report. This consultation Near and shall include, but is not limited to, (1) distant visual an interpretation of an ECG and chett acuity 20/40 in better eye, corrected X-ray.
or uncorrected.
(2) Peripheral visual fields 5.4.8 Abdomen and Viscera. If hernia by confrontation to 1200 or greater. is present it shall be adequately supported (3) Color vision adequate to by appropriate device or not be of distinguish among red, green, and such nature as to interfere with the orange-yellow signal lamps, and performance of assigned duty or present any other coding required for safe significant potential for incapacitation.
operation of the particular facility as definsd by the facility operator. 5.4.9 Musculo-skeletal. Normal (4) Adequate depth perception, either by stereopsis or secondary symmetrical structure, range of motion and power. If any impairment exists, clues as demonstrated by practical
- the applicant shall demonstrate ability test.
to effectively complete all expected duties.
5.4.6 Respiratory. Capacity and reserve to perform strenuous 5.4.10 Skin. Capability to tolerate physical exertion in emergencies, use of personal protective and ability to utilize respiratory covering (7
(V protective filters and air supply and decontamination procedures.
masks. Pulmonary function studies 5 .4 .11 Endocrine, Nutritional, Meta-
, that include a forced vital capacity bolic. Normal. Ability to change sched-and forced expiratory volume I second would be helpful to the at ule or delay meals without potential incapacity.
examining physician in determining the candidate's ability to perform 5.4.12 Hematopoietic. Normal' function.
assigned work. --
5.4.13 Lymphatic. Normal function.
5.4.7 Chrdiovascular. Normal configuration and furiction including 5.4.14 Neurological. Normal central normal blood pressure with tolerance and peripheral nervous system function.
to postural changes and capacity Tactile discrimination (Stereognosis) for exertion during emergencies, sufficient to distinguish among various The examining physician shall report shapes of control knobs and handles whether asymmetrical neck and by touch.
peripheral pulses or resting pulse rates less than 50 or more than 5.4.15 Psychiatric. Normal mental 100 beats per minute are normal status including orientation. Ability for the individual and of ne signifi. to function in emergencies and unusual cance. If the examination reveals environments such as:
i significant cardiac arrhythmia, murmur, confined or crowded spaces, alone 'in darkness, untreated hypertension (over 160/100 on elevations, on open metal grids, mm Hg), intolerance to postural and on ladders.
changes, cardiac enlargement or This ability is to be determined by the clinical judgment other avidence of cardiovascular
((q ./
of the examining physician.
I
, Americcn Natinnal Standard ANSI /ANS-3.41983 5.4.16 Laboratory. be reasonably expected to be affected O (1)
~
Normal hemoglobin, white bx the im nairmenti
{
blood cell count, and differential. (4) Certification from the desig-nated medical examiner and facility (2) In urinalysis, absence of operator indicating that the individual proteins and glycosuria unless the can safely perform his assigned duties, absence of a disqualifying systemic or genitor-urinary condition has 6.2 Specifically Limited Approval.
been demonstrated. Examinees who do not meet all require-(3) Normal ECG. ments for either qualification or waiver (4) Other medical investigative for unrestricted nuclear reactor operator procedures, including chest X-ray, that the designated medical examiner duties may request specifically limitei'l approval. Consideration of any such considers necessary for adequate medical evaluation.
request shall require the facility opera-for's concurrence and recommendations and all other information necessary
- 6. Waiver or Specifically Limited for a waiver application (::ce 6.1). The Approval facility operator shall also propose 6.1 Application Requirements and the exact wording of any such specific limitation.
Criteria. if an examinee fails to meet any of the above specified minimum requirements but can demon- 7. References strate to the satisfaction of the facility operator complete capacity [1] Title 10, Code of Federal Regulations to perform operational duties, the Part 50 " Licensing of Production
\ designated medical examiner may and Utilization Facilities," Govern-i recommend waiver of that portion ment Printing Office, Washington, of this standard. It is the examinee's D.C.
responsibility to supply additional information necessary for consideration [2] American National Standard Specifi-of the granting of such a waiver. cations for Audiometers, ANSI Documentation supporting the waiver 53.6-1973. American National
- shall include
- Standards Institute, Inc., New York, (1) Medical history and results N.Y.
of physical examina' tion ar.d other
. pertinent medical findings; [3] International Organization for (2) Specific statements by Standardization, Standard Reference the designated medical examiner as to the individual's capacity and 0 for Calibration of Pure Tone Audiometers, ISO 389-1975. Amer-the potential effects of any medical ican National Standards Institute, impairment on the individual's ability Inc., New York, N.Y.
to perform nuclear reactor operator duties; When the preceding American National (3) Description by the facility Standards referred to in this document operator of specific practical tests are superseded by a revision approved and demonstrations of ebility to by the American National Standards perform those duties which might Institute, Inc., the revision shall apply.
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, NRR STAFF PRESENTAT!ON TO THE O ACRS .
SUBJECT:
REGULATORY GUIDE 1.8
" Qualification and Training of Personnel for Nuclear Power Plant" DATE: November 26, 1985 PRESENTER: J. J. Persensky O' l i
PRESENTER'S TITLE / BRANCH /DIV: Section Leader Licensee Qualifications Branch l Division of Human Factors Safety PRESENTER'S NRC TEL. NO.: 492-4892 i SUBCOMMITTEE: Human Factors O
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I REGULATORY GUIDE 1,8 i !
- REVISION 2 i QUALIFICATION AND TRAINING 0F i
O PERSONNEL FOR NUCLEAR POWER PLANTS
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i 11/26/85 0
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- REGULATORY GUIDE 1.8 ENDORSES, WITH CLARIFICATIONS, ADDITIONS, AND EXCEPTIONS, ,
ANSI /ANS 3.1-1981 FOR R0, SRO, AND SS
-* SUPPORTS PROPOSED CHANGES TO 10CFR 55 PROVIDES CLARIFICATION FOR STA POSITION
(])
CONTINUES ENDORSEMENT OF ANSI /ANS N18.1-1971 FOR ALL OTHER POSITIONS (R.G. 1.8-1975)
LIMITED BY COMMISSION POLICY STATEMENT ON TRAINING AND QUALIFICATIONS l[ .
11/26/85
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REGULATORY GUIDE 1,8 IMPLEMENTATION & APPLICATION THE METHOD DESCRIBED IN THIS GUIDE WILL BE USED 1 YEAR AFTER ITS '
PUBLICATION IN THE EVALUATION OF:
THE QUALIFICATIONS & TRAINING REQUIREMENTS FOR NPP PERSONNEL
(]) AS DESCRIBED IN OPERATING LICENSE APPLICATIONS THE QUALIFICATIONS 8 TRAINING REQUIREMENTS FOR APPLICANTS FOR R0 & SR0 LICENSES THE QUALIFICATIONS & TRAINING REQUIREMENTS FOR REPLACEMENT PERSONNEL IN POSITIONS NOT YET ACCREDITED BY INP0 11/26/85 0
O REGULATORY GUIDE 1,8 LICENSED OPERATORS (R0, SRO, SS) - ENDORSES 3,1-1981 WITH THE FOLLOWING EXCEPTIONS, CLAR ADDITIONS REGULATORY POSITION 1 a. COLD LICENSE APPLICANTS - MUST MEET ALL THE
" i- OBJECTIVES INCLUDED IN THE NRC APPROVED COLD m j TRAINING PROGRAM p % = 1., :'~ ~~;.~ 4 '
'C~"~ ~ c. THE EDUCATIONAL REQUIREMENT FOR SS AND SR0 I 3y~:fgp56 g)gMQW _p HIGH SCHOOL DIPLOMA j d. INCREASE OF POWER PLANT EXPERIENCE FOR SRO F YEARS.
- d. AT LEAST 6 MONTHS OF THE 2 YEARS NPP EXPERIE APPLICANT SHOULD BE AT THE PLANT FOR WHICH T SEEKS A LICENSE
- d. SRO APPLICANTS (WITHOUT A DEGREE IN ENGINEEF EQUIVALENT) SHOULD HAVE HELD AN OPERATOR'S L ACTIVELY PERFORMING LICENSED DUTIES FOR AT L O
O REGULATORY GUIDE 1.8 LICENSED OPERATORS (CONT'D)
REGULATORY POSITION 1 e. TRAINING IN THE CONTROL & MITIGATION OF ACCIDENTS IN WHICH THE CORE IS SEVERLY DAMAGED
- f. TRAINING ON SHIFT AS AN EXTRA PERSON FOR 3 MONTHS FOR R0 &
SR0 APPLICANTS 9 HOT LICENSE APPLICANTS - MANIPULATION OF CONTROLS DURING A MINIMUM 0F 5 SIGNIFICANT REACTIVITY CHANGES O h. COLD LICENSE APPLICANTS - 6 MONTHS PRACTICAL WORK ASSIGNMENTS
- 1. DESCRIPTION OF PERFORMANCE-BASED REFRESHER TRAINING FOR LICENSED OPERATORS WHO HAVE NOT BEEN ACTIVELY PERFORMING LICENSED FUNCTIONS
- 1. DESCRIPTION OF PLANT REVIEW 8 CERTIFICATION OF LICENSED OPERATORS RETURNING TO LICENSED FUNCTIONS
- 1. CRITERIA USED BY NRC TO EVALUATE THE PLANT'S CERTIFICATION OF THE RETURNING LICENSED OPERATOR i
I i
11/26/85 0
O REGULATORY GUIDE 1.8 POSITIONS OTHER THAN LICENSED OPERATORS-ENDORSES, ANSI N18,1-1971 WITH THE FOLLOWING EXCEPTIONS, CLARIFICATIONS AND ADDITIONS REGULATORY POSITION 1 b. & STA IS REQUIRED ON ALL SHIFTS AND SHOULD ASSUME AN ACTIVE 2 a. ROLE IN SHIFT ACTIVITIES 2 a. STA SHOULD HAVE A BACHELOR'S DEGREE IN ENGINEERING OR A RELATED SCIENCE
({) a. DESCRIPTION OF " ACTIVELY PERFORMING" STA FUNCTIONS
- a. STA & SR0 FUNCTIONS MAY BE COMBINED IF PROVISIONS OF THE POLICY STATEMENT ON ENGINEERING EXPERTISE ON SHIFT ARE MET
- a. DESCRIPTION OF SPECIFIC TRAINING FOR THE STA
- b. DESCRIPTION OF QUALIFICATIONS, TRAINING & EXPERIENCE FOR THE RPM
- c. CONTRACTOR PERSONNEL - MEET QUALIFICATIONS REQUIREMENTS OF POSITIONS THEY COVER 11/26/85 O
O REGULATORY GUIDE 1.8
SUMMARY
OF PUBLIC COMMENTS
- 1. CLARIFICATION OF WHAT POSITIONS WILL BE COVERED BY R.G. 1.8
- 2. DELAY R.G. 1.8 UNTIL A NEW VERSION OF ANSI /ANS 3.1 IS PUBLISHED
- 3. INP0 ACCREDITATION PROCESS IN LIEU OF NUREG-0737
- 4. DELETION OF COLLEGE CREDIT REQUIREMENTS FOR OPERATORS
- 5. EXPERIENCE REQUIREMENTS FOR SR0s IN NUREG-0737 ARE OVERLY RESTRICTIVE O 6. INSTRUCTOR CERTIFICATION
- 7. CLARIFICATION OF STA POSITION
- 8. CLARIFICATION OF REACTIVITY MANIPULATIONS
- 9. CLARIFICATION OF PRACTICAL WORK ASSIGNMENTS
- 10. CLARIFICATION OF " ACTIVELY PERFORMING" THE FUNCTIONS OF AN OPERATOR i
11/26/85 l
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ANS-3.5 kDRKING GTiOUP Page 1 of 24 6 FINAL DRAFT RFNTSTON OF ANST/ANS-3.5-1981 ANSI /ANS-3.5-1985
,[
American National Standard Nuclear Power Plant Simulators -
for use in Operator Training O
Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Conunitteo Working Group ANS-3.5 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park. Illinois 60525 Approved month day. 1985 by the American National Standards Instituto. Inc.
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ANS-3.5 kORKING GROUP Page 2 of 24 FINAL DRAFT REVISION OF ANST/ANS-3.5-1981 O tere era <*is vere ~ era is =et Power Plant Simulators a=rt forer ^Use erica"in" tie = 1 sta a ra "ecie r Operator Training, ANSI /ANS-3.5-1985).
Nuclear Power plant simulators 1 nuclear power plant operators: have become an important tool in training of training programs has resultedAcceptance of the use of simulators in operator in the need minimum standard configuration and performance of such a unit.for a standard describing the is he obj ectivo of this criteria necessary to specify minimum for effective simulator performance and configuration training.
It is not for an effective operator training program.the intent of this standard to individual organizations It is the responsibility of the -
to operate and maintain the nuclear facility, and how must be determined by each party.
the jobto esta is accomplished
'Ihe standard has been revised to incorporate expanding knowledge con capabilities, use, design, and updating of nuclear power plant simulators that has been developed in the years since the previous revision.
been given been provided to theto effects of improvements made in simulators. Consideration aid users Appendices have has simulators. in maintaining simulator data and in testing of j
When a simulator is
- O reseir meets set ferta i= tais sta aara.used in an operator training program, it shall m Working Society Group had ANS-3.5 the following of the Standards Comit tee of the American Nuclear membership:
N S El11ott. Chairman, Babcock t- WI1cox Company J C Velotta Vice-Chairman, Flvrida Power & Light Co -
i T Dennis, Secretary, Pennsylvania Power & Light Company
( J M Black Northeast Utilities Service Company B A Boger, U S Nuclear Regulatory Comission .
l i J H Harris, Comonmwealth Edison Company R A Johnson, Interfacts, Inc J W Lehner, Tennessee Valley Authority M F Reisinger, Electronic Associates, Inc P J Swanson, Public Service of New Hampshire D L hames, General Physics Corporation -
G H Wanner, The Singer Company - LINK SSD R M Wyatt, General Electric Company Certain hJghly technically qualified individuals provided additional expert assistance standard. h ey and advice to the working group during the development of the are:
W F Fernow, Arizona Public Service, Company W M Guinn, Institute of !!uciear Power Operations i
O. e M He s. o
- aio e e " tie > t 8eraterv J P Jankovich, U S Nuclear Regulatory Comissfon L.
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ANS-3.5 WORKING GROUP Page 3 of 24
,' FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 O
N B Kraje, Babcock & Wilcox Company E W Merschoff, U S Nuclear Regulatory Comission . '
J P Sursock, Electric Power Research Institute -
'1he membership of Subcomi ttee ANS-3,ReactorOperations,hadkhefollowing membership at the time of its approval of this standard:
D H Beckham, U S Nuclear Regulatory Comission s A Dougherty. Utility Services N S Elliott Babcock & Wilcox Company T W Fitzgerald, American Nuclear Insurers H J Green. Tennessee Valley Authority E Jackson, Vermont Yankee Nuclear Power Corporation T Murray, Toledo Edison ,
V Poeppolmeier Institute of Nuclear Power Operations R J Rodriguez, Sacramento Municipal Utility District D Roth, General Physics Corporation J D Shiffer, Pacific Gas & Electric J E Smith, Duke Power Company J M Taylor, U S Nuclear Regulatory Comission W T Ullrich, Philadelphia Electric Company P F Walzer, Public Service Electric & Gas Company
. M D Weber, American Nuclear Society
, G K Whitham, Argonne National Laboratory i
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- 2. .
ANS-3.5 WORKING GROUP Page 4 of 24 t
FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 The American Nuclear Socloty's Nuclear Power Plant Standards Committoo (NUPPSCO) had the following membership at the time of its approval of this standard.
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Name of Representative................................ Organization Represented L J Cooper, chairman...........................
M D Weber, secretary. . . . . . . . . . . . . . . . . . . . . . . . . . . Nebraska Public Power Dis tri ct
'e
......American Nuclear Society i R F V Bettinger .................................. Pacific Gas & Electric Company Boorboor..................... United Engineers and Constructors Incorporated i
R J Breen ......................
- W S Brown ...................... ............ ... Electric
........ Westinghouse Power Research Electric Corporation Institute .
, CO JD Coffer.......................... ...
....... Pacific Gas & Electric Company Crawford............................ .. Combustion Engineering Incorporated W H D'Ardenne ................... .................... General Electric Company S B Gerges.......................
CJ .............................NUS Corporation G111.........................
C E Johns on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Bech t el N4. t i ona l , Incorpora t ed R T Lance t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . U S Nucl ear Regul a t ory Comi s s i on JF Mallay......................... ..Rockwell International Corporation f
L M Mills .........................................
P Morlette(non-balloting)
Tennessee Valley Authority
( C Morrell(Alternate)........................... ..............................
C Nguyen(non-balloting) ... Stone & Webster Engineering PT Reichert...................................................................DAS/BRTSN WM ............Stearns Catalytic, Incorporated Rice.......................... ...........................................
- (for the Institute of Electrical M O Sanford ...........................and Electronics Engineers Incorporated)
............ ....GPU Nuclear Corportion J E Smith (Alternate)............................... ........ Duke Power Company-S L S t am . . . . . . . . . . . . . . . . . . . . . . . . . . .
J D Stevenson ....................... ............. Stone & Webster Engineering
..................Stevenson & Associates T J Sullivan......................(for the American Society of Civil Engineers)
C D Thomas . . . . . . . . . . . . . . . . . . . . . . ...... . . . . . . . Ins t i tut e of Nucl ear Power Opera tions W T Ullrich ............................ ....... Yankee Atomic Electric Company G P Wagner.................... ........ Philadelphia Electric Company G L Wes sman . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Comonweal th Edi son Company J E Windhorst ............................................Torrey Pines Technology G A Zimmeman . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Southern Company Servi ces 1
1
.......... Portland General Electric Company 1
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ANS-3.5 kORKING GROUP Page 5 of 24 FINAL DRAFT REVISTON OF ANST/ANS-3.5-1981 Contents Section......................................Page
- 1. Scope...................................... 6 :
1.1 Background............................. 6 1'
- 2. Definitions............................... 6
- 3. General Requirements....................... 9 3.1 Simulator Capabilities................. 9 3.2 Simulator Environment................. 12 -
3.3 Systems to be Simulated and the Degree of Completeness................ 12
, 3.4 Simulator Training Capabilities....... 13 s
- 4. Performance Criteria...................... 14 4.1 Steady State Operation................ 14 4.2 Transient Operation................... 14 4.3 Simulator Operating Limits............ 15 4.4 Monitoring Capability................. 15
- 5. Simulator Design Control.................. 16 5.1 Simulator Design Data................. 16 5.2 Simulator Update Design Data.......... 16 5.3 Simulator Modifications............... 16 5.4 Simulator Testing..................... 16 j 6. References................................ 17 l
l
! Appendix A Guide for Documenting Simulator Performance..................... 18 Appendix B Simulator Operability Tests..... 21 i
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ANS-3.5 h0RKING GROUP Page 6 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 Nuclear Power Plant Simulators for use in Operator Training
- 1. Scope This standard establishes the minimum functional requirements for full-scope nuclear power plant control room simulators used for operator training. Criteria are "
established for degree of simulation, perfonnance, and functional capability of
) instrumentation and controls. the simulated control room address simulators for test, mobile This standard does not and research reactors, or reactors not subj ect to U. S. Nuclear h -
Regulatory
.- Coninission (NRC) licensing. Also excluried are part-task or limited scopo simulators intended for or familiarization. specialized training g This standard does not establish
- criteria training for use of simulators in training programs. The criterion is established in ANSI /ANS-3.1-1981 j
(American National Standard for Selection and Training of Nuclear Power Plant Personnel).
1.1 Background. .
Operating and training practices differ among reactors; the however, various organizations that operate nuclear power coninon goals are assurance of safety, equipment availability, and efficient operations. It is intended that this and use of a nuclear power plant simulator. standard provide flexibility in design It is intended that in meeting the criteria of this
- standard, the simulator possess a sufficient degree of completeness -
- and accuracy to meet the needs of industry and the requirements of NRC as described in Title 10, Code of Federal Regulations, Part 55, " Operators' Licenses", and American National Standard for Selection and Training of
[ Nuclear Power Plant Personnel. ANSI /ANS-3.1-1981.
. 11.2 11
- 2. Definitions backtrack. Restoration of the simulator to a previous set of conditions that have been automatically recorded at designated time intervals. ,
l best estimate. Reference plant responra Q a based upon i
t engineering evaluation or operational asses. ment.
2 Numbers in brackets refer to corresponding numbers *n l Section 6 (References).
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ANS-3.5 kORKING GROUP Page 7 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 O
computed values. Physical parameters calculated by the simulator mathematical models and stored in computer memory. . ,
critical parameters: .
(1) Those parameters that require d? rect and; continuous 7. -
observation to operate the power plant ur.dcr manual control.
(2) Input parameters to plant safety systems, freeze. A condition whereby the dynamic simulation is interrupted and remains static until the simulator is taken out of the " freeze" mode, at which time dynamic simulation resumes.
full scopo simulator. A simulator incorporating detailed modeling of systems of the reference plant with which the operator interfaces in the control room environment. The control room operating consoles are included. Such a simulator demonstrates expected plant response to normal and off-normal conditions.
functionally simulated hardware. Hardware which has
() dynamic interface with the real time simulation.
Initialization condition. A set of data that represents the status of the referenced plant from which real time simulation can begin.
limited scope simulator. A simulator incorporating limited modeling of a generic plant or subsystem design. Such a simulator demonstrates basic operational principles. -
malfunction. Failure or degradation in performance of plant equipment.
, operational control panels.1 Panels that enable the
- operator at the controls to perform required manual
! safety actions and equipment surveillance and to monitor plant conditions under normal and accident conditions, i
operator-training. That training given to t
prospective and licensed nuclear power plant reactor operators and senior reactor operators to meet the requirements of 10 CFR 55, and ANSI /ANS-3.1-1981.
() (1.2 1
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AMS-3.5 WORKING GROUP Paga 8 of 24 FINAL DRAFT REVISION OF ANST/ANS-3.5-1981 .
O va ive tr=#ctie"- Ta e r iiure usca ae et become evident to the control room operator until ' - -
the affected system is called upon to function.
part-task simulator. :
A simulator incorporating '
detailed trodeling of a limited ntsnber of specific reference plant components or subsystems. Such a simulator demonstrates expected response of those components or subsystems.
real time. Simulation of dynamic performance in the same time base relationships, sequences, f durations, rates and accelerations as the dynamic performance of the reference plant. -
reference plant.
g The specific nuclear power plant from which the simulator control room configuration, system data control arrangement and simulator design is derived.
shall, should and may.
The word "shall" is used to denote a requirement; the word "should" to denote a recomendation; and the word "may" to denote permission, neither a requirement nor a recomendation, snapshot.
The instantaneous storage of existing conditions at any selected point in time. The stored condition then becomes a temporary initialization point and may be called up repeatedly.
visually simulated hardware. Hardware which is present on the reference plant control panels but -
i has no dynamic interface with the real time simulation (for example, square root converters.
sumers) and is present on simula'.ed hardware for visual orientation only.
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ANS-3.5 WORKING GROUP Page 9 of 24
.- FINAL DRAFT REVISTON OF ANSI /ANS-3.5-1981 O
- 3. General Requirements The nuclear power plant simulator is intended to be used -
primarily as a training device to provide initial and .
requalification training for nuclear power plant operators. .-
h e simulator may also be used as an examination tool. The simulation of the control room equipment, plant systems, and plant operation shall be as described in the following 4
paragraphs. h e extent of simulation shall be such that the operator is required to take the same action on the simulator to conduct an evolution as on the reference plant using similar procedures. The extent of simulation shall permit control of simulated tr.inslents to a steady state condition, provided that the sim lator operating limits (Section 4.3, Simulator Operating Lin.its) are not exceeded.
3.1 Simulator Capabilities. h e response of the simulator j resulting from operator action, no opertitor action, improper operator action, automatic plant controls and inherent operating characteristics shall be realistic to the extent that within the limits of the perfomance criteria (Section j 4. Perfomance Criteria) the operator shall not observe a difference between the response of the simulator control room instrumentation and the reference plant.
O a11 ser i ri =i svei=ti # - n capable of simulating continuously, and in real time, plant 1 i i r a ti de operations of the reference plant. He simulator shall
- calculate plant system parameters corresponding to l
particular operating conditions, display these parameters on the approplate instrtsnentation, and provide proper alarm or protective system action, or both. The minimum evolutions that the simulator shall be capable of perfoming, using only operator action normal to the reference plant, are as ~
follows:
(1) Plant startup -
cold to hot standby. The starting conditions shall be cold shutdown conditions of temperature and pressure. Removal of the reactor vessel head is not a required condition for simulation; (2) Nuclear startup from hot standby to rated power:
(3) Turbine startup and generator synchronization:
l (4) Reactor trip followed by recovery to rated power:
(5) Operations at hot standby:
(6) Load changes; (7) Startup, shutdown and power operations with less than -
full reactor coolant flow *
(8) Plant shutdown from rated power to hot standby and cooldown to cold shutdown conditions:
(9) Core performance testing such as plant heat balance, de of shutdown margin, and measurement of -
O retermination ciiviiv coerrici permanently installed instrtsnentation:
- - a#a co trei rea woria # i e (10) Operator conducted surveillance testing on safety-related equipment or systems.
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ANS-3.5 kORKING GROUP Page 10 of 24 FINAL DRAFT RLNISION OF ANSI /ANS-3.5-1981 O,' 3.1.2 Plant andsystematic a numberprocess of malfunctions to be simulated should bo part o --
operator training curricula. for designing performance-based process should utilize: The malfunction assessment s:
(a) Licensee Event Reports (particularly like-plant):
(b) Probabilistic Risk Assessment studies; (c) NSSS and BOP manufacturer equipment availability / reliability data and technical service bulletins: information (d) experiences:local site considerations and plant-specific operating I
The(c) NRC bulletins and circulars.
' abnormalsimulator and shall be capable of simulating, in real timo, -
emergency events including malfunctions to demonstrate control functions. inherent plant response and automatic plant Each type of accident analyzed in the reference plant safety analysis report that results in
? observable for indications on control room instrumentation and training shall be simulated.which the simulator is determined to be appropri Where the operator actions are a function of the degree of severity of the malfunction (e.g., loss of condenser vacuum, steam line break coolant, degraded feed water flow, etc.),
loss of
(^T shall have adjustable ratas for the malfunctionthe simulator
\/ range to represent of such a the plant malfunction conditions. The .
remaining events shall consist of a variety of nulfunctions associated with the electrical, auxiliary, engineered safety features systems, steam systems, reactor coolant system, and instrumentation and control systems.
The (1) malfunctions Loss of coolant: listed below shall be included: -
(a) significant PWR steam generator leaks:
(b)
(c) inside and outside primary containment:
large and small demonstration of saturation condition: reactor coolant breaks including (d)
(2) Loss failureof of safety and relief valves:
l t
system or individual headers can loseinstrument air to the extent that the whole pressure and affect
( the plant's static or dynamic performanco:
(3) Loss or degraded electrical including loss of offsite power. loss power to the station, l
loss of of emergency power,
' electrical distribution busesemergency generators, loss of power to the plant's individual instrumentation buses and loss of power to the (AC provide power to control room indication as well as DC) that or plant control functions affecting the plant's response:
i (4) Loss of forced core coolant flow due to single or multiple pump failure:
O (5) Loss levol control:of condenser vacuum including loss of condenser
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ANS-3.5 WORKING GROUP Page 11 of 24 FINAL DRAPT REVISION OF ANSI /ANS-3.5-1981
,.O (6) Loss of service water or cooling to individual components: . ,,
(7) Loss of shutdown cooling:
(8) Loss of component cooling system or , cooling to :
Individual components: 1' (9) Loss of normal feedwater or normal feodwater system failuro; (10) Loss of all feedwater (normal and emergency);
(11) Loss of protective system channel:
(12) Control rod failuro including stuck rods, uncoupled .
rods, drifting rods, rod drops, and misaligned rods:
(13) Inability to drive control rods:
(14) Fuel cladding failure resulting in high activity in .
reactor coolant or off gas and the associated high radiation alarms:
~
(15) Turbine trip:
(IG) Generator trip:
(17) Failure in automatic control system (s) that affect reactivity and core heat renoval:
(18) Failure of reactor coolant pressure and volume control systems (PWR):
(19) Reactor trip; (20) Main steam line as well as main feed line break (both
(~) inside and outside containment):
(_/ (21) Nuclear instrumentation failure (s):
(22) Process instrumentation, alarms, and control system failures:
(23) Passive malfunctions in systems, such as engineered
, safety features, emergency feedwater systems:
(24) Failure of the automatic reactor trip system:
, (25) Reactor pressure control system failure including
- turbine bypass failure (BWR)
The response of the simulator shall be compared to actual plant response or best estimate plant response (see Section 4 Performance Cri teria) . Safety analysis calculated response is based on conservative initial conditions and assumptions and may not accurately reflect realistic plant response. Comparing simulator response to safety analysis results may show significant discrepancies which shall be resolved based on best estimate results. Where applicable to the malfunction the simulator shall provide to the operator the capability of taking action to recover the plant, ,-
mitigcte the consequences, or both. The sliulation shall be capable of continuing until such time that a stable, controllable and safe condition is attained which can be continued to cold shutdown conditions, or until the simulator operating limits (Section 4.3, Simulator Operating Limits) are reached.
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ANS-3.5 WORKING GROUP , Page 12 of 24 FINAL _DRATT REVISION OF ANSI /ANS-3.5-1981 3.2 Simulator Environment 3.2.1 Degree of Panel Simulation.
contain sufficient operational panelshtoe simulator provide shall the controls, instrumentation, alarms, -
interfaces to conduct the normal plantand other man-machine evolutions of 3.1.1 (Normal Plant Evolutions) and respond to the malfunctions of ,
3.1.2 that (Plant Malfunctions). h e control panels and consoles shape, are simulated color, shall be designed and configuration to duplicate the size, of the simulated hardware of the referenco plant. functionally deviations in dimensions and arrangement of panelsThere may be provided
- these deviations 3.2.2 Controls on Panels. do not detract from training.
's n o controls on panels and .
consolcs the that are simulated shall be designed to duplicate size,
' shape, color, and
, configuration of the functionally Consideration should simulated hardware of the reference plant.
b: given to face-front visual
!} simulation panels butofnot hardware used components located on simulated by the trainee during training. All functionallythat replicate simulated and visually simulated hardware shall may be dimensional in the reference plant control room. here
, deviation in the configuration of components and instrumentation, provided these deviations do not impact on actions to be taken by the operator.
O infom tion shall form and units that are available inbe displayed to the operator in the same Plant Meters, recorders, switches, annunciatiors, the reference plant.
! controllers, plant computer interface hardware and other components or displays that would function during normal, abnormal, and emergency 3.2.3 Control evolutions shall be included in the simulator.
Room given to simulating as much of the control rocenEnvironment. Consideration sh as environment is reasonable and practical, for example, turbine noise, control lighting.rod stop counter noise, flooring, obstructions and Comnunication systems that a control room operator would use to connunicate ~with an auxiliary operator or other support activities shall be operational to the remotethat extent the simulator activities, shallinstructor, be when performing these appropriate connunication system.able to communicate over the 3.3 Completeness Systems to be Simulated and the Degree of 3.3.1.
Systems Controlled from the Control Room. he inclusion of systems of the reference plant and the degree of simulation shall be to the extent necessary to perform the reference plant evolutions described in 3.1.1 Plant Evolutions), (Normal
' O <ri
- a ir="ctio==>-and the malfunctions described in 3.1.2 control manipulations it "eit 8 Pe 181 i aere r *" -
and observe plant responso as in the
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ANS-3.5 WORKING GROUP Page 13 of 24 FINAL DRAFT REVISION OF ANST/ANS-3.5-1981 O
reference plant. This shall include system interactions with other simulated systems and shall provide total system Integrated response. ..
3.3.2. Systems Operation or Functions Controlled Outside :
i of the Control Room. The systems that are operated outside the control room or that provide some input to the j simulation models and are necessary to perform referenco plant evolutions described in 3.1.1 (Normal Plant Evolutions) and malfunctions described in 3.1.2 (Plant Malfunctions) shall be simulated. The simulator trainee -
shall be able to interface with the remote activity in a similar manner as in the reference plant.
l 3.4. Simulator Training Capabilities. The simulator shall contain:
3.4.1. Initial Conditions. The simulator shall possess a minimum capability for storage of 20 initialization conditions. At the time of commencement of operations of the simulator in the training program, a minimum of ten initialization conditions shall be operational and shall ,
include a variety of plant operating conditions, fission l product poison concentrations, and various times in core life.
3.4.2. Malfunctions. It shall be possible to conveniently insert and terminate the plant malfunctions specified in 3.1.2 (Plant Malfunctions). The simulator shall be capable of simulating simultaneous or sequential malfunctions, or both. If these malfunctions can be expected to occur by design or operational experience. The introduction of a malfunction shall not alert the operator to the impending malfunction in any manner other than would occur in the reference plant. Provision shall be made for ,
incorporating additional malfunctions identified from .
operational experience and not included in 3.1.2 (Plant Malfunctions).
3.4.3. Other Control Features. The simulator shall have -
the capability of freezing simulation. In addition, consideration should be given to incorporation of fast time, slow time, backtrack, and snapshot capabilities.
3.4.4. Instructor Interface. The capability sha.11 be provided for the instructor to act in the capacity of auxiliary or other operators remote from the control room; for exampl.e. change the operating conditions of valves, breakers or other devices.
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IF ANS-3.5 WORKING GROUP Page 14 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981
() 4. Performanco Criteria 4.1. :
Steady Stato Operation. The simulator accuracles shall 7. '
be related which validto full power values and interim powcr levels for parameters displayed on the reference plant information is available. The
, control panels may have the
' instrument error added to the computed values.
tasting, the accuracy of computed values shall be determinedDuring i
for a minimum of three points over the power range:
(1) The simulator instrument error shall be no greater than that of the comparable meter, instrument system of the reference plant: transducer and related (2) Principal mass and energy
' satisified. Examples are: balances shall be power: (a) Net NSSS thermal power to generated electrical (b) Reactor coolant system temperature generator pressure: to steam (c) Feedwater flow to reactor thermal power:
(d) Mass balance of pressurizer:
(e) Mass balance of steam generator:
The simulator operation with computed values for steady state, full power the reference plant O configuration control shall be stable and not vary more than 12% of the initial values over a 60-minute period; system (3) The simulator computed values of critical parameters shall agree within 12% of the reference plant parameters and shall parameters not are: detract from training. Some examples of critical (a) Reactor thermal power:
l (b) Reactor hot and cold leg temperatures; _
(c) Feedwater flow:
(d) Steam pressure:
(e) Generated electrical power:
(f) Recirculation flow:
(g) Reactor coolant system pressure.
(4) The calculated pertinent to plant operation, values of noncritical parameters simulator control room that are included on the the reference plant parameters an shallpanels, shall agree within 110% of training. not detract from 4.2 Transient Operation 4.2.1 Tests shall be conducted to prove the capability of the simulator to perform correctly during the limiting cases of those evolutions identified in 3.1.1 (Normal Plant Evolutions)
Acceptance and 3.1.2 (Plant Malfunctions) of this standard.
Os applicable, becriteria the samefor these tests shall: (a) where acceptance critoria: as plant startup test procedure (b) require that the observable change
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- l ANS-3.5 WORKING GROUP Page 15 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 {
In the parameters correspond in direction to those expected from a best estimate for the simulated transient and do not i violate the physical laws of nature: (c) require that the ' '
simulator shall not fall to cause an alarm or automatic .
action if the reference plant would have caused an alarm or ._ !
automatic action, and conversely , the simulator shall not cause an alarm or automatic action if the reference plant would not cause an alam or automatic action.
4.2.2 Malfunctions and transients not tested in accordance
^
with 4.2.1 shall be tested and compared to best estimate or other available information and shall meet the acceptance criteria of 4.2.1(b) above.
4.3 Simulator Operating Limits. Mathematical equations may be simplified to meet real time simulation requirements. In addition, it is sometimes possible to create events on a simulator which progress beyond plant l design limits.
Examples of such events include primary containment failure, gross core damage, and reactor coolant system two-phase ilow.
In order to avoid negative training which could result from simulator operation during such events, administrative controls or other means shall be provided to alert the instructor when certain parameters approach values indicative of events beyond the implemented model or known plant behavior. Conditions to be considered are:
(1) Primary containment pressure greater than design '
limit:
4 (2) Reactor coolant system pressure greater than design limit:
1 (3) Fuel temperature histories indicative of gross fuel failure:
(4) Reactor coolant system pressure versus temperature -
relationship indicative of gross voiding:
(5) BWR suppression pool temperature greater than the highest value at which condensation instability is known not to occur; 4
4.4 Monitoring Capability. It shall be possible to obtain hardcopy transient data in the fom of either plots or printouts for critical parameters during the evolutions of 3.1.1 (Normal Plant Evolutions) and the malfunctions of 3.1.2 (Plant Malfunctions). ~1his monitoring chpability t shall provide sufficient parametric and time resolution to '
detemine compliance with the performance criteria of section 4 (Perfomance Criteria).
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ANS-3.5 WORKING GROUP Page 16 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981
- 5. Simulator Design Control Simulator design control provides a means for initial and operator verification ongoing training.
of simulator performance for use in i' Simulators constructed within the guidelines of this standard shall be based on actual or predicted piant configuration and performance. Appendix A (Guide for Documenting Simulator Performance) provides examples of acceptable performance documentation.
5.1 Simulator Design Data. The simulator design data forms the basis for existing simulator configuration. This data base may include predicted plant performance until the reference plant has been in commercial operation for 18 months. After this period, available actual plant configuration and performance data shall be included in the simulator design data. -
5.2 Simulator Update Design Data. The simulator update design changes. data forms the basis for future simulator design This data base shall include available plant data within 18 operation months after the reference plant.is in commercial or date, whichever !swithin 18 months of the simulator operational
() shall be later. Reference plant modifications reviewed at least once per year and the simulator update design data shall be revised as appropriate based on engineering and training value assessment.
Student feedback should be evaluated as part of the review process.
5.3 Simulator Modifications. The simulator shall be -
modified as required within 12 months following the annual establishment of the simulator update design data referenced ,
in section 5.2 (Simulator Update Design Data).
Simulator modifications may precede based on training value. reference plant modifications 5.4 Simulator Testing 5.4.1 Simulator Performance Testing. Simulator performance shall performance test.
be established by preparing a simulator conducting the tests, and comparing the simulator's performance with the simulator design data within the requirements of section 4 (Performance Criteria).
Testing shall be the following conGucted and a report prepared for each of occasions:
(
(1) Completion of initial construction; b
ANS-3.5 WORKING GROUP Pagn 17 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 (2) If simulator design changes result in significant simulator configuration or performance variations.
khen a limited chango is made, a specific performance test -
on the affected systems and components shall be performed. 1' 5.4.2 Simulator Operability Testing. A simulator operability test shall be conducted annually. The intent of this test is to:
(1) Verify overall simulator model completeness and integration:
(2) Verify simulator performance against the steady state criteria of section 4.1 (Steady Stato Operation);
(3) Verify simulator performance against the transient criteria of section 4.2 (Transient Operation) for a benchmark set of transients.
Appendix B (Simulator Operability Tests) provides examples of acceptable simulator operability tests. The simulator user should substitute other applicable steady state and transient operability tests if those tests provide a more representative comparison to actual or predicted reference plant performance. A record of the conduct of this test .
shall be maintained.
- 6. References i (1) Title 10. Code of Federal Regulations. Part 55, " Operator's Licenses". Government Printing Office. W ashington, D.C.
(2] American National Standard for Selection and Training of Personnel for Nuclear Power Plants. ANSI /ANS-3.1-1981 American
' Nuclear Society. La Grango Park. Ill.
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ANS-3.5 h0RNING GROUP Page 18 of 24 l FINAT, DRAFT REVISTON OF ANST/ANS-3.5-1981
.O APPENDIX A (This 3' Simulators for use in Operator Training, ANSI /ANS-3.5-198 for information purposes only.) but is included a
Guide for Documenting Simulator Performance A. Purpose lhe j
6 of thata simulator's conformance to the requirements of ANS-3.5. pur provide a sufficient basis for It is intended the I documentation simulator performance. verification of A1. Simulator Information.
The intent of this section O i "i=* r o A1.1 General 2*= < eret 99 tica'i22*v 9r* r *r >ai a v "> 2 -is to provide familiar (1) Owner / Operator / Manufacturer g
(2) Reference Plant / Type / Rating (3) Date Available for Training (4) Type of Report
- Initial or date of Standard Compliance
- Update A1.2 Control Room -
Comparison to Reference Plant with emphasis on differences:
(1) Control Room Physical Arrangement; (2) Panels / Equipment:
(3) Systems:
(4) Simulator Control Room Environment:
A1.3 Instructor Interface List:
(1) Initial Conditions:
(2) Malfunctions (Specify adjustable rates):
(3) Controls provided for items outside Control Room:
A1.4(4)Operating Additional special instructor / training features available Procedures for Reference Plant.
Itjicate significant difference between the simulator procedures and reference plant procedures .
A1.5 It'?ntify changes'since last report.
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ANS-3.5 kDRKING GROUP Page 19 of 24 FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 O A2. Simulator Design Data
> The intent is to present the complete data from which th'e s'imulator was designed, on which upgrading has been and may be based, and which. correlation will be shown. As such, it is necessary to provide listings of the data P utilized to support construction of the simulator and define the reference d
plant. Many times, simulators are constructed far in advance of the reference l
power plant's operation. In those cases, comparison of response to design data for similar type plants may be used during verification testing. When these comparisons are used, any data should be identified and referenced as to its applicability for the simulator. Examples of the design data include:
(1) Technical manuals listed by name, vendor and document identification:
(2) Drawings listed by maj or type and subsection. Within each type and .
subsection drawings are identified by generating body, drawing number, and drawing revision:
(3) Power plant data utilized in the simulator should be categorized, properly identified, and incorporated into the design data . Examples of such items are:
- Process computer listings:
- Recorder strip charts:
- Design calculations:
- Analytical data (accident analysis):
(4) Applicable plant modifications incorporated into the simulator
- Plant or utility identification of plant modification package:
l
- Date incorporated and models affected:
- Supporting test data and verification:
A3. Simulator Tests.
"The intent of this section is to demonstrate compliance with the documentation requirements of the standard by comparison of simulator performance with the data base where applicable. Testing of a simulator falls into four major categories. In each category, test procedures should be generated to establis5 criteria for those tests.
(1) Computer Real Time Test:
(2) Steady state and nonnal operations:
.(3) Transient tests:
(4) Malfunction tests.
A3.1 Computer Real Time Test Test the computer complex for verification of real time simulation:
l A3.2 Steady State and Normal Operations Tests (1) Stability of the simulator is demonstrated by establishing a steady state condition and monitoring parameter variation with respect to time. Documentation of steady state operation may be logged via strip charts, line printer listings or similar means.
I (2) Demonstrate the ability to operate the simulator in accordance with
! similar reference plant operating procedures. Combinations of logs, data sheets, test procedures, strip charts, and line printer listings may be used to verify simulator compliance.
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ANS-3.5 WORKING GROUP Paga 20 cf 24 FINAL DRAFT RINISTON OF ANST/ANS-3.5-1981
.O A3.3 Transient Tests .
Transient tests of the simulator fall into two areas: 1) Comparison to transients which have occurred in the reference plant and for wh3ch data is available: 2) Transients which fall into the realm of accidents or major occurrences and for which no actual reference plant data exists.
(1) Transient tests verify adequate capability of the simulator to reproduce the defined transients. Many of these tests are introduced via malfunctions but the intent of the transient test is to verify simulator response and not to test the malfunction. Transient test responses may be compared to:
(a) Actual plant results: .
(b) Analytical or design data:
(c) Results from similar plants: ,-
(2) Compare transient tests for which no design data or actual plant response is available to best estimate. FSAR transients are based on
" worst case" situations and as such may be inappropriate for real-time dynamic simulation comparisons.
A3.4 kblfunction Tests Test each generic . malfunction and document utilizing a procedure which identifies and predicts the plant response based on actual plant experience or best estimate, and verifles proper simulator response and system interaction.
() A4. Simulator Discrepancy Resolution and Upgrading Describe program for:
(1) Identifying, logging, correcting, and testing reported simulator discrepancies:
(2) Tracking of design changes incorporated into the reference plant but not yet incorporated into the simulator.
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ANS-3.5 WORKING GROUP Page 21 of 24 FINAL DRAFT RFNISION OF ANSI /ANS-3.5-1981 O
APP 2NDIX B
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(This Appendix is not a part of American National Standard Nuclear Power Plant Simulators for use in Operator Training. ANSI /ANS-3.5-1985, but is included for Information purposes only.)
Simulator Operability Tests .
B. Purpose Ihe purpose of this appendix is to provido examples of tests, paramotors to be recorded, and time resolution for demonstration of simulator operability. The example tests documented herein will clarify the scopo and intent of simulator operability testing required by section 5.4.2 (Simulator Operability Testing). ,
Bl. BkR Simulator Operability Test.
Bl.1 Steady state performance. Record the following data at thoso power O 2evei rer aica he=t 8=1 #ce e te i #er tiv >i die or recere the a t= t approximately 25%, 75%, and 100" rated thermal power. Verify simulator stability at 100% rated thermal power for 60 minutes.
(1) Primary plant:
- Neutron flux (%):
- Core thermal power (%);
Individual Recirculation loop flows:
- Total core flow: .
- Reactor domo pressure: ,
- Reactor water level:
- Total steam flow:
- Total feedwater flow;
- Control Rod Drive Hydraulic System flow and temperature:
- Reactor Water Cleanup System inlet and return flows:
- Reactor Water Cleanup return temperature.
(2) Secondary plant:
- Secondary plant heat balance data:
Bl.2 Transient Perfomance. Run the following set of transients from an initial condition of approximately 100% power, steady state xenon and decay heat with no operator followup action (unless otherwise noted):
(1) Manual scram:
(2) Simultaneous trip of all feedwater pumps:
(3) Simultaneous closure of all Main Steam Isolation Valves:
O (4) si =>t=#ee#- tria er 11 recirc#i ti== 9 n :
(5) Single recirculation pump trip; (G) Main turbine trip (maximum power level which does not result LT imediate reactor scram): g.
ANS-3.5 WORKING GROUP Page 22 of 24 l
FINAL DRAFT REVISION OF ANSI /ANS-3.5-1981 ~
() (7) Maximum rate power ramp (master recirculation flow controller in (8) Maximum " manual") down to approximately 75% and back up to 100%:
size ..
offsite power: reactor coolant system rupture combined with loss of all (D) Maximum size unisolable main steam line rupture: 1' (10) Simultaneous closure single stuck open safety / relief valvo.of all Main Steam Isolation Valves co pressure Faergency Core Cooling Systems). (Inhibit activation of high Bl.2.1 For transients Bl.2(1), Bl.2(2), Bl.2(3), Bl.2(6), and Bl.2(7) recor the 0.5 secondsfollowing set of parameters simultaneously versus time with a nresolutio or less: of
.!i
- Reactor power (% neutron flux):
- Total steam flow:
- Total feedwater flow:
J ,
- Wide range reactor pressure:
- Narrow range reactor pressure:
i
- Wide range reactor water level:
- Narrow range reactor water level (feedwater control):
k
- Generator gross electrical power:
i
- Turbine Steam Flow;
- Total core flow:
t
- Total recirculation loop flow;
() Bl.2.2 For transients B1.2(4) and Bl.2(5),
paraneters record the following set of simultaneously with a resolution of 0.5 seconds or less:
Reactor power (% neutron flux):
Total steam flow:
- Total feedwater flow:
Narrow range reactor pressure:
- Narrow range reactor water level (feedwater control):
Total core flow:
Individual recirculation loop flows: -
Individual calibrated jet pump flows:
- Bl.2.3 For transients Bl.2(8), Bl.2(9), and Bl.2(10),
parameters
- Reactorsimultaneously power (% neutron versus flux): time with a resolution of 0.5 seconds or less: r Wide range pressure:
Wide range water level:
Fuel zone water level:
Total steam flow:
Total feedwater flow:
Containment temperature:
Suppression pool temperature:
z Containment pressure:
Drywell temperature:
Drywell pressure:
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ANS-3.5 WORKING GROUP Pago 23 of 24
, FINAL DRAFT REVTSION OF ANSI /ANS-3.5-1981 O
V
- Total low pressure injection flow:
Total low pressure coro spray flow: - ..
- Total ~ high pressure injection flow.
B2. PWR Simulator Operability Test B2.1 Steady State Performance. Record the following data at those power sy levels at which heat balance data is normally available, or record the data at approximately 25%, 75%, and 100% rated thermal power. Verify simulator stability at 100% rated thermal power for 60 minutes.
(1) Primary plant: -
- Neutron flux (%):
- Core thermal power (%);
.
- Tc (all loops):
- Th (all loops):
- Tav:
- Boron concentration:
- Pressurizer pressure:
- Pressurizer level:
- Pressurizer tenporature:
- Control rod positions:
(~) (2) Secondary plant:
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- Steam generator secondary side level, pressure and temperature:
- Secondary plant heat balance data.
B2.2 Transient Performance. Run the following set of transients from an initini condition of approximately 100% power, steady state xenon and decay heat with no operator followup action (unless otherwise noted):
(1) Manual reactor trip:
(2) Simultaneous trip of all feedwater pumps: .
(3) Simultaneous closure of all Main Steam Isolation Yalves; (4) Simultaneous trip of all reactor coolant pumps (5) Trip of any single reactor coolant pump; (6) Main turbine trip (maximum power level which does not result in immediate reactor trip): -
(7) Maximum rate power ramp (100% down to approximately 75% and back up to 100%);
(8) Maximum size reactor coolant system rupture conioined with loss of all offsite power:
, (9) Maximtsn size unisolable main steam line rupture:
(10) Slow primary system depressurization to saturated condition usfr.g pressurizer relief or safety valve stuck open. (Inhibit activation of high pressure Emergency Core Cooling Systems):
B2.2.1 For transients B2.2(1), B2.2(2), B2.2(3), B2.2(4), B2.2(6), and B2.2(7), record the following parameters simultaneously 'versus time with a resolution of 0.5 seconds or less:
O
- Neutron flux (%):
- Average temperature;
- Pressurizer pressure:
ANS-3.5 WORKING CROUP
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- Pressurizer level:
l
- Pressurizer tenperature: ,,
Total steam flow (if available);
Total feedwater flow (if available)
- Hot leg tempora *ure (any single loop):
- Cold leg temperature (same loop as hot leg temperature);
Steam generator level (same loop as hot leg tanpera B2.2.2 For tr.nsient B2.2(5),
versus
- time with a resolution of 0.5 seconds or less: record the following paramet i
- Neutron flux (%)
- For both affected and unaffected loops:
Hot leg temperaturo; -
Cold leg temperature:
Steam generator secondary pressure; Steam generator level;
- Steam generator steam flow (if available);
Steam generator feedwater flow:
l B2.2.3 For i transients B2.2(8) and B2.2(L),
simultaneously Pressurizer versus time with a resolution of 0.5 seconds or less: record the follo pressure:
l
- Narrow range pressurizer pressure:
l Pressurizer level:
Containment pressure:
Containment temperature; i
B2.2.4 For transient B2.2(10), record the
( following parameters
! simultaneously
- versus time with a resolution of 0.5 seconds,or less:
l
- Relief valve flow (if available);
Pressurizer pressure: -
Pressurizer femperature:
Pressurizer level:
Loop flow rates:
Surge line temperature: *
- Hot leg temperature (surge line leg):
Source range monitor output;
- Reactor vessel level (If available):
Saturation margin monitor output (if availablo).
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L-ANSI /ANS 3.11981 I
O American National Standard ,
for Selection, Qualification and Training of Personnel for Nuclear Power Plants O
Secretariat '
American Nuclear Society Prepared by the American Nuclear Society -
Standards Committee Working Group ANS 3.1 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park. Illinois 60525 USA Approved Deccmber 17,1981 by the American National Standards Institute. Inc.
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America n ^= ^==ic== Nadonal Stand =d impu.s a cons.asus of tho.e suostadany can.
O Nationai corned with its scope and provisions. An Amencan National Standard is intended
, , ,,ia,to ,ia 3, ,,,,,,,,,,,,,t3, . ,,,,,,3,,,,,,,3 ,,33, 73, Standard =,istene. of an Amancan Nadonal Standard does not in any respect p anyone, whether he has approved the standard or not, from manufadaring, marketing, purchasms, or using products, processes, orrA not co%
to the standard. Amancan Nadonal Standards are subject to penodic rwiew and users are cautsoned to obtain the lasset editions.
CAUTION NOTICE: This American Nadonal Standard may be revised or with.
drawn at any time. The procedures of the Amencan Nadonal Standards Inecitute require that aedon be taken to reaffirm. revise or withdraw this standard no later than five years from the date of publicadon. Purchasers of this standard may receivs surrent i.iformadon. including interpretation, on all scandards published by the Amancan Nuclear Society by calling or writing to the Society.
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I Published by Amestean Nuclear Society ,
556 North Kensington Avenue, La Grange Park. Blinois 60625 USA Pricae 32S.00 Copyright c 1981 by American Nuclear Sodety.
Amy part of this Standard may be quoted. Credit Hess should read "Essected from Amenma .
National Standard A1.SI/ANS.3.11981 with W- - of the publisher, the Aasencea Narinar Souscy ** Reproduction prohibited under copyright coevencion unless wntsaa par.
museos is grensed by the Amancea Nuclear Somecy Printed in the United States of America
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F o re w o rd t"'hise.,s.nn.1 Forewordfo,isx..i.a, not ago..,
partgranta.
of American xxS1,433 Nationa1 3.1 1 Sta,n.dard 1., for Selection. Quahfication and Trauung o The personnel of the operating organization who have the responsibility for the safe and efficient operation of a nuclear power plant throughout its operationallifetime must understand the complexities of the plant design and must be capable of pro-perly manipulating the plant controls and maintaining and repaanng the plant equip-ment. '
The selecdon of the operadng and support personnel for nuclear power plants and the training of these personnel to provide, sound judgment, based on knowledge and ex-perience of nuclear and power plant systems, are essential to the safe and successful operation of these plants.
This standard contains criteria for selection, qualificadon and training of nuclear power plant personnet This standard was revised as required by procedures of the -
American Nadonal Semndards Institute and updated to factor in lessons learned from the Three Mile Island Unit 2 incident es well as Ansg regulatory re-quirements. Major chanps were made to several sections throughout the standard.
A new definition was added for startup testing and new plant posidons and their associated experienci. mtv ements were added for Training Manager, Shift Super-visor, Senior Operator, i r. uperational Testing Personnel, Start Up Testing Person-nel. Traimng Instructor, Shift Technical Advisor, Trammg Coordinator, Non-Licensed Operators, and L ensed Operators. .
The Shift Techmcal Advis 's position is indicated as being a temporary operating O
staff position in this staa .ard since Subcommittee ANS 3, Reactor Operations, believes that for the long erm the line organization of shift management must be tramed to fulfill this need. ' Te STA is therefore considered to have a narrow scope of responsibility concentr- . on plant transient analysis and response, recognition of degradation of safet- system and core cooling parameters and advising the shift supervisor regarding cevective acdons that should be taken to maintain core cooling and keep the plant in 4 safe condition.
A new paragraph was added to 3.1 requiring job overlap for personnel being replaced in the station organi:s. tion. A major addidon was made to 4.1 which provides guidance for the selection of those rare, exceptional individuals who have demonstrated outstanding management ability yet do not possess the formal educa-tion reqmrements specified in the standard. These individuals, however, have addi-tional experience, training and educadon that is considered equivalent to that re-quir.4 a meet the quahfications of a particular position. Some colleges and univer-sities now give nuclear power plant personnel college credits for many of the struc-tured courses given in the plant trainimr programs. These recognized college level courses provide an incentive for employees to pursue academic degrees and enhance their job qualificadons.
The entire Section 5 Traming, has been revised and more detailed guidance is provid-ed for the plant traimag programs. The major revision consists of requiring task analysu, as the basis for traming programs. Several other changes have been made throughout this revision which are too numerous to describe in this foreword:
therefore, the user should compare each section against the comparable secdon of ANSI /ANS 3.11978 to determine all of the detailed changes that have been made.
t c . _ _ _ - _ _ _ _ _ - _ _ - - _ _ _ _ _ _ - _ - _ - - . .. ._ _
A revised appendix has been provided as an example of a typical Nuclear Regulatory Comnussion (NRC) approved licensed candidate trainmg program.
- Several issues were raised by the ANS Nuclear Power Plant Standards Committee INUPPSCO) members that voted " negative" initially on this draft of the standard.
In order to reaolve these issues they were deferred for consideration and action to the next standard revision when more information will be available from work now under way at the Institute of Nuclear Power Operations (INPO) and within the utility in-dustry on job task analysis. hoe analysee will have the potential to affect the cducation, experience and training requirements set forth in Seedons 4, Qualifica-dons. and 5. Traming.
These issues were as follows:
- 1. Alternatives for educational requirements.
- 2. Differences in requirements for " hot" and " cold" license training.
- 3. Review of the collective gnatifiention of the plant staff by work groups. .
- 4. The need for and implementation of the team training concept, particularly in the operating organization.
- 5. The type of ==ninations that should be given following each training module in Section 5.
- 6. The need forinteraction between NSSS suppliers and architect engmeers durmg the course of traimng.and retraming programs.
The membership of ANS.3, Reactor Operations, at the time of its approval of this standard was:
J. E. Smith. Chairman. Duke Power Company *F. A. Palmer. CommonweshA Edison Company G. C. Andognial Aosson Edison Company W. J. Ritsch. EDS Nuclesa lac.
I S. E. Bryan U.S. Nue'aer Reguissory Consus. R. J. Rodriques. Secremesso X ase pal Ugary sian Dissnet W. W. Crouch. Power AusAodry of the Sasse of D. J. Skovheit. U.S. Naciner Regulosory Com.
New Yore mission F. W. Dougherty. EDS Nuclear lac. J. Shstfer. Pheitte Gas & Eleesne Company N. Elliott. The Babeoe4 & Wileas Company P. Snyder. Ameneen Nuclearlasurses H. Falter. Power Systems.A Mordsen Knudsen E. L Thomaa. Inssisuse of Nuclear Power 0 pere.
Division siens H. J. Green. Tennessee Valley AutAodry W. T. UDrich,PeacA Aorsom Asemic PowerSte.
F. L KeUy Personnel Quaktfeation Services aion H. L Ottamon. SousAern Cali/pende Edison Com- G. K. Whitham. Argonne NesionalLe6 oratory peny P. Walaer. Combusnon Engineenng. Inc.
"F. A. Pahner served a's director for the effort to produce this revimon.
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The American Nuclear Society's Nuclear Power Plant Standards Committee (NUPPSCO) had the following membership at the time cfits approval of this stan-dard.
J. F. Mallay, Chairman M. D. Weber, Secretary Name of Repreeentative Organssation Represented G. A. Arlotto . U.S. Nuclear Retsdatory Commission R. G. Bonham . . . ..
. . . . . . . . . . . . . . . General Atomic Company
~
the the Insa'tute of Elecencal and Electronses Enyneers Inc.)
R.E. AlleaVslt.) . . United Enoneers & Constructors. Inc.
..... ...Ihr the insatute of Electneal and Electronics Enpneers lacJ R. V. Bett.inger .. Pacise Gas andElecme Company P.Bradbury . Westinghouse AdvancedRosetorDiension D. A. Campbell .. . Wesanghouse Ewerne Corparation C. O. Cotter .KaiserEnoneers L J. Cooper .... ......Nebrus&a P:sblic PowerDistner W.H.D'Ardenne . . Genera!Eleetne Company C. J. Gill. . . . .BechtetPowerCorporenen l A.R Kasper . Com6usnon Enoneering. Inc.
l R.W.Keeten . . . . . . . . GPUServicts Corporenon J. W. Leatsch . . Portland GeneralElectric Company J. T. Mallay . . . . .Babcoch & Wileas Company the tAs American Nuclear Soesetyt A.T.Mc?~ . United Enoneers and Consermeters. Inc.
J. H. Nobw . . . Chas T. Main. Inc.
E. P. O'Donnell . ....... .Ebasco Services. Inc the the Atomic Industnel Forums
, T. J. Paeboe . . QuadrwNuclear Services Corporanon l P. T. Reschert . . . . . . . . Catalyue. . lac.
M. E. Realey .RockweilInterneaanal
, J. E. Smith . . .. . Duke PowerCompany l J.Stacey ... Yankee Asomic Eleeme Company
\ y S. L Stamm . . Stone & WebsterEngineenngCorporenon L J.Staank . . . . Babcock & Wileas Company J. D. Stevoooon .. . . . . .StructuralMeekenies Associates ihr aAe Ameriesn Society of Ciud Enonnerso G. W asaer . Commonwealth Edison Compsny G. L Wes. sa . .. . . .Torrey Pines Technology J. E. Winahorst . .. ...... Soushern Company Services. Inc the the American Soesery of Mechanscal Engineerst E. R. Wlos . .NUS Corporenen L
Selection, Qualification and Training of Personnel -
O for Nuclear Power Plants
- 1. Scope licensed operator. Any individual who possesess an operator's license pursuant to Title 10.
This standard provides criteria for the selection. . " Energy." Code of Federal Regulations. Part 55.
qualiEcation and trauung of personnel for sta- " Operators' Licenses." [2]
tionary nuclear power plants. QuallHeations, responsibilities, and traimng of personnel in licensed senior operator. Any individual who operating and support orgamzations ap- possesses a senior operator's license pursuant to propriate for the safe and efficient operation of 10 CFR Part 55. [2]
nuclear power plants are addressed. Re- -
quirements for security forces are spec 15ed in nuclear power plant. Any plant using a nuclear ,
American National Standard Industrial Securi- reactor to produce electric power, process steam ty for Nuclear Power Plants. N18.171973 or space heating.
(ANS 3.3). [1]2 Test, mobile, and research reac-tors as well as reactors not subject to Nuclear nuclear power plant experience. Experience ac-Regulatory Commission (NRC) Licensing are ex- quired in the preoperational and startup testing cluded because of differences in operational activities, or operation of nuclear power plants.
ractices and contnctual reqmrements. Experience in derign. construction. and opera-tional traimng may be considered applicable
- ndividual job titles and orgamzational struc- nuclear power plant experience and should be
- res vary among organizations operating evaluated on a case by-case basis.
ower reactors: therefore this standard is (1) Experience acquired at* military, non-edicated on levels of responsibility rather stationary, propulsion, or production nuclear Q '
an on a particular organizational concept. plants may qualify as equivalent to nuclear power plant experience on a two forone time beeis up to a mazunum of three years. (Two
. Definitiona years of such experience equals one year nuclear power plant experience.)
The definitions given below are of a restricted . (2) Traimng may qualify as equivalent to nature for the purpose of this semndard. nuclear power plant experience if acquired in reactor simulator *.aining programs to a max-academic training. Successfully completed imum of three month's credit.
college level work leading to a recogmzed degree (3) On-thejob training may qualify as in a disopline related to the position in quandon- equivalent to nuclear power plant expe-ience on a one for one time basis for y to a mammum of experience. Applicable work in design, construc- two years credit.
l tion. preoperational and startup testing l activides, operation. maintenance, onsite ac- nuclear reactor. Any assembly of fissionable civities, or technical services. Ob.ervadon of material which is designated to achieve a con-others performing work in the above areas is not trolled, self sustauung neutron chain reaction.
experience.
offeite personnel. Those personnel providing high school diploma. High school diploma or technical and operational support and not re-successful completion of the General Education porting directly to the plant manager. These Development (GED) test. personnel may be located on or offsite.
onsite personnel Those personnel that are INumbers in brackets refer to corresponding unznbers in assigned to the site as their normal work loca-Secuan 6. References. tion.
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l Amancas Nuional Standard ANSI /ANS 3.11981
. on-thejob training. Participation in nuclear the specific organization that must be establish-
. power plant startup. operation, maintenance, or ed for nuclear power plants, or to completely technical services as a trainee under the direc- define the responsibilities of each level of an tion of asperienced personnel orgamzation. In evaluating the ability to ac-complish required activities, both the onsite and ,
owner organizadon. The orgamzation, including offsite capabilities of the operating orgamzation '
the onsite operating orgamzation, which has shall be considered.
overall legal, h==ri=1 and technical respon-sibility for the operation of one or more nuclear Personnel temporarily filling posidons due to power plants. This includes contracted person- absences of the principal may not meet the nel literal requirements of this standard. Use of per-sonnel to fill a position for which they do not I power plant experience. Experience acquired in meet the minimum requirements set forth in the testing, operation, and maintenance of this standard, is permissible on a justifiable power generating facilities. Experience in basis ordinarily not to exceed three continuoua ,
design and construction may be considered ap- months, and shall not be used as a means of plicable power plant experienca and should be reducing the level of minimum qualifications evaluated on a case-by-case basis, which the following paragraphs establish as be-ing acceptable. The personnel filling positions related technical training. Formal traimag due to the absence of a principal shall, as a beyond the high school levei in techmen! sub- nummum, possess the qualifications of the next jects associated with the position in question. Iower level in that field. This does not apply to such as acquired in traimng schools or programs posidons requinng active NRC senior operator conducted by the military, industry, utilities, or operator licenses or where otherwise stated in universities, vocational schools, or others. Such this standard.
training programs shall be of a scheduled and planned length and include text material and When personnel are to be replaced, a reasonable O lectures. amount of job ovulap should be provided such that the new personnel have an adequate shall, should and may. The word "shall" is used understanding of their new duties and respon-to denote a requirement; the word "should" to sibilities prior to assuming these duties.
denote a recommendation: and the word "may" to denote permission, neither a requirement nor b collective qualifications of the plant staff a recommendation. shall be greater than the sum of the minimum in-dividual requirements described in this stan-start of preopersdonal testing. That time when dard, particularly in the area of nuclear power construction of the first safety related system is plant experience and for supervisory and complete fo: performance / integrated system management positions involved in the opera-testing (not component testing). tional aspects of the facility. In those cases where the collective qualifications do not =we==d startup testing. Commences following the the sum of the munmums for individual poei-receipt of the unit NRC operating license which tions, additional tachai-al support for%e plant allows fuel loedfug, inithi criticality, low power staff shall be provided. A periodic review of testing and the power ascension test program. staff qualifications should be performed as in-dicated in American National Standard Ad-
- 3. Functional-Levels and Assignment of ministrative Controls and Quality Assurance Reeponsibility for the Operational Phase of Nuclear Power Plants. ANSI /ANS 3.21982, subsection 4.5 [3]
3.1 General. The establishment of functional levels and assignment of responsibility require 3.2 Operating Org=nhation. The operating establishing various levels of qualified in- orgamzation of a nuclear power plant consists of dividuals that must be a part of the organization onsite personnel concerned with day t+ day licensed to operate nuclear power plants. The operation, maintanance, and certam technical functional levels used are not intended to define services and offsite personnel who provide 2
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Amancan Naional Standard ANSI /ANS-3.11981 operational support. The functional levels of the These individuals may puform work without onsite operating organization are broken down the direction and observation of qualified in- !
O as follows: Marmgers. Supervisors, Professional-Technical. Operators. Technicians, and dividuals if.they have previously demonstrated their ability to perform these speczfic tasks.
i Maintenance Personnel 3.2.1 Managers. Individuals at the functional Individuals in training or apprentice positions level of managw are those who are assigned who do not meet the qualification requirements 1 broad responsibilities for direction of major may perform work under the direction and '
aspects of a nuclear power plant. This functional observation of a qualified individual.
level generally includes the plant marager (plant superintendent, or other title), his line 3.3 Technical Support Personnel Technical
- assistants, if any, and the principal members of support personnel provide additional services the operating organization reporting directly to beyond those provided by the operating the plant manager who have overall responsibili- organization professional technical personnel.
ty for plant operation, maintenance personnel Additionally, they may also review and audit trammg or technical service activities. operations of the nuclear power plant. Such ser-3.2.2 Supervisors. Supervisors are persons vices may be performed by owner orgamzation .
principally responsible for directing the actions pesonnel or by individuals or orgamzations pro-of operators, technicians, or maintenance rr- viding consulting or contract services.
sonnel. Those positions usually designated as in-termediate an d first line supervisors are includ- 4. Qualifications ed in this category.
3.2.3 Professional Tecanical. Professional. 4.1 General Nuclear power plant personnel technical personnel are responsible for supervis- shall have a combination of education. traimng, ing and perfor:mng certain technical services in experience, health, and. skills commencurate support of plant operations. Examples are those with their funedonal level of respons:bility responsible for reactor engineering, instrumen- which provides rfasonable assurance that t'seir tation and control. radiation protection, train- decisions and actions durmg normal and abnor-O ing, chemistry and quality assurance. mal conditions will be such that the plant is operated in a safe and ef5cient manner. The medical requirements for licensed pesonnel are As discussed in 3.3, other technical services specified in American National Standard for beyond those provided by professional technical Medical Certification and Monitoring of Person-personnel who are a part of the station orgamza- nel Requiring Operator Licenses for Nuclear tion are provided by Technical Suppo4t Person- Power Plants, N5461976 (ANS 3.41. [4] Staff not personnel and applicants for licensing prior to 3.2.4 Operators Techniciano Maintenance initsal fuel loading at a new facility may not be Personnel. Operators, technicians, and able to meet nuclear power plant experience re-maintenance personnel are persons principally quirements. Special allowances for acceptance involved in the manipulation of plant controls. of personnel based on the additional training monitoring of instrumentation, radiation they will receive prior to fuel load may be per-surveys, plant chemistry, or the operations of mitted in these cases if the mimmum experience equipment: and pesons principally involved in at an operating nuclear power plant is satisfied.
the calibration. repair, maintenance, or perform-ance of other craft and technician activities in Individuals who do not possess the formal the plant. Examples are reactor operator, elec- educational requirements specified in this sec-trician, mechanic, electronics technician, or tion shall not be automatically eHminated where l laboratory technician. Individuals in traimng or other factors provide sufficient demonstration apprentice positions are not considered techni- of their abilities. These other factors shall be cians or maintenance personnel for purposes of evaluated on a case by case basis and approved defining qualifications in Section 4. Qualifica- and documented by the plant managw. The tions, but are permitted to perform work in the positive factors listed as follows may be con-job classification for which qualification has sidered in malnng the evaluation of an acceptsble been demonstrated. alternative to the educational requirements.
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., Amencan Naional S'arfard ANSI /ANS 3.11981
- a. High school diploma or "ED. to the position, whichever is later, the opera-
- b. Academic and related te:hnical training. tions manager shall have four years of power O c a tiit a assigned plant.
xac ier e, ter t es- >> < ce er wa<cs ts nuclear power plant experience. During the 7 -
- ti6-
- d. Four years of additional experience in his three years, the individual shall have par-area of responsibility. dcipated in the operadons or *A=M section
- e. Four years of supervisory or management acdvities of an operating nuclear power plant i experience. during the followmg periods.
- f. Demonstrated ability to communicate (1) Two month operation above 20 per-clearly (orally and in writing). cent power.
- g. Certification of academic ability and (2) Routine refueling outage (one to two knowledge by corporate management. months).
- h. Successful completion of the Engineer In- (3) Initial plant startup tesdag or poet Traimng ===mmation. refueling outage startup testing L Professional Engineer License. c. Training: Obtain and hold senior
- j. Assocante Degree in Engmeerms or related operator license (5.2) and as r.quisd by 5.3.1. ,
science. 5.4, and 5.5.
- d. The initial operations manager shall be 4.2 Managers assigned to the site six months prior to the start 4.2.1 Plant Manager of preoperational testing.
- a. Educadon: Bachelor Degree in Engineer. 4.2.3 Malatenance Manager ing or related science. a. Education: Bachelor Degreein FnM
- b. Experience: At the time of commence- lag or related science. Shall have non-ment of preoperational testing or appointment destructive tencing f=miHarity, craft knowledge, to the position, whichever is later, the plant and an understanMng of electrical pressure manager shall have six years of power plant ex- vessel, and piping codes and standards.
perience of which three years shall be nuclear b. Experience: At the time of commence-power plant experience. Dunng the three years, ment of preoperational testin2 or appointment O es i aivie= i a i> s rec *>at a i ts-management activities of an operating nuclear to es itic . -sica maintenance manager shall have four years of i i t - **-
power plant dunng the following periods. power plant experience of which two years shall (1) Two months operadon above 20 per- be nuclear power plant experience. Durmg the cent power. two years, the individual shall have participated (2) Routine refueling outage tone to two in the maintenance section activities of an months). operating nuclear power plant during the follow-(3) Inidal plant startup testing or poet ig periods.
refueling outage startup testing. (1) One month operation above 20 percent power.
The plant manager shall have a minimum of four (2) Routine refueling outage (one to two years of supervisory or management experience, months).
l
- c. Traimng: Hold an NRC senior operator c. Training: As required by 5.3.1 and 5.4.
license, or have held a IIcense for a similar unit d. The initial maintenance manager shall be j (LWR, LMFBR, HTGR), or have been cerufied assigned to the site six months prior to the start at the plant _ or at an appropriate simulator of preoperadonal testing.
(5.5.1.6) in accordance with 5.213. Also as re. 4.2.4 Technical Manager quired by 5.3.1 and 5.4. a. Education: Bachelor Degree in Engineer-
- d. The initial plant manager shall be assign- ing or related science.
ed to the site six months prior to the start of the b. Experience:. At the time of commence.
preoperadonal testing program. ment of preoperational testing or appointment 4.2.2 Operations Manager to the position, whichever is later, the technical
- a. Education: Bachelor Degree in Engineer. manager shall have four years experience in ing or related science. responsible positions related to power genera-
- b. Experience: At the time of commence. tion of which three years shall be nuclear power ment of preoperational testing or appointment plant experience. During the three years, the in-4 L
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American Nnfocal Standard ANSUANS 3.11961 dividual shall have participated in the technical 4.3 Supervisors or operations section activities of an operating 4.3.1 Supuvisors Requiring NRC License nuclear power plant during the following 4.3.1.1 Shift Supervisor. (Person in charge pe iods. of operations on shift at the station.)
(1) One month operation above 20 percent a. Education: High school diploma, plus power. the equivalence of 60 semester hours of college (2) Routine refueling outage (one to two level education. (900 classroom or instructor months). conducted hours) in mathematics, reactor 131 Initial plant startup testing or post physics, chemistry, materials, reactor ther-refueling outage startup testing. modynamics, fluid mechanics, heat transfer,
- c. Traming: Hold an NRC senice operator electrical and reactor control theory.
license. or have held a license for a similar unit (LWR, IJiFBR, HTGR), or have been certified at the plant or at an appropriate simulator If the shift supervisor does not meet these (5.5.1.6) in accordance with 5.2.1.3. Also as re- educational requirements, a shift technical ad-quired by 5.3.1 and 5.4. visor (4.4.8) shall be present durmg this super-
- d. The initial technical manager shall be visor's shift. .
assigned to the site six months prior to the com- b. Experience: At the time of initial core mencement of preoperational testing. loading or appointment to the position, 4.2.5 Training Manager. (Individual responsi- whichever is later, a shift supervisor shall have ble for the content of traimng programs de- four years of power plant experience of which scribed in Section 5. Trainmg.) two years shall be nuclur power plant ex-
- a. Educatior Bachelor Degree including paience. During the two years, the individual courses in education and technical subjects. shall have participated in reactor operator ac-
- b. Experience: At the time of the start of tivides at an operating nuclear power plant dur-the licensed program or appointment to the ing the following periods.
position, whichever is later, the training ,, (1) Six weeks opwation above 20 per-manager shall have four years of professional cent power.
level experience of which two years shall be (2) Startup from subcritical to 20 per.
O ==ct >ew at== < o >=<** --
years, the individual shall have part'cipated in cw-(3) Shutdown from above 20 percent the operations or traimng section activides of power to cold (less than 212*F) and subcritical an operating nuclear power plant during the (4) Startup preparations following a following paiods. refueling outage.
(1) Requali5 cation written and oral exam c. Trammg: Obtain and hold a senior period tone to two months). operator license (5.2) and as required by 5.2.1.8, (2) One month operadon above 20 percent 5.4. and 5.5. A portion of this traming is ap-power. plicable to fulfillirg educational requirements
- c. Training: As required by 5.3.1 and 5.4. shown in 4.3.1.1.a.
Shall have trammg in educational techniques if d. Certification. The competency of each not included in the Bachelor Degree course applicant to operate the plant safely and com-material potently shall be certi5ed by corporate manage-
- d. If the training manager does not possess ment prior to proposing the candidate for licone-a senior operator license, another individual who ing by the NRC. This certf5csdon shallinclude holds a senior operator license shall be responsi- consideration of successful compledon of train-ble to the traming manager for the content and ing, demonstrated abilities, satisfactory health, conduct of the traming program for licensed dependability, stability and trustworthiness. In operators. mairing this determmation, it is not sufficient to review only the training record of the applicant.
In addition, the responsible manager shall The training manager shall be assigned on a review or cause to be reviewed less subjective schedule consistent with requirements for train- documents such as supervisory evaluations, ing of pesonneL This individual may be located results of medical eraminations and tests, onsite or offsite. security checks. and sick leave records for pac.
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Amencan N:tional Standard ANSI /ANS 3.11981 terns indicative of ill health, drug addiction or 4.3.2 Supervisore not Requiring NRC Os- alcoholism. Licanoes 4.3.1.2 Senior Operator. (Person in charge of a. Education: High school diploma.
reactor operators on shift-first line supervisor.) b. Experience: At the time of initial core
- a. Education: High school diploma, plus loading or appointment to the position, which-the equivslence of 30 semester hours of college ever is later, a supervisor in this category shall .
level education. (450 classroom or instructor have four years of experience in the craft or conducted hours) in mathematics, reactor discipline he supervises, of which one year shall physics. chemistry, matertals, reactor ther- be nuclear power plant experience.
modynamics, fluid mechanics, heat transfer, c. Traming: As avirmi by 5.3.1, 5.2.1.8.
electrical and reactor control theory. 5.4, and specific tachnial training related to
- b. Experience: At the time ofinitial core their area of supervision.
loading or appointment to the position, d. If the supervisory activities could affect whichever is later, a senior reactor operator the quality of structures systems, and com-shall have three years of power plant experience ponents important to safety, the supervisor of which two years shall be nuclear power plant shall have performed these activides under experience. During the two years, the individual supervision for a nummum of three months at shall have participated in reactor operator ac- the site or shall have demonstrated knowledge tivities at an operating nuclear power plant dur- of the safety nianm~~a of these activities as ing six weeks operation above 20 percent power. well as systems interactions.
For upgrade from a licensed operator to a senior operator at an operating nuclear power plant, 4.4 Profeselonal Technical. The onsite the individual shall normally have one year ex- professional technical group leaders shall perience as a Han==d operator and in no case possess the following qnallffemtions in the in-less than six months. .
dicated disciplines. A smgle individual may be qualified and perform in more than one discipline.
O' In some instances it is desirable to have a col- 4.4.1 Reactor Engineering lege graduate obtain an SRO license even a. Education: Bachelor Degree in Engmeer-though he will not become a part of the shift ing or related =a====.
orgamzation. The need for on-shift experience b. Experience: At the time of initial core should then be evaluated on a case by case basis. loading or appomtment to the position, which-
- c. Traming: Obtain and hold a senior ever is later, the responsible person shall have operator license (5.2) and as required by 5.4 and four years professionallevel experience of which 5.5. A portion of this traimng is applicable to two years shall be nuclear power plant ex-fulfilling educational requirements shown in perience. The experience shall be in such areas 4.3.1.2.a. as reactor physics, core measurements, core
- d. Certification: The competency of each heat transfer, and core physics testing pro.
applicant to operate the plant safely and com. grams. During the two years, the indivir al potently shall be certified by corporate manage. shall participate in the reactor engineering scc-ment prior to proposing the candidate for lic4ns. tion activitfee at an operating nuclear power ing by the NRC. This certification shallinclude plant during the following periods.
consideration of successful completion of tram- (1) Initial fueling or refueling outage fuel ing, demonstrated abilities, satisfactory health, hanEng period.
dependability, stability and trustwortM-=._In (2) Initial startup test program or poet making this determination,it is not sufficient to' refueling outage startup test program.
review only the training record of the applicant. (3) Power increase from 10 percent to 100 In addition, the responsible manager shall percent power including stabilization of zenon.
review or cause to be reviewed less subjective (4) Rod sequence exchange (BWR only).
documents such as supervisory evaluations. (5) Two weeks operation above 20 percent roeults of medical examinations and tests. power.
security checks and sick leave records for pat-terns indicative of ill health, drug addiction or O alcoholism, Successful completion of a reactor engineering traming program (such as a reactor engineering 6
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American Nacional Standard ANSUANS.3.11981 certification program offered by NSSS Vendorsi year shall be nuclear power plant experience in may be considered equivalent to one year's radiochemistry. During the one year, the in-nuclear power plant experience. Six months ex- dividual shall participate in the chemistry sec-
, perience shall be onsite. tion at an operating nuclear power plant for
- c. Training: As required by 5.3.2 and 5.4. three months. No less than two months shall be
, d. The individual who temporarily replaces with the plant operating above 20 percent the reactor engineer shall have a Bachelor poww. Successful completion of a chemistry and
. Degree in Engineering or related science and radiochemistry training program (such as a two years professional level experience, of which chemistry and radiochemistry certification pro.
! one year shall be nuclear poww plant ex- . gram offered by NSSS Vendors) may be l perience. Six months expwience shall be onsite. equivalent to six months nuclear power plant
- 4.4.2 Instrumentation and Control experience. Six months experience shall be on-
- s. Education: Associate Degree in site.
Engineering or related science. c. Traming: As required by 5.3.2 and 5.4.
- b. Experience: At the time of initial core d. The individual who temporarily replaces i loading or appointment to the position, which- the chemistry and radiochemistry group leader
' ever is later, the responsible person shall have shall have a Bachelor Degree in Chemistry or .
two years power plant experience in instrumen- related science and one year experience in .
tation and control, of which one year shall be chemistry, of which six months shall be nuclear
- nuclear pown plant experience. Durmg the one power plant experience in radiochemistry. Six year, the individual shall participate in the in- months experience shall be onsite.
strument and control section activities at an 4.4.4 Radiados Protecdon
, operating nuclear power plant during the follow- a. Education: Bachelor Degree in a science Ing periods. or engmewing subject, including formal train-
- ill Surveillance testing and calibradon of ing in radiation protection.
i instruments and controls during initial fueling b. Experience: At the time of initial core l or refueling. - loading or appointment to the active position.
(2) Startup preparation testing at the end whichever is later, the responsible ladividual
! of initial fueling or refueling. shall have four years of asperience in applied l (3) Initial fueling or post refueling outage . radiation protecdon. At least three years of this startup testing. experience shall be in applied radiation protec-
- 14) One month operation above 20 percent- tion work in a nuclear facility dealing with power. radiological problems simdar to those en-countered in nuclear power plants, preferably in
! Six months expwience shall be onsite. a nuclear power plant. During the three years.
the individual shall participate in the radiation If the person filling this position has a protection section of an operating nuclear power
- Bachelor's Degree in Engineering or related plant during the following periods.
i science, the experience requirement will be (1) Routine refueling outage (one to two i fulmind by six months experience onsite and monthal.
- completion of items bil),12). (3), and 141. (2) Two months operation above 20 per-
- c. Trainmg: As required by 5.3.2 and 5.4. cent poww.
i d. The individual who temporarily replaces 4
the instrumentadon and control group leader Six months experience shall be onsite.
shall have the educational requirements of c. Training: As required by 5.3.2 and 5.4.
- 4.4.2.a and one year expwience in this field. Six d. The individual who temporarily replaces months expwience shall be onsite. the radiation protection group leader shall have 4.4.3 Chemistry and Radiochemistry a Bachelor Degree in a science or enginewtng
- a. Education: Bachelor Degree in subject and two years experience, one of which
- Chemistry or related science. shall be nuclear poww plant experience. Six
.! b. Experience: At Ll:c time of initial core months expwience shall be onsite.
loading or appointment to the position. which- 4.4.5 Quality Assurance ever is later, the responsible person shall have a. Education: Bachelor Degree in Engineer-two years experience in chonistry, of which one ing or related science.
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American Nuional Standard AN:,UANS 3.11981
- b. Experience: At the time of initial core O loading or appointmeat to the position.
Preoperational and startup test procedures and test results for systems, structures and com-whichever is later, the responsible persca shall ponents important to safety shall be reviewed have four years experience in the field of quality and approved by individuals having the follow-assurance. or equivalent number of years of ing mintn um qualifications. One individual may nuclear plant experience in a supervisory posi- fulfill more than one of the categories listed in tion, preferably at an operating nuclear plant or the following paragraphs.
a combination of the two. At least one year of (1) An individual who meets the re-this four years experience shall be nuclear power quirements of the Operations Manager (4.2.2) or plant experience in the implementation of the Technical Manager (4.2.4). This individual sha" quality assurance prcgram. also be knowledgeable of the test program ad-
- c. Training: As required by 5.3.2 and 5.4. muustration.
44.6 Pr, operational - Startup testing: At (2) An individual who meets the re-the time the activity is bemg performed. in- quirementa of the group leader of the related dividuals responsible for preoperational and professional tWie=3 group as provided in 4.4 startup testing activities for safety related or who has a Bachelor Degree in T'=i- ing or systems shall p=== the following qumIffies- related sciences and three years of power plant tions: experience including two years of nuclear power (16.1 Prweional Testing. These per. plant experience.
sonnel are responsible for developing a preopern- C) An individual from the responsible tional test procedure, briefing personnel respon- engineering (design) organization who is sible for operation of the plant during the test, knowledgeable of system and equipment design ensurmg the test is performed in accordance and performance requirements. For startup test, with the procedure and generating the preopera- this individual shall also be knowledgeable of tional test report. plant operating and transient response
- a. Education: Bachelor Degree in characteristics. This requirement may be ful.
Engmeering or related science.
O .
- b. Experience: One year of power plant experience.
filled by assigning another individual with this knowledge to the team, '
(4) The individual responsible for
- c. Training: As required by 5.3.2 and 5.4. developing the preoperacional or startup test
- d. Individual shall be knowledgeable of procedure and report as indicated in paragraph the test program ariminiatration and the des'gn. 4.4.6.1 and 4.L6.2.
and operational performanes requirements of- 447 Training. The individual responsible the system and equipment being tested and its for the content of training programs Indicatedin interaction with other plant systems. Section 5. Training, is described in 4.2.5.
(4.6.2 Startup Testing. These personnel (L7.1 Training Coordinator. (Reeponsible are responsible for developing a startup test pro- for coordinating the onsite training program.)
cedure, briefing personnel responsible for opera- s. Education: High School Diploma.
tion of the plant during the test, ensuring b b. Experience: Theindividualresponsible test is performed in accordance with the pro- for coordinating the onsite training progrsm cedure and generating h startup test report. shall have two years power plant experience of
- a. Education: Bachelor Degree in which six months should be in the onsite train-Engineering or the related sciences. Ing organization.
- b. Experience: Two years of power plant c. Traimag: As required by 5.3.2 and 5.4.
experience of which one year shall be nacisar d. The person responsible for the coor-power plant expertence. dination of the training program and the person j
- c. Training: As required by 5.3.2 and 5.4. roeponsible for content of training may be the
- d. Individual shall be knowledgeable of same, in which case that person shall meet the the test program arlministration, the system higher qualification and be located onsite, design and operational requirements and ex- 447.2 Training Inst: actor pected plant operational c'iaractertstics during a. Education: High school diploma and the test. speczal education consistent with the materials LL6.3 Review and Approval of Proopere- being presented.
O tional and Startup Test Procedures and Resulte. b. Experience: Instructors shall have ex.
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American Niuonal Standard ANSI /ANS 3.11961 perience consistent with the materials being ble for operation of systems and components as presented. directed by a licensed senior operator cr O c. Trainin.: rersons whe instruct s,ecific license subjects such as technical specifications, e,eracer.>
- n. Education: High school diploma.
operating practice (5.2.1.3) and control b. Experience: Non licensed operators manipulations (5.5.1.2.1) shall have received whose actions could affect the quality of struc-Senior Operator tratmng (5.2) and appropriate cures, systems, and components important to general employee training (5.4) and retraimng safety shall have one year of power plant ex-4 (5.5). Non licensed instructors may be used as perience.
I inscructors in other areas where they possess c. Training: As required by 5.3.5 and 5.4.
specific expertise. d. Non licensed operators shall be
! qualified to perform various tasks at the nuclear power plant by demonstrating perfcrmance Instructors who provide instruction on the capability for the tasks assigned and operating simulator shall hold, or have held, a senior knowledge of systems involved and their rela-operator license for a similar unit (PWR, BWR, tionship to plant safety.
LMFBR, HTGR) or have been certified at an ap. 4.5.1.2 Ucensed Operatore.(Responsible for i propiace plant simulator (5.2.1.3). control room operations of structurse, systems,
- d. The . Instruecor shall have and components important to safety.)
demonstrated knowledge of instructional a. Education: High school diploma.
techniques and be certified by the Trauung b. Experience: At the time of core loading Manager as a qualified instructor for the or appointment to the position, whichever is
- material being presented. later, NRC IIconsed operators shall have three 4.4.8 Shitt Technical Advisor. Responsible for years of power plant experience. One year of this plant accident asseesment function during tran- experience shall be spent, preferably performing
- sients. May also be assigned operations assess- nonlicensed operator duties at the nuclear ment function during normal operations. This is power plant for which he holds an NRC license.
- an interun position and may be discontinued As a mimmum, six months of plant operational i
O wae ts saif= sneervis r i =>
the requirements of 4.3.1.1.
d d t - t duties as a non ticensed e,erator is reautred.
- c. Traimng: Obtain and hold operator
- a. Education: High school diploma and 60 license (5.2.1.1 through 5.2.1.5), 5.4 and 5.5.
semester hours of college level education. (900 d. CertiScation: The competency of each l
classroom or instructor conducted hourst in applicant to operate the plant safely and com-I mathematics, reactor physics, chemistry, potently shall be certified by corporate manage-materials, reactor thermodynamics, fluid ment prior to proposing the candidate for licens-
-wes, heat transfer, electrical and reactor ing by the NRC. This certification shallinclude control theory. consideration of successful completion of train-
- b. Experience: One year of nuclear power ing, dunonstrated abilities, satisfactory health, plant experience. Six months experience shall be dependability, stability and trustworthinese. In onsite. making this determmadon, it is not sufficient to
- c. Training: As required by 5.3.3 and 5.4. review only the training record of the applicant.
- d. Individual shall be knowledgeable of con- In addition, the responsible manager shall trol room instruments and controls and be review or cause to be reviewed lose subjective assigned to advise the responsible shift super- documents such as supervisory evaluadons, visor concerning abnormal plant operating con- resulta of medical ===mM=tiens and tests, didons. security checks, and sick leave records for pat-terns indicative of ill health, drug addiction or alcoholism. .
4.5 Operator Technician Maintenance Person- 4.5.2 Technielma. (Responsible for the per.
nel The qualifications of personnel described in formance of tests, calibrations, inspections, the following paragraphs are for operators and surveys, and repairs of instruments, controls, journeymen level personnet and equipment.)
4.5.1 Operatore a. Education: High school diploma.
4.5.1.1 Nos.ucensed Operatore. (Responsi- b. Experience: Three years of working ex-9 L
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Amencan Ntti nal Standard ANSI /A.%3.11981 perience in their specialty. mittee members respectively. In those cases
- c. Traming- As required by 5.3.4 and 5.4.
O d. Shall have demonstrated their ability to where independent review'is performed by an orgamzational unit, the qualineations given in perform assigned tasks and their knowledge of 4.7.1 and 4.7.2 shall apply to the supervtsor of the significance of these tasks on plant opera- the orgamzational unit and to the staff tion.
=p- i h st performmg independent reviews 45.3 Malatenance Personnel (Responsible respectively. An organizational unit responsible I for the maintenance and repairs of equipment.) for independent review of operational phase ac-
- a. Education: Jcurneyman level tivities may also provide some or all of the re-
- b. Experience: Maintenance personnel shall l quusd eachnie=1 support service. Members of j have three years work experience in one or more the orgamzational unit shall not review at.-
crafts. !
tivities for which they have direct responai- l
- c. Traming: As required by 5.3.4. and 5.4. bility.
- d. Shall have demonstrated their ability to 47.1 Supervisor of Organisational Unit or perform assigned tasks and their knowledge of Chairman of Standing Comunittee Responsible the significance of these tasks on plant opera- for Independent Review tion. ,
- a. Education: Bachelor Degree in Engmese-ing or related science.
4.6 Engineering and Technical Support Person- d prdessional neL As described in 3.3, engmeering and eveb. Wence managen Sixs@the expen ein poww M technical support personnel provide additional c. As W by 5.3.1.
services beyond those provided by the operating d. In addition, the individual shall have the orgamzation professional technical personnet _ ,,,,7 g , gg Additionally, they may also review operations mbe wk u d condtanu and cem of the nudear power plant. for dealing with complex problems beyond the 46.1 Enginser in Charge .
- pe d owner o@ta.on W
- a. Education: Bachelor Degree m, Engineer- 47.2 Staff Speciallete or Standing Commit-
- " I *# #'I* N'"#*** w hk In h m h stdf
- b. Experience Six years of professional specialists provide the independent review of level expertence m nudear serv 2ees, nuclear dond % acdWda d a w m plant operation, or nuclear engmeering, and the nh pown plants, th individuds #m necessary overall nudear background to deter- g,g ,,yg, ,,g,g3 , ,,,,,of ,gm,,;,,,,ggy, ,,,,
mine when to call consultants and contractors trd nudear m plant pdons. W, for dealing with complex problems beyond the nudw enghring, metdlum qudity scope of owner orgamzation expertise. assurance, non-destructive testing, chemistry
- c. Trainintr: As required by 5.3.1, and if on- and radi~+==iaty, instrumentation and con-site, as required by 5.4. mis, mdidgicd sdety, and Ma'dcal and j d. This is normally an offsite position that doctned wW shd! have does not report to the plant manneer. a. Education: Bachalor Degree in Engineer- '
i ggg ,
- b. Experience Five years of professional 4.7 Independent Review Personnel Independ- level experience in the field of his specudty.
ont review as stated in subeection 4.3 of c. Training:,As required by 5.3.1.
( American National Standard Admmistrative ,d._An individual performing reviews may Controls and Quality Assurance for.the Opera- poseees competence in.more than one specialty tional Phase of Nuclear Power Plants, area. Requisite experience for reviewers may ANSI!ANS 3.21982, may be performed by have been gained concurrently in related special-either a standing committee or by a separate ty areas.
established organizational unit independent of the onsite operating organantion. [3] In those cases where independent review is provided by a 5. Training standing committee the qualifications given in 4.7.1 and 4.7.2 apply to the chairman of the 5.1 General Aspects. A traming program and standing committee and to the standing com- schedule shall'be established for each nuclear O 10
Amancan Nrtional Standard ANSIIANS 3.11981 power plant to initially develop and maintain an These exceptions will be noted and documented.
organization fully qualiEed to be responsible for Such trammg programs shall cover the subject operation, maintenance, technical upects, and matter listed in the following subsections to the O 9e te - ci Ts 85 tivertri-ing programs shall be to provide qualifed per-t = = c ve ta t atvia i - t the applicable requirements of Section 4. -
' sonnel to operate and maintain the facility in QuahEcations. -
compliance with its license, tachaie=1 specifica- 5.2.1 Training Program to Establish Eligibill-tions and appropriate governmental regula- ty for NRC F=-i== tion for Operator and tions. Training programs shall be reviewed by Senior Operator License. Candidates for 1 management and kept up to date to reDect operator and senior operator licenses shall have !
changes to the facility, procedures, governmen- had operating experience and trauung in the tal regulations, and quality assurance re- plant for which the erammations are to be re-quarements as well as industry operating ex- quested. Experience and prior trauung may be parience, LERs. and personnel errors as ap- gamed through the program described in the plicable for their area of responsibility. The pro- followieg paragraphs.8 gram shall be formulated to provide the required trauung based on individual employee ex- Erammations covering material presented in ,
perience, the intended position. and a job task each completed segment are required. Attend-analysis for positions indicated in 4.2 through ance at each written er=mination shall be 4.5. The training program shall be such that ful- documented and retained as set forth in 5.6. Ex-ly trained and quali5ed operating, maintananc=, anunation records shall include each ev=mina-profescional, and tachnical support personnel tion, eramination grade keys, and exammation are available in the necessary numbers when grades.
fuel loading commences. A continuing program shall be used after plant startup for traimng of The oral awarnination shall be documented.
replacement personnel and for roquali5 cation Areas of ===mmation questions and the overall
, traimng necessary
- such that personnel remain grade of satisfactory / unsatisfactory assigned to l proficient. An appropriate evaluation shall be each examination shall be included in this
! made for each training program which may in- documentation.
O ci ae -ritt erai er ee-tion. The concept of trauung personnel as a team tr tie -in - 211
- ie rrow rri tr d -
A fundamentals course shall cover the theory of t.ie.
should be used where practicable. the nuclear fission process and reactor opera-tion.
Section 5 specifies the traming programs iden-tiBed in Secdon 4, Qualifications. The course shall contain instruction in:
(1) Principles of reactor operation.
Quali5ed individuals who successfully pass the (a) Atomic structure and radioacdvity.
NRC aw=mmation are issued operator and senior (b) Nuclear reaction and the fission pro-operator licenses. E==minations conducted ceae.
prior to initial core loading of the subject reactor (c) Neutron behavior and control of 6 are termed " Cold" avaminations. Ezannnations fission process.
admimatered subsequent to the initial criticality Id) Core and Nuclear Steam Supply of the reactor are termed " Hot" ===minations. (NSS) characteristics thermal hydraulic design.
The licensee issued based on the results of either 12) Design features of the nuclear power hot or cold avaminations are equivalent, and are plant.
issued for two year periods. (3) General operating characteristics of the nuclear power plant.
5.2 Trainlag of Personnel to be Licensed by b (4) Reactor instrumentation and control NRC. The training programs outlined in this systems.
section are for individuals with no previous (5) Radiation control and safety provi-training and experience. Traimag coursee and sions .
durations indicated in the following paragraphs may vary based on the person's experience and prior training as compared to the task analysie. 8 A typical schedule is contained in Appendiz A.
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Ammcan Naional Standard ANSI /ANS 3.11981 (6) Fundamentals of heat transfer, undergo an examination for a license, and at a thermodynamics and fluid flow related to tran- simulator if one is available.
O sient analysis.
The course shall contain instruction in Instruction durmg this period shall include:
mathematics, electricity, mechanics and other (1) Standard and emergency operating procedures.
subjects of a theoretical or engmeenng nature in support of the proceding listing. Portions of this (2) Plant trusients.
program may be applied to fnifilling the educa-(3) Accident identification and analysis including trending.
tional mtuirements listed in Sectin 4. (4) Controlling the plant from a central Each cold license candidate shall participate in a coner I room during normal, abnormal and supervised program at a research or power reac- emergency situauona.
tor dunng which the individual shall perform (5) Operating philosophy, use of pro-ten reactor startups. This trainmg shall also in- uns, sm M reuef turnover, d v&-
'Tude instructions, application and " hands on" don o tatus experience relating to subjects (1), (4). and (5) in _ ,
5.2.1.1. Completion of this traming must be Perime. CanMates sM owe the operadng -
documented by certification by the reactor practices and the operscon of a nuclear power plant from a central control room. Hoc license faduty12 5.2 Plant Systems. Systems instruction can& dates shau manipulate the untrola under for a licensed candidate shallinclude both obser- the direct supervision of a h,eensed operator at vation and classroom work. This instruction the individual's duty station for a varietyi shan be plant s@. plant operations. Cold licanaa candidates shall I 5.2.1.2.1 P - : x Instruedon. Instruc- @te b the pht pmoperadonal teedng tion covering nuclear power plant systems shall program. A check off list of minimum opera-include the fouowin tions to perform or observe shall be establish &
Plant instrumenta ion and control systems 5M.3.2 Simaw Training. Can& dates Safety, fire and emergency systems shall praedce manipulating the controls of a O Pnmary and secondary mechanical systems Electrical systems plant as represented by an applicable simulator as described in 5.5.1.6. (Also see Amerscan Na-P!st a ed support systems ti nel Standard Nuclear Power Plant Plant protection systems S on for me b Operaw %
Fuel hanAHM sysums ANSI /ANS 3.51981. [51) As a minimum, the Waste processing systems conse canddate sM partMpete b training Integrated plant operation, system interac- sessions that include all of the applicable plant tions and casualty response. manipuladons identified in 5.5.1.2.1. Pardeipe-tion shall be in groups of no more than four This instruction shall also include system and people manipulating the controls or directing component malfunctions and be documented by the activities of individuals dunng plant exer-a written aramination. cises.
5.2.1.2.2 Plant Observation. Planned systematic observation trauung of license can. Eraminations using the simulator shall be pro- .
didates shall be perfonned on acces-ible piang vided, and shall. include an aramination while equipment. Emphasis shall be on understanding operating at power with plant malfun:tions, and system operation. !ocal plant control. system in_ wh.!e starting up the reactor. The certification teractions and indication. '"'"atin shall demonstrate the candidate's ability to:
Student / instructor ratio shall be no greater than (1) manipulate the controls in a safe
. six to one. Documentation of this training shall and competent manner, i
be maintained by system study check oft. and (2) predict instrument response and use an oral examination. the instrumentation available, 5.2.1.3 Operating Practice. Training in (3) follow the facility procedures, and operating practices shall take place both in the (4) understand alarms and annun-control room for which the candidate will cistors and take proper action, and 12
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.,_ ..__.-_ - ._-___._ _ ,._ ..-_ ,,___, - _ _ __., ,__. _._-. - __ .__, ~ __- __ _ ..____ , _
Annoncan National Standard ANSUANS 3.11981 (5) communicate promptly and effec- Instruction in these subjects may be conducted tively. throughout the training program.
5.2.1.4 Practical Work Assignments for O Cold Ucense Candidates. Traming in the form of practical work assignments for the site shall Poru.ons of this program may be applied to n
[the educaumal mquinments Usted in be provided. Work assignments may include:
plant operating procedure preparation and 511d Teodng la Uen of Training. Exten-
,;y, ,, , f,gy vwification, preoperaconal testing of plant systems, participauon in hot funcuonal tesung g;,3 ;, ,gy ,;,g , g program. providing instruction on plant complexity and operating charactenstics to the systems to the remainder of the group. Em- nuclear power plant at which arammations are phasts shall be on the beense candidate gnimng to be requesW w subsdtute fw se of 6 thorough knowledge of his own plant. Some of training described in the proceding listing. Ex-this training shall be done in the central control aminations venfying the present knowledge of room of the plant involved. A check-off list of the individualis comparable to the knowledge of an individual completing the traimng segment
{"*511.5 Pre Ucense 3'r==laation. A com-h p radons to perfonn a obsene shah shall be required prior to excusmg this in-un m t a traimag. n au casu. the prehensive examination to determine the indi- owner w con sM man ht det vidual's ability to operate the plant in a safe and plant 8pecific instruction is provided, competent manner shall be administered by the 1.8 rain ng of Ucensed SaW.
ownw orgammation. This ====M= tion is re- Individuals selected for supwvtsory posidons quired prior to certification of competency of "9"*"".g C Sedw Openta Heenm M this indiviriual to the NRC. A brief simuistor " * * * * " * * * * " ** "*I " "I training program emphamirmg overall plant
- operadon shall be included for cold license can- 11) Leadeship
, ,3 g ,
, didates. Oral and wntten araminations are en-couraged. An intensive period of instruction 13) Command nsponsibilities and limits prior to the NRC license examination should be g 4) y,ggy,gg,, ,, p,,,,,,,3 provided. Operating features of the facility (5) Problem analysis i and expwience at mmdar plants shall be (6) Decisional analysis (7) Admini=tradve requirements for the 511.6 Senior Reactor Opwater Instnc- su Mry position.
tion. Senior reactor opwator license candidates shall have additional instruedon in subjects 5.3 Training of Pereoanel not Requiring NRC relating to their dudes. Instruction shall in-D- -A shad W d ahad Im mu88ws. Mpwvisms, profmWs, operators, technicians, and maintenance person-i Han and disposalof. and hasards na t mat t e ents es s ed h the l u.ociated with, maioaceve matenals. facility heensee as well as the requirements of (3) Specific operating characteristics of Secda 4. QuaHScadona, of @ stanM the nuclear power plant. Eraminations covering material pnsented in (4) Fuel handling and core parameters. each completed segment are required. Atten-(5) Administrative proceduns, condi- dance at each wrftten araminadon shall be tions, and Ilmitadons. documented and retained as set forth in 5.6.
(6) Chemistry and radiochemistry. 5.3.1 Training for Manaswo and Supervisors.
(7) Operating philosophy, use of pro. SIMaffnd training for each individual in this cedune, shift and relief turnovn, and verifica- category shall be based upon an analysis of the tion of system sestus. Individual's background, abilities and roeponsi-r (8) Fundamentals of heat transfer, ther- bilities and the effect his area of responsibility modynamics, fluid Dow and dynamics as related could have on overall plant safety. Training to transient analysis. shall be provided to compensate for deficiencies (9) Responsibilities during emugency identified by comparing the individual's ex-conditions. perience and knewledge to the task analysis.
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American Nuional Standard ANS!/ANS 3.11981 The programs may include assignment of the in- performanca capability. The special traimng
(')
O' dividuals to operating reactors or simulators or both, involvement in plant design and partici-above the journeyman level of technician and maintenance personnel shall be based on a task pation in the programs listed in 5.2.1.8. Con- analysis of the individuals's assigned functions.
struction and startup activities may be utilized 5.3.5 Training for Non Ucessed Operatoes.
as necessary to complete the training. Individuals permitted to ope. ate systems or 5.3.2 Training for Professional Technie=1 Per- equipment independently that could affect the soonel. Traimng shall be provided to compen- quality of structures, systems, and components sate for deficiencias identified by comparms the important to safety shall receive instruction for individual's experience and knowledge to the tasks to be performed. These instruedons shall task analysis. The required trammg of these include as a rninimum:
professional technical personnel can be imple. (1) Generic equipment or component design mented. by involvement in related training pro- and applications.
grams. These traming programs may include (2) Speci5c equipment and system opera-l assignment at operating reactors or simulators, tion and operational requirements.
or both, and at vendor facilities. The training (3) Specific equipment and system shall be for periods of time sufficient to develop operating procedures, the proficiency required for safe and competent (4) Specific equipment and system function supervision and performance. during a transient (if applicable). '
5.3.3 Training for Shift Technical Advisor (5) Relationship of specific equipment and with Bachelor Degree Without an NRC Senior system to plant safety and technical specifica-Operator Ucense. A trammg orogram for this don limiting conditions for operation and individual shall be provided c: nelude: surveillance requirements (if applicable).
(1) Lectures which cover the accidents (6) Responsibilities during transients.
analyzed in the Final Safety Analysis Report malfunctions and emergency procedure IFSAR) and the consequences of these ac- response.
cidents. (7) Identification and reporting of equip-
' O, (2) Lectures on plant specific thermo-dynamics / fluid flow, reactor physics system ment or system deficiencies.
- (8) Specific tasks involved in operation of engineering transient and accident analysis, system or equipment. ,
nuclear instrumentation. process computer.
plant response, and the duties and respom Th bdividual's understanding of the informa-sibilities of the Shift Technical Advisor, tion provided by this program shall be -
(3) Performance of control manipuladons evahtated by written araminations. The ability on an applicable simulator (5.5.1.6) to include to m the tasks -ary to ws the asterisk (*) items listed in 5.5.1.2.1. equipment and systems shall be demonstrated (4) The individual s understanding of the la walk through may be subetituted if equip-information provided by the program shall be ment cannot be removed from service). This evaluated by written ==='aiaa tions for (1) and (2) traimng shall include on-the job training under
" ~
the guidance of a qualified individual A super-5 Tra T Main- vis r r qualified operator shall certify satisfac-tenance Personnel. T=chairi=== and main- tory performance capability.
! tenance personnel shall be trained by on.thejob 5.4 General Employee Training. All persons
! training: by participation in initial calibration, regularly employed in the nuclear power plant l testing, and equiptnent acceptance programs: or shall be trained in the following' areas commen-by related technical training to meet the surate with their job duties:
qualifications set forth in 4.5. General Description of Plant and Facilitfee Ab Related Procedures and Instructions A training program shall be provided for job Radiological Health and Safety Program functions that could affect the quality of strue. Station Emergency Plans tures, systems and components important to Industrial Safety Program safety. The program shall include applicable Fire Protection Program l administrative controls, special complex system Security Program and component instruction. and demonstrated Quality Assurance Program.
t 14 i
,, Amancan N;tional Standard ANSI /ANS 3.11961 Temporary maintenance and. service personnel basis. Retraining programs may be conducted shall be trained also in the areas listed in the by persons othe than the facility licensee pro-proceding paragraph to the extent necessary to vided such programs meet the requirements and O- assure safe execution of their duties. evaluation criteria described in 5.5.1.1 through The individual,s understanding of 6 informa* 5.5.1.6 for the facility involved. A simulator tion provided by this program shall be shan W used to fuHiH portions of h reW evaluated by ariminierering an eramination of program for those evolutions whwe the
- sufficient difficulty covenng the previously simulator is capable of simulating continuously listed areas to ensure the individual has suffi" and in real time plant operadons of the refer-
- enced facility (5.5.1.8).
cient knowledge to work independently at the i
facility. Individuals who do not pass this ex- 5.5.1.1 I4etures ammation shall not be permitted u, uade the pro- 5.5.1.1.1 General. The minimum number tected ama without a fun time acwt. of preplanned !wturn in ny caladar yur shan not be less than six, appropriately scheduled i 5.5 htraining. A retraining program shall W throughout the year and taking into considers-established which maintains the proficiency of tion heavy vacadon periods and infrequent the operating organization. Machanisma shall opwadons such as refueling periods and forced
- be established to ensure that individuals in & outages. Lectures may be deferred due to unan-operating organization performing safety ticipated shutdowns. However, these lectures
' related funcdons remain cosmzant of changes shall be conducted as soon as practicable to the facility, procedures governmental regula, thematter, dons, and quality assurance requimments as i
well as industry opwating upwience, Licensa Content of the lectures shall take into considera-
! Event hports (LERal, and personnel errors as don the categories as listed in 10 CFR Part 55,
' applicable for their area of responsibility. In Appendix A. heat transfer, thermodynamics.
determining the staff complement, the facility operating experiences from similar plants and management shall recognize 6 important rela- the msults of the annual aramination. (2l l tionship the trauung program has to the 5.5.1.1.2 Attendance. All licensed in.
O maintenance of operational safety by (a) pro-viding experienced and knowledgeable person.
dividuals shan attend every preplanned lecture, uc*pt the mqualification program may contain i
nel to develop and audit the training program as a grade criterion for allowable uompdon froca well as serve as training program instructors; attenslanca at a given lecture except for lectures and (b) provide sufficient personnel in classifica, on 5.5.1.3.1.J. The minimum grade acceptable l dons to permit training and requalificadon for allowing uomption from a particular lecture i work. Is 80 percent in that category of the annual ex.
aminadon per 5.5.1.3.1 The training program shall be evaluated by per- 5.5.1.1.3 Training Alde. Training aids sons other than those directly responsible for such as video tapes and films may be used.
the training. Le., standing committee member or However, an instructor shall participeto in at staff specialists. This evaluadon shall be for least 50 percent of the lecture series.
content, quality and appropriatenese such as 5J.1.2 On the Job Trainias saam difficulty, grading quality and Iseture sub- 5.5.1.2.1 Centre! Manipaleties. The jocts. The training program shall be evaluated following control manipulations and plant on an annual basis. Pwsonnel camporarily evolutions where applicable to the plant design removed from or prevented from performing are acceptable for meeting the reactivity control operating activities for periods greater than six manipuladons required. The starred items shall months shall be roqualified for their specific job be performed annually; all other items shall be duties. A special program may be used based on performed on a two. year cycle. Multiple failure appropriate sections of 5.5 and evaluadons casualties shall be included in the program.
made band on 5.5.1.3. However, the roqualification programa shall 5.5.1 htraining of Perosanel Lleemed by & contain a commitment that each individual shall NRC. Annual ntralmng programs shallinclude perform or participate in a combinadon of reac.
pre planned lectures, on.thejob tralmng and civity control manipulations which may be per.
operator evaluadon on a ngular and continuing formed as part of normal plant evoludons.
15
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Am mo Nruonal Standard ANSUANS-3.11981 Those control manipulations which are not per- (18) Mispositioned control rod or rods formed at the plant shall be performed on a O simulator. The use of the Technical Specifica-tions should be ==W=i'ad during the simulator (or rod drope).
(19) Inability to drive control rods, (20) Conditions requiring use of control manipulations. Personnel with senior emerger.cy boration or standby liquid control licenses are credited with these activides if they system.
dirtet or evaluate control manipulations as they (21) Fuel cladding failure or high no-are performed. tivity in reactor coolant or offgas.
PWRIBWRIHTGR" (22) Turbine or generator trip.
- (1) Plant or reactor startups to in- (23) Malfunction of automade control clude a range that reactivity feedback from system (s) which affect reactivi:.7 nuclear heat addition is nociceable and heatup (24) Malfunction of reactor coolant rate is established. pressurevolume control system.
- (2) Plant shutdown. (25) Reactor trip.
- (3) Manual control of steam genera- (26) Main steam line break (inside or tors or feedwater, or both, during startup and outside containment). .
shutdown. (27) Nuclear lasern==tmeian imikastel. -
(4) Boration or diludon, or both, dur-
. Ing power operation. "LMFBR reqmroments will be added in a
- (5) Any significant (10 percent) future revision.
1 power changes due to manual changes in control 5.5.1.2.2 Enewledge rod position or recirculation Dow. Theroqualificadonprogram,of Plant shallinclude Systems, review (6) Any reactor power change of 10 of system operational requiremente 68aA8=
percent or greater where iced change is perform- limitations, set points, tripe, alarms and the ed with load limit control or where Suz, required operator response to alarm and trip j
temperature, or speed controlls on manualifor conditions. ,
HTGRh
, *(7) Loss of coolant including: Acceptable methods to demonstrate this train-1 1. m== hat PWR steam genera- Ing may include; but are not limited to:
i tor tube leaks., . (1) Manipulation of the systems and
- 2. Inside and outside prunary con, their associated equipment.
tainment. (2) A walk.through of the ,. d..!
- l
- 3. Large and small, blaA4arlenk- steps required to start, stop or change condi-rate determination. tions of the systems.
! 4. Saturated Reactor Coolant re- (3) An applicable simulator (6.5.1.6) sponse iPWR). may be used to demonstrate knowledge of plant (8) Loss of instrument air (if systems; however, walk through is required to simulated plant specific). demonstrate knowledge of physical (9) Loss of electrical power (or characteristics of plant systema.
- degraded power sources, or both). 511 Cl Esewledge of FamiMey Chassea
- (10) Loss of core coolant Dow/ natural and Appileable Operneing r=p--& The pro-circulation. gram shall clearly indicate the methods to be (11) Loss of condenser vacuum, employed to assure each licensed individual is (12) Loss of service water is required e -at of facility design changes, procedurs....
for safety, changes, facility IIconse changes, and operating (13) Loss of shutdow's cooling. experience.
I (14) Loes of component cooling i system or cooling to an individual component. Acceptable methods may include; but are not
! (15) Loss of normal feedwater or nor. limited to:
l mal foodwater system failure. (1) Brieflectures conducted by the shift
- (16) Loss of all feedwater (normal and supervisor or other appropriate personnel.
emergency). (2) Staff meetings.
l (17) Loss of protactive system chan. (3) Written communications to each not licensed individual from facility management.
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t Amencan N:tional Standard ANSI /ANS 111981 (4) Explanscion of major changes as requires accelerated requalification in all
, part of the preplanned lecture series. categories graded less than 80 percent. Where a
- 15) Supervised discussion of applicable O opwating experience.
5.5.1.2.4 hview of Abnormal Emergency simulator is used as part of the retraining ex-ammation, an evaluation of each person's operating skills and capabilities should be in-and Security Proceduree. The program shall cluded as part of the overall ==aminadon.
Indicate the methods to be employed to assure 5.5.1.3.2 Annual Oral E===1= ados. An each licensed individual reviews the abnormal, annual oral requalification == amin = tion shall be emergency and security procedures. The sect.rity given. The == amination shall be graded as procedums covwed shall include only those pass / fall. Persons faillag the awaminadon shall which plant personnel have a need to know as require accelerated requali5cadon.
required by American National Standard In- 5.5.1.3.3 Certifiestion of Lleensed dustrial Security for Nuclear Poww Plants. Operatore. Every two years the competence of N18.171973 (ANS 3.3), subsecdons 4.2.4 and each operator shall be evaluated prior to relicens-4.7(1).[1] ing in accordance with paragraphs 4.3.1.1.d and 4.3.1.2 eeptable methods may include, but are not 5 .1.3.4 Accelerated hqualification. .
III Actual performance unttw abnormal Pomons mquinns accelerated mquaH8cah as -
a result of annual examinadon shall not perform
""d ""3'"*7 "" "*'
licensed duties until successfully completing the (2) Drills utdizmg a simulator.
- 13) A walk through of the procedural p lumd @wde shu k steps necessary to cope with the situadon.
, g gg ,,, g, (4) Shift in plant drill in response to und b th w*un w wal da Suc-abnormal or accident conditions. cessful completion of the program shall be (5) Brief lectures conducted by the shift measured by a ree===Instion of ladividual supervisor or other appropriate personnel camp a u dre d u n u n al (6) Self study combined with items 1 == amination or repeating the oral exammadon.
Successful completion of an accelerated roquali-8cados program shall be by grade criteria in 0 1 E alaadon. Annual eamminadons shall be given to each licensed operator and 5.5.1.3 5 5 e e Esaminadene. Other 5 . hanual Writua Emandmation. teen e=mminadons sham administand de The e= amination shall contain categoria of 4 the emm of de lectum Mw.The pmgram e= amination questions as follows: shall provide a grade criterion that the in-
- a. Theory and principles of operadon. dividual has learned the material presented. A
- b. General and specific plant operating de of h em 80 pt d @
addidomi mW in eat mbjus.
t instrumentation and control 5.5J.3.8 hedom. The pmerman sW
'Y***
- provide for systematic observation and
- d. Plant protecdon systems. documented evaluadon of an ladividual's perfor-
- e. Enginsend safety systems. ad compuncy. %td - w
- f. Normal, abnormal. and emergency other indicadons of degraded proficiency shall W avkwd by faculty managemet ud appm.
. dia control and safety.
- h. Technical Speciacations. ud.
- 1. Applicable portions of Title 10. Chap- 5.5.1.4 Condidened Lleesees. Some in-ter 1. Code of Federal Regulations. [2l dividuals have bwn issued licenses that only b Operadng espwience fmin se pwmit Mpulada of We entmis. Thw plants. individuals shall participate in a requalificados
- k. Items 7,8 and 9 from 5.2.1.6. program applicable to their responsibilities. The evaluation criteria specified in 5.5.1.3 shall also A grade of !as than 70 pwcent in any category apply to this program.
shall require accolwated requalification in that 5.5.1.5 Trainias Personnel. Training pw-category. A grade ofless than 80 pecent ovnall sonnel who are licensed are esempt from the pro-17 L
Amencan NIdeaal Standard ANSUANS.3.11961 visions of 5.5.1 for & area in which they have Certain personnel recorda associated with the prunary administrative responsibility. For ex- American Society of Madaaie=1 Engineers ;
ample, an individual who prepares, admmisters (ASME) activities should be maintained accord-and grades a written aramination need not take lag to American National Stardard Quality the ====ination. Assurance Program Requirements for Naclear 5.5.1.8 Applicable Simulator. Where a Power Plants. ANSUASME NQA 11979. [6]
simulator is used to meet the training require-ments for license candidates and requali8 cation training (5.5.1.2.1), the simulator shall have 6. References -
simular operating characterisdes to the trainee's own plant. For example, a once through steam (1) American Nadocal Standard Industrial generator plant simulator is not acceptable for Security for Nuclear Power Plants, trainist of personnel from "U" tube steam N18.171973 (ANS 3.3). American Nuclear generator planta. Simulators with convendonal Society, b Grange Park. Ill.
control rooms are not acceptable for training of personnel for plants with advanced control [2] Title 10 Code of Federal Regulations. Part center design plants. Consideration shall be 55, "Operescrs' Lle=== " Government -
given to other features such as training of per. Printing Office. Washington, D.C.
sonnel from two loop plants on a four loop simulator.
[3] American National Standard Adminis-5.5.2 Res.'s.g of Personnel Not Requiring trative Controls and Quality Assurance for NRC IJcesse. Nonlicensed personnel shall the Operational Phase of Nuclear Power receive annual retraining in the areas listed in paragraphs 5.3.1. 5.3.2. 5.3.3, 5.3.4. 5.3.5 as Plants. ANSUANS 3.21982. American Nuclear Society, I.a Grange Park. Ill.
appropriate, and 5.4. In addition, retraining shal! include: changes to the facility, pro- [4] American National Standard for Medical .
cedures, governmental regulations, and quality Certi8 cation and Monitoring of Personnel assurance requirements as well as ladustry Requiring Operator IJeanees for Nuclear O . operating experience.1. era, and personnel errors as applicable for their area of respon-Power Plants. N5461978 (ANS 3.4),
American Nuclear Society. La Grange Park, sibility. Ill. '
The retraining program may contain a grade [5] American National Standard Nuclear Power criterion for allowable exempdon from atten- Plant Simulators for Use in Operator Train-dance at a given lecture except for lectures on ing. ANSI /ANS 3.51981. American Nuclear 5.5.1.3.1.J. The minimum grade acceptable for Swiety, La Grange Park 111.
allowing esempdon from a perdenlar lecture is 80 percent la that category of the annual sa. [6] American National Standard Quality andnation per 5.5.1.3.1. Assurance Program Requirements for Nuclear Power Plants. ANSI /ASME 5.8 Deemenesseeles. Auditable records of the NQA.11979. American Society of Mechani-qualiscatione, experience, training, retraining cal Engineers. New York. N.Y.
and operator roqualiscadon program saamdna-tion for each member of the plant organizadon When the precedlag American Nadoeal Stan-covered by this standard shall be maintained for dards referred to in this docenant are saperseded a period of at least Eve years or as long as a by a revision approved by the American Na-person performs work in job categories de- donal Standards Institute, Inc., the revision !
scribed in this standard, whichever is shorter, shall apply. .
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Amaruna Nedcaal Standard ANSUANS3.11ss!
Appendix A ,
tThu Appendiz le not part of Amencan National Standard for Selection. Qualdwation and Traming of Personnel for Nuclear Power Planta ANSDANS3.11981. but is included for informadon purposes onlyJ Typical NRC Approved Ucense Candidate Training Program Training Segmente Nominal Durados Nuclear Power Plant Fundamentale (15 Weeks)
Principles of reactor operadon Design features General operating characterisdes Reactor instrumentation and control -
Radiadon control and safety Fundamentals of heat transfer, thermodynamics, and fluid flow related
, to transient analysis
. Plant Systems (16 weeks)*
Plant instrumentation and control systems Safety, fire and emerpacy systems Primary and secondary md=aical systems Electrical systems P! ant aunliary and support systems Plant protection systems O r= i s dit 7 --
Waste processing systems Integrated plant operation and casualty response Operating Praedee (17 weeks)
Simulator Operations (Includes Classroom) 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> Control Room Operation (Hot License Candidatae Only) 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br /> Praedeal Work Assignmente (Cold Deesee Candidates Only) (6 months minimum)
Pro License F=-l== dos (4 weeksi Pro License Audit Exams 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> In Plant Briefing 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Pro License Review Course 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />
' Hot license candidate's previous training and dudes may have provided these individuals with con-siderable knowledge of some of these systems, thereby permitting reduction of this segment's duration.
(See 5.2.1.2 of this standard.)
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m e Amencan N:donal Standard ANSIIANS 3.11M1 Appendix B P
U IThis Appendix is not a part of Amancan Nadonal Standard for Selecdon. Quahrtrassoa and TrainLag of Pereenmal for Neolame Power Manta. i NSI/ANS 3.11M1. bos is inchased for informados purpaae onlyJ Minimuns Education and Experience for ANSI /ANS 3.11981
. weeAYtou evemm.c Tamwa im - -- ,
Tsume .h A4mse ,
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selection, qualification and training of i personnel for nuclear power plants i
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Contents S=*=. Page
- 1. Scope.. .. . ... . . . .. . . .... . . .. 1
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- 2. Definidons . . . . . . . . . . . . . .. ... . .. . . .. . ....... 1
- 3. Functional Levels and Assignments of Responsibility . . . . . . . . . . . . . . . . . 2 3.1 General . . . . . . . . ... . .... . . .... .... ..... 2 3.2 Operating organizatica . . . . .. .. .. ... . . .. ... 2 3.3 TechnicalSupport Personnel . . . . . . . ... .. ........ .... . 3
- 4. Quali5 cations . . . . . . . . . . . . ..... ... ...... ....... ... 3 4.1 General . . . . . . . . .. .. ............. .................. . 3 4.2 Managers . . ... . ..... .. .. . . . ... .......... 4 4.3 Supervisors ..... . ....... .. ... ..................... 5 4.4 Professional. Technical ... .... . .................... 6 4.5 Operator. Technical. Maintenance Personnel . ...... ............. 9 .
4.6 Engineering and Technical Support Personnel . . . . . . . . . . . . . . . . . . . . 10 4.7 Independent Review Personnel . ... .. ... .................. 10
- 5. Training ..... ...... .. ..... . . ... ................... 10 5.1 General Aspects . . . . . . .... .. . .................. 10 .
5.2 Training of Personnel to be I.icensed by the NRC . . . . . . . . . . . . . . . . . . 11 5.3 Training of Personnel Not Requiring NRC Licenses . . . . . . . . . . . . . . . . . 13 5.4 General Employee Training . . . . ... .. .. . ................ 14 5.5 Retraining . ........ ......... ... ................... 15 5.6 Documentation . . . . . . . . . ... .. ....... ................. 16
- 6. References . . . ... . ... . .... ..... .... .......... . 18 Appendia A Typical NRC Approved License Candidate Training Program . . . . 19 Appendix B Minimum Education and Experience for ANSI /ANS.3.1 1981. . . . 20 I
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)U tkn c:toinalve report on the U.S. Nuotoar Regulatory Cotnmission Vol. 7, No. 24 - Nu mtar 25,1985 NRC RESPONDS TO INPO LETTER WITH HARD LINE ON TRAINING AND MAINTENA The Institute of Nuclear Power Operatiom (INPO) will hase to be more open in sharing infor-marion on utility training and maintenance programs "if NRC is to be able to step back while industry attempts to correct its clearly identified problems" in those areas, NRC Executise Director for Opera-tions William Dircks has told INPO President 72ck Pate.
Dircke remarks were made in a letter responding to an INPO letter alleging that NRC staffis "unpethng or undermining" INPO efforts by re-examining utility training programs after they have bcen aaredited by INPO and by demanding access to specific data by plant name (INRC,29 Oct.,1).
Although he chaiaeteriied as " clearly a move in the right direction" INPO% willingness to rnake its fi.
nal accrnhtation team seports and plant evaluation reports available for review by the NRC staff, {.
t Dircks said,"There are sneral areas where additional accen to the details that e tablish the basis for i INPO findings and conelmiom is necessary " ;
Dircks charged that the original NRC/INPO agreements on maintenance indicators "hase fallen ,
b) the wayside" and that INPO has recently reneged on its pledge to allow agency staff to select INPO training documents for resiew. INPO h..d originally agreed to let NRC examine plant +pecific data at the indmiry gronp% emen, but refused to allow records to be remmed from there, according to NRC omebts in a letter pn nding the Direts rnpinse, NRC Deputy Esecutise Director Victor Stello told I INPON C. O. h.Jy. w. psu.nl of Florida Power & Light Co.,"It appears that our onginal amensnt ten tw.ntoana ! o no lasting meaning, and this has placed NRC in an unacceptable pwi-tion." '
}O V in an addrew to the Atomic Indmirial l'orumi recent annual conference. Dircks sowed. "Nf is not about to stand back and say,it% not our bminew to probe beneath the surface to look at train-(
ing, at snaintenance, and at prm urement practices became these are management (wues." Citing recent agency stnibes of Toledo Pdison Co's Dasivilewe, Public Sersice E!cetric & Gas Co.4 Salem, and oth-er plmts. he said inanagerial deficiencies at those facihtin "were clear to m. They mmt ha$e been slear to iNPO."
P inh took much the i.arne hard line in his repome to INPO% demand that NRC stay on the d!a t, of maintenance and trainir.g iwues "The current positiom being taken by INPO in these areas n(ed to l'c rictified promptly," he imisted, asking the inJmtry group to inform NRC "when >ou will N pre; arnt to work with u to ntablish a tenabic arrangement for acccu to the detailt"
-Eric l.indeman. Ncw York i . C LilH. G I!: FO CARRY CALL ON GETTlHG SOi'.E SAFETY PR001. EMS CORRECT NP.C is dep oding en wluntary utilit) resromn to In titute of Nuelcar Power Operatiom s
llNPO) safil) notten to pel solHe generic %%Isly iwucs corrated. NRC% Omee of Impection & En.
forect ant ilE) stafT is followinf those iwuc by sursc>ing utility rnpomes, which hase been found ade-ip et in enc case and ina.i.quate in another in the latter c.we, IE iwued a bulletin requiring utilit ti a t at s'ni so 10 months after another NRC omee had declared the problem a generic ufety l**ue.
'ihe INPO safet) neuen calicd dgmficant operating experience reports (SOERs), are not pubbe 14 e !! Isdhrins and are lapt wnfidemi.d b) NitC. There is em asailable list of the tories on which
' RC a wa ang for INI'O to get enulis. and NRC okab .uJ there are no hard and.f.nl ruin for de
.l v , nl..n to Ic.n c ; n n we up to INPO
- llh ITNs to olabIlsli (of final op.*ratifi/ proeC' II .55%.d a In.til,thttibt;r 29 rngintilip t'tlhMJ lla luffetm was ioned after IE dettemined er. . to c.WJ st6am hmJoy m aunhar) fnde.a:ct pn ips -_
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