ML20197H558
| ML20197H558 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/14/1984 |
| From: | Eddleman W EDDLEMAN, W. |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| 82-468-01-OL, 82-468-1-OL, OL, NUDOCS 8406180443 | |
| Download: ML20197H558 (10) | |
Text
Lb 2-RELATED CORRESPONDENCR June 14,;S.50 DW UNITED STATES OF AMERICA 1984*
NUCLEAR BEGULATORY COMMISSION
.g4 g;gg gjj:12 BEFORE THE ATOMIC SAFETY AND LICENSING BOA Glenn O. Bright Dr. James H. Carpenter James L. Kelley, Chairman In the Matter of CAROLINA POWER AND LIGHT CO. et al.
)
S ar Harris Nuclear Power Plant, ASLBP No. 82-466-01
)
OL Wells Eddleman's Response to Summary Disposition on Contention 132(c)(2) (Control Room)
Since the last response, Applicants have informed me through their counsel Hill Carrow (and others) that indeed they had not copied the cabinet layout blueprints; that these could not be readably copied; and that these were the best available blueprints of the control room cabinet fronts.
Counsel Carrow also informed me that no mockups of the control room cabinets were used in the Detailed Control Room Design review -- only for the Main Control Board were mockups made.
Applicants then kindly lent me the original blueprints, delivered by messenger, for use in responding to their motion for summary disposition.
I cannot get them copied at full size.
Therefore some copies of relevant parts of some prints (at full size, or blown up to larger-than-original siaze if possible) are used to illustrate this response.
As can be seen by inspection, most of the prints
- This filing date by hand-service at the first day of hearings was anuroved by the Board, Applicants and Staff, see transcrint of 6-12-84 conferenes call.
8406180443 840614 PDR ADOCK 05000400 G
i PDR
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2 DO NOT show the actual appearance of the lights, gauges, meters or l
other indicators on these control room panels, but only the location and/or general shape of cortain devices and indicators.
Since Applicants have said this is the best infonation available to show the appearance of the fronts of the control room cabinets, I can see no way they could have analyzed it as to readability, visibility, signal density, contrast, or other human factors.
From the size of some of the indicators, especially those referred to in the last response (filed June 5, 198h) re panel 11, etc, 4
one would have to be close to them to read them accurately, especially if the labeling of the indicator is not large print.
Few, if any of the blueprints CP&L has provided show the size or sort of print that identifies the indicators on any of the panels of concern in this contention.
Given that this information is the best they have, it is exturemely difficult for me to see how they could have analppum yzed it to show that operators could see and use the information.
For example, documents 000611 and 000612 relate to radiation montizoring information on panels 12 and 13 These include the plant vent stack, snent fuel pool, " cont post loca (Loss of Coolant Accident" area, and many legations within the plant, e.g. containment atmosphere leak detection system, constaingment isolation system, and air intakes 0 including emergency ones) for the control room itself.
From the description, the Unit 1 cabinet contains a great deal of information, not all of which can be displayed at large size (see typical cabinet front view on document 0006111.
7 6
Panels in and 12 contain nuclear instrumentation and incore instrumentation, respectively.
Although #17 is said to be duplicated on the main control board, (Applicants' motion, p.7), #16 is of great potential importance in an accident (e.g. TMI).
3 I
The problem of integrating the information is that one operator would have to go near, e.g., panel 16, or panels 12 and 13, to read the info, and relay it back to another operator who is also picking up information from an operator at the Main Control Board or operator's desk or at a location along panels 1-5 or 8-11.
This doesn't leave any of the 3 operators actually running the plant, unless dhey can run it with their hands behind their backs while facing back toward the panels.
Applicants assert that operators would not remain near these panels for long.
That may be true, but they would evidently have to go to the panels for information, e.g. on incore instrumentation and on radiation monitoring, and then relay it back.
The potential for confusion or error is obvious, and relaying information as Applicanta postulate would require all the operators (3), one at one set of panels, one at a desk or the control board, and one at another panel, again leaving no one running the plant or witchigg the main control board.
To re-emphasize, the information provided re the layout and design of the control room cabinet fronts does not allow the sophisticated analysis which the DCRDR (NUREG-0727 Rev. 1) requires.
Applicants cbiticize my response (Motion, p.7) that more detailed analysis is necessary.
Even with these blueprints, the analysis is limited to the kinds of information, because generally the size and manner of display of the information are.not shown on the prints.
i Assuming Applicants to have truthfully represented the attached bluenrint i
segments (I'11' send the originals to the Board if Applicants will let me, and will show them to the Board at the hearing on June 14-15),
f there is.no way they could have meaningfully analyzed human factors in picking up and using and integrating information.from these panels.
Yet much of the information, as noted. above, is very imnortant for This Applicants' Motion
~ controlling adcidents and protecting the public.
should be denied.
c
_ ~
INTERROGATORY NO.132C(H)-9. Please provide in dstan all fzets and oth:r information and identify all documents which support your statement made in response Interrogatory 132C(D)-4(a) that Applicants "are in violation of GDC 1 (10 C.F.R. 50 A A) because the control room is inadequate to its purpose and functionc."
9.
Analysis continues when I have mo're time.
If you can't i
read information or it can't be coordinated in an accident so 2 that the info is not useful or timely or accurately available (e.g.
as described in the contention) you are. violating GDC 1 by not having your equipment safely designed and,able to perfom its I
functions, if the problem is caused by the equipment layout.
Setting this layout into concrete before the NRC finished reviewing your nonstandard DCRDR is also a mistake: mismanagement, i
I and bad design to t he extent it does not rectify mistkkes made t
that are identified or exparessed in the ' contention.
j i
I INTERROGATORY NO.132C(II)-10. Please provide in detail all facts and other information and identify au documents which support your statement made in resonse to i
l Interrogatory 132C(II)-4(a) that Applicants are "also (in violation of GDC 19 because t alpplicants] can't maintain the plant in a safe conhition under serious (e.g. LOCA) accidents."
_ gg MSl46X. ' See the LOCA rionitor on panels 12 or 13; lack of incore instrument info except from obscured panel 16, i
which is important, e.g. in the TMI accident which was effectively a Small ~ Break LOCE and was not kept under control safely, at all times.
INTERROGATORY NO.132C(H)-11. Please provide in detan all facts and other -
information and identify au documents which support your statement made in response to
(
Interrogatory 132C(H)-5(b) that "the signal density analysis on pp 6-11 is just exactly backwards of what is needed for accidents...."
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I think-it speaks for itself with the i
following explanation, but if you want I can do some more analysis, amassc. m
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