ML19341A643
| ML19341A643 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/21/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0752, RTR-NUREG-752 L1L-019, L1L-19, NUDOCS 8101270592 | |
| Download: ML19341A643 (3) | |
Text
N 1
e Metropolitan Edison Company y
Post Office Box 480 Middletown, Pennsylvania 17057
- 71) 9444041 Writer's C rect Dial Number January 21, 1981 LIL 019 Office of Nuclear Reactor Regulation Attn:
R. W.
Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Three 3dle Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Human Factors Engineering The Nuclear Regulatory Commission's Control Room Design Review report for TMI-1 (NUREG 0752), transmitted by NRC Letter dated December 22, 1980 to H. D. Hukill from R. W. Reid, indicates action which TMI-1 is expected to take prior to restart.
This letter is intended to document that, with the exception of the items discussed below, we are presently undertaking such actions and plan to complete them prior to restart.
- 1) Section 9.0.a states that "a newly designed remote shutdown pz.nel...
will be implemented".
Work is presently underway to design and procure the equipment associated with this panel.
There appear to be, however, problems in obtaining this equipment on a schedule consistent with completing the modifiestion prior to restart.
In addition, we are curreatly evaluating rle newly issued Appendix R to 10 CFR 50 which establishes some new recuirements and schedules.
We, therefore, plan on completing the <urrently planned remote shutdown panel and it's associated em.rgency lighting during the first refueling outage following restart.
This proposal will be
~
discussed in greater detail in a separate submittal.
- 2) Section 14.c reauires that a backup display system for selected in-core thermocouples be installed prior to restart.
This item will be addressed in our response to NUREG 0737, to oe sent in the very near future.
We currently have two different means of reading in-core thermocouples (computer readout and an operator using portable test equipment).
- 3) Sections 7.b through e discuss alarm sound levels and state that they will be adjusted to oLeain a level "6-10 dba above che ambient noise".
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R. W. Reid L1L 019 e
It is our intent to. perform tests on audible tones for individual alarm systems and to adust these tones so that (1) each is clearly audible and distinguishable above normal control roem background and (2) operators can communicate with each other while the~ tone is sounding.
It is expected that this will result in individual tones being set at a-level of 6-10 dba above the ambient noise in a one -
octave band.
'We believe this meets the intent of the commission's.
requirements.
- 4) Section 9.0.c src.tes "a sound powered microphone / headset will be permanently available at the-remote shutdown' panel."
A more detailed evaluation of the. appropriate communication system-for the remote shutdown panel has recently been performed.
The resn'ts indicate that the preferred approach is to use the exf ting maintenance and instrument communications system.
Mod -
ifications willine made to this system so that it is independent of both the control' room and the relay room.
We believe this
. meets the intent of the commission's reauirements.
- 5) Section 13.b states that ".
. light fixtures will be moved..
An evaluation will be made of the adeauacy of the emergency lighting in the' control room, but light fixtures will be moved only if this is determined to be required.
We believe this meets the intent of the commission's requirements.
. 6) Section 3.e discusses burned out bulbs in legend indicators.
Currently bulbs that are normally lit are checked on a daily basis.
For those bulbs which are not normally lit in the Engineered Safeguards (ES) and Emergency Feedwater (EFW) systems, surveillance procedures will be modified to check indicators when the status of the component is changed during the test.
Du';ing the biannual review of tech. spec. surveillance procedures for other systems they will be modified to check light operation.
- 7) Section 3.d addresses the interchangeability of legend switch covers.
New labelling will be added to the panel vice changing administrative or operating procedures to ensure that switch covers are return'ed to the proper location.
~
- 8) Section 4.c recommends placing normal operating ranges or setpoints on vertical meters.
In order to clarify the issue, only instruments with well defined operating ranges and setpoints will be marked.
However, meter faces will not be cluttered to the point of operator confusion.
In addition to those actions to be taken prior to restart, NUREG 0752 also discusses certain further improvements which will be developed on a long-term basis.
This is in general consistent with the licensee's
- plans as indicated in the GPU Design Review Report discussed below.
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'R.-W.-Reid' L1L 019 With specific reference to section 3.b, 3.d, and 3.g, however, we believe that the short term corrective actions addressed in Met-Ed/GPU.
Letter ILL 559 dated November 7, '1980 to R. W. Reid from H. D. Hukill, is fully adequate and we presently plan no additional actions related to these specific findings..
As indicated in NUREG 0752, GPU has independently performed a control room design assessment.
A copy of the report discussing the results of_this review has been separately submitted to you.
This report also discusses methods-for addressing the deficiencies which were identified by our review.
As we have previously discussed withivou'there is substantial commonality between the GPU and NRC findings.
The recommended-actions developed from the GPU Design Review Report are-
. summarized in. Table III-1 starting on page 25 of the Design Report.
Our current plans for implementing these recommended actions are as follows:
1.
The'following items are currently planned to be completed prior to restart - mosc. of these items are also identified as restart modifications.in NUREG 0752:
1, 2, 3, 4, 5, 7- (light readability),
.8 (flow indication), 9, 11, 12, 13 (scales), 17, 18, 19 (maintenance and repair), 20 (glare reduction), 21, 22, 29, 30, 31, 34.
2.
The following items are scheduled for completion during the first refueling outage following restart.
In some cases, however, depending upon availability of engineering and materials and contingent upon the actual restart date, selected items or portions of items might be completed prior to restart:
7, 8, 20, 23*, 24*,
25, 26, 27, 28, 32, 33.
3.
The following items can be pursued while the plant is in operation and are expected to be completed by the end of 1981:
6 and 10.
4.
The following items require detailed engineering studies which are expected to start sometime in 1981:
13, 14, 15, 16, 19, 35, 36.
Those items marked with an asterisk indicate that the recommendations in the CPU Design Review Report will be implemented somewhat differently than indicated in the report, but in a manner which adequately addresses the deficiency.
Sincerely, H. D. H kill Director TMI-1 HDH/RWK/jes cc: D DiIanni H. Silver S. S. Hanauer V.'A. Moore