ML17324B282
| ML17324B282 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/13/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0773X, AEP:NRC:773X, NUDOCS 8703190510 | |
| Download: ML17324B282 (16) | |
Text
REGULATORY " FQRl'IATIQN DISTRIBUTION BY 'N'R IDB)
ACCESSION NBR: 8703190510 DOC. DATE: 87/03/13 NOTARIZED:
NO FAC IL:50-3f 5 Donald C.
Cook Nuclear Pouer Plant'nit 1 i Indiana 5
50-3fh Donald C.
Cook Nuclear Potoer Planti Unit 2i Ind iana 0
AUTH. NAIVE AUTHOR AFFILIATION ALEXICH>N. P.
~~c Nichigan Electric Co.
RECIP. NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 0 05000315 05000316
SUBJECT:
Responds to NRC 870304 ltr re audit oF Facility DCRDR suppls,util 861230 DCRDR summary rept. Implementation schedules For correction oF human engineering deFic iencies (HED>
Sc completion dates 5 listing oF new equipment encl.
DIBTRIDOTION CODE:
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TITLE: QR/Licensing Submittal:
Supp l 1 to NUREQ-0737(ceneric Ltr 82-33)
NOTES:
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INDIANA 8 MICHIGAN ELECTRIC COMPAN Y P.O. BOX 16631 COLUMBUS, OHIO 43216 March 13, 1987 AEP'NRC:0773X Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 DETAILED CONTROL ROOM DESIGN REVIEW AUDIT RESPONSE U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Dear Sirs:
The purpose of this letter is to transmit our response to your letter of March 4, 1987 and to the comments of NRC audit of the D.
C.
Cook Nuclear Plant Units 1 and 2 Detailed Control Room Design Review (DCRDR).
This information also supplements the data provided in our DCRDR Summary Report submitted with our letter AEP:NRC:0773V, dated December 30, 1986.
1
~
Attachment 1 to this letter provides an implementation schedule for correction of safety-significant human engineering deficiencies (HEDs) in Categories I and II.
Please note that 70 percent of the corrective actions are scheduled for implementation by the end of 1987 and 80 percent by the end of the next Unit 2 refueling outage.
We believe the schedules proposed in the Summary Report also show that we are implementing the bulk of the higher priority corrections as early as practical.
It should also be noted that several completion dates are shown in Attachment 1 as April 1987 and June 1987.
These involve component labels for Unit 1 and annunciator window engraving and color coding tasks on both units.
We estimated in the Summary Report that these tasks would be complete by March 1987.
This schedule slippage is due to the reiterative design review process and the use of specialized installation personnel for the enhancement projects.
Thorough engineering and operations review of designs and careful, methodical construction and installation of thousands of labels and windows are taking more time than estimated.
We believe we are carrying out these projects in the most expeditious manner practical.
8703190510 870313 PDR
- DOCK 05000315' PDR~
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AEP:NRC:0773X 2.
The following response addresses the audit team's comments on HEDs identified during the mini-control room survey.
a)
The glare shields for RVLIS indicators NLI-110, 111,
- 120, 121, 130 and 131 were found to cast shadows on the indicator scales during the control room audit.
These indicators were not installed on the panels during the human factor surveys by ESSEX in 1984.
There are over one hundred curved glass vertical indicators in the top row of panel space throughout the control room, none which have glare shields, except the six RVLIS indicators.
Because of the shadows, it is obviously better not to have glare shields.
We currently plan to remove the shields during the next refueling outages.
b)
The NRC audit team found a hand-drawn scale for a potentiometer on the Unit 1 Delta Temperature Unit (DTU)
Panel.
This scale was reviewed by engineering and found to be unnecessary, and the scale has been removed.
c)
The NRC audit team found some holes in the Unit 1 Flux (FLX)
Panel where the wind speed and direction indicators were mounted.
These indicators were removed for maintenance and will be reinstalled.
3.
The following are three HEDs which we had identified but had not yet, resolved.
a)
HED Vl-21 concerning containment ambient temperature determination relative to the pressurizer PORVs discharge line temperature in Emergency Operating Procedure E-3, Step 19, will be resolved by implementing more specific instructions in the procedure.
This will be done during the next scheduled biennial review.
b)
HED 1.3-8 concerns lack of written or posted instructions for emergency equipment.
This will be resolved by June 30, 1987 by implementing posted instructions or emergency equipment where no posted or hardware instructions now exist.
c)
HED 6.1-49 concerns several unlabeled panel components.
This has been resolved by labeling the few panel mounted devices that had no component label whatsoever.
This was completed in February 1987.
The audit team expressed a desire for a schedule for completion of a list of specific HEDs identified in the pre-audit letter Appendix B4.
Attachment 2 to this letter provides an implementation schedule and planned completion dates for those HEDs.
Attachment 3 to this letter provides a
complete listing of new equipment planned for installation as a result of the System Function Task Analysis (SFTA).
These items are identified in the Summary Report but not specifically identified with the SFTA.
AEP:NRC:0773X The audit team also expressed a concern with the steam generator panel rearrangement schedule in that there may be a period of time when the Unit 1, Unit 2 and the Simulator control room panels will be different.
The D.
C.
Cook Training Department is planning to develop a training and operator working schedule to minimize the impact of this difference in configuration.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.
. Al ich Vice President cm Attachments cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis NRC Region III
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDs Cook DCRDR - Category I & II Corrective Action Implementation - Planned Completion Dates CLO/HED CAT.
- 1. 1-5
- l. 1-9 1.1-10 1.2-1 1.2-2 UNIT 9-86 9-86 12-86 UNIT 2 9-86 9-86 12-86 l.3-1 2
1.3-3 4
5 12-86 12-86 12-88 12-87 12-86 12-86 12-86 12-88 12-87 12-86 6
7 1.3-8 1.5-2 3
12-89 12-86 6-87 12-89 12-86 6-87 4
7
- l. 7-2 2.1-1
-2
-3
-4
'.1-5
-6
-7
-13 3 0 1 2
-3
-4
-5 4-87 9-86 12-89 12-89 12-89 12-89 12-86 12-89 12-89 9-86 6-87 12-86 6-87 2-87 9-86 12-89 12-89 12-89 12-89 12-86 12-89 12-89 9-86 6-87 12-86 6-87
-7
-8
-11
-13
-17 9-86 6-87 12-87 9-86 9-86 6-87
" 12-87 9-86 See page 6 of this attachment for codes and abbreviations.
Pg.
1 of 6
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDs Planned Completion Dates Cont'd CLO/HED CAT.
UNIT 1
UNIT 2
-20
-21
-22
-23
-24
-27
-30
-32
- 4. 1-1
-3
-5
-9
-10
-20
-22 5.1-4
-6
-8
-11
-17
-46
- 6. 1-1
-3
-5
-6
-7
-16
-20
-21
-23 II II II II II IIIII 6-87 NA 6-87 6-87 NA 6-87 9-86 NA 12-86 9-86 9-86 NA 12-87 12-87 4-87 4-87 4-87 NA 4-87 12-87 4-87 6-87 NA 6-87 6-87 NA 6-87 9-86 NA 12-86 9-86 9-86 NA 12-87 12-87 2-87 2-87 2-87 NA 2-87 12-87 2-87
-24
-31
-35
-37
-40 9-86 9-86 9-86 9-86 9-86 9-86 9-86 9-86 Pg.
2 of 6
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDs Planned Completion Dates Cont's CLO/HED CAT.
UNIT 1 UNIT 2 6.1-43
-44
-46
-47
-49 4-87 12-87 4-87 4-87 2-87 2-87 12-87 2-87 2-87 2-87
-57
-60
-61
-63
-64 12-87 9-86 12-87 12-87 9-86 12-87
- 7. 1-1
-3
- 8. 1-1
-13
- 9. 1-1 12-91 12-87 4-87 9-86 12-91 12-87 2-87 9-86
-2
-4
-6
-7 Vl-4 6-87 6-87 See Vls
& V2s II 1I
-16
-25
-26
-42
-47 12-86
-57 V2-1
-5
-6
-9 6-86 6-86
-17
-18 8-86 8-86 Pg.
3 of 6
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDS Cook DCRDR Cat. III-S Corrective Action Implementation Planned Completion Dates CLO/HED UNIT 1 UNIT 2
- l. 1-1
- 1. 4-1 1.7-4
- l. 7-7
- 2. 1-9
- 3. 1-6
-9
-10
-15
-19 12-86 12-87 9-86 9-86 12-87 9-86
- A'*
12-86 12-87 9-86 9-86 12-87 9-86
-26
-31 4.1-4
-8
.13
-14 5.1-3
-18
-19
-44 6-87 NA 6-87 6-87 12-86 6-87 NA 6-87 6-87
-48
-50
- 6. 1-2
-4
-8 6-87 12-86 4-87 6-87 12-86 2-87
-11
-12
-13
-14
-22 12-86 12-86 4-87 4-87 4-87 12-86 12-86 2-87 2-87 2-87
-27
-32
-39
-42
-51 4-87 9-86 9-86 12-87 2-87 9-86 9-86 12-87 Pg.
4 of 6
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDS UNIT 2 Planned Completion Dates Cont'd. III-S CLO/HED UNIT 1 6.1-53
-55
-59
-62
-66 6.1-67
-69
-70
-71 7.1-14 4-87 4-87 12-86 12-87 12-87 4-87 9-86 9-86 12-'87 2-87 2-87 12-86 12-87 12-87 2-87
,9-86 9-86 12-87
-20 8.1-6
-10
-12 12-87 12-87 12-87 12-87 Pg.
5 of 6
AEP:NRC:0773X Attachment 1
SAFETY SIGNIFICANT HEDs Codes for approximated Outage Schedules:
Unit One Unit Two Unit One Unit Tvo Unit One Spring 1987 Refueling Outage Early 1988 Early 1989 1989 Steam Generator Replacement Outage Late 1990 Refueling Outage NA = No Action
~Not Applicable Total'= 151; 6
No Action; 88 in 86/87; 28 in First Outages or 80% Fixes Planned By First Outages Abbreviations CLO = Checklist Observation HED = Human Engineering Deficiency Pg.
6 of 6
AEP:NRC:0773X Attachment 2
Cook DCRDR Item B4.
NRC Audit Implementation Schedules Planned Completion Dates CLO/HED CAT.
UNIT 1 UNIT 2
- 1. 1-8
- 1. 1-10 l.4-1 1.4-2 1.7-5 2.1-10 2.1-11 2.1-12 3.1-3
-4 III II III-S IVIII III III III IIII 12-86 12-86 12-87 12-87 9-86 12-86 6-87 12-87 12-86 6-87 12-86 12-86 12-87 12-87 9-86 12-86 6-87 12-87 12-86 6-87
- 3. 1-9
-15
-30 4.1-8 4.1-16 III-S III-S IIII-S III 9-86 9-86 5.1-4 5.1-50 6.1-1 7.1-20 8.1-6 II III-S II III-S III-S 4-87 12-87 2-87 12-87 9.1-7 Vl-65
AEP:NRC:0773X Attachment 3
Cook DCRDR New Panel Equipment to be added to satisfy SFTA ICCR Review New E ui ment HED Ref.
SG Pressure Recorders SG Stm. Relief Valves Position Indication PRZ Spray Valves Position Indication Containment Isolation Status Indication FW Isolation Alarm SI Pump Disc Flow Square Root Extractors BIT Flow to Loops Square Root Extractors Vl-16 V2-6 V2-17 V1-12, V2-12 V1-24 V1-25 Vl-26 RFS:le(GEN9-v)
March ll, 1987 DOCKET NO(S).
50-315/316 k1e. John Dolan> Vice President Indiana Indiana and llichigan Electixc Company c/o American Electric Power Service Corporatbhn 1 Riverside Plaza Columbusi Ohio 43216
SUBJECT:
D. C. Cook Nuclear plant> Units 1 and 2 Di'stribution:
PRC System PWRN4 Rdg MDuncan DWigginton ACRS (10)
OGC-Bethesda MYoungblood JPartlow BGrimes E7ordan NThompson Notice of Receipt of Application, dated s
Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.
dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License.or Amendment to
~ Faci1 ity Operating License, dated Qx Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No Significant Hazards Considerations, dated 02/26/87 'see page(s) ]
5857 Exemption, dated Construction Permit No.
CPPR-
, Amendment No.
dated Facility Operating License No.,
Amendment No.
Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-dated transmitted by letter dated
. The following documents concerning our review of the subject facility are transmitted for your in'formation.
En cl osures:
As stated Office of Nuclear Reactor"Regulation cc:
See next page t
OFFICE)
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DATE0 l
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/87 "
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NRC FORM 318110/80) NRCM 0240 OFFICIAL RECORD COPY
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