ML20203N502

Requests mark-up of Encl List of plant-specific Actions to Implement Approved Regulatory Improvements by 860531.Readily Known or Best Estimate Dates Acceptable.Omb Clearance Cited

ML20203N502
Person / Time
Site:	Byron
Issue date:	04/29/1986
From:	Olshan L Office of Nuclear Reactor Regulation
To:	Farrar D COMMONWEALTH EDISON CO.
References
TASK-1.D.1, TASK-1.D.2, TASK-2.K.3.05, TASK-TM NUDOCS 8605050456
Download: ML20203N502 (3)

Text

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,- 1 Docket Nos.: STN 50-454 Mr. Dennis L. Farrar Director of Nuclear licensing Conmonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Gentlemen:

The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." To correct this situation, the Nuclear Regulatory Conmission is working on a long-term program which will improve its documentation on the status of power reactor licensees' implementation of approved regulatory improvements.

To assist me in developing this information for Byron Station, Unit 2, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirement were completed / implemented or are expected to be completed. For each requirement that has been completed, enter " completed" under the Status column and the date the item was completed. For requirements that have not been campleted/ implemented, provide the projected date and enter " projected" under the Status column. I do not expect or want a major effort made to obtain precise dates. Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented. For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time. For projected completions / implementations in 1986, use month and year. Use year only for projections thereafter. Please provide a response in the form of a marked up listing by May 31, 1986.

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In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.

This request is covered by 0M8 Clearance Number 3150-0011, which expires September 30, 1986.

Sinc rely, h/

leonard N. Olshan, Project Manager PWR Project Directorate #5 Division of PWR licensing-A EncEosure: /

PD#5 As stated T D l01shan 4/29/86 Distribution:

Docket Files OELD B. Grimes NRC PDR J. Partlow T. Novak local PDR E. Jordan M. Rushbrook PD#5 R/F ACRS (10) 8605050456 ADOCK hS4 PDR PDR P

R-1208731-001 RE@ULATORY INF0RMATION TRACKI'NO SYSTEM PAGE NO.s FACILITY IMPLEMENTATION 03/31/Q BYRON 1 (CONTINUATION)

TAC NO. LIC ACT LICENSEE MPA 9 TITLE COMPLETE STATUS palg

, M57197 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM ,

M57196 F-71 I.D.f.2 DETAILED CONTROL ROOM REVIEN (FOLLOWUP TO 03/01/87 '

M60889 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.5.5) e

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E R-1208731 A.0 01 REGULAT0RY INF0RMATION TRACKINO SYSTEM PA0E NO. i FACILITY IMPLEMENTATION 03/31/i FACILITY: BYRON 1 PLANT LOCATION: 17 MI SH OF ROCKFORD, ILL LICENSED P0HER: 3411 MHT PROJECT MANAGER: L. OLSHAN DOCKET NUMBER: 050-00454 DESIGN POWER: 1120 MHE BRANCH CHIEF: V. NOONAN ARCH / ENGINEER: NSSS VENDOR: HEST LIC. ASSISTANT: M. RUSHBROOK S8p IE INSPECTOR: .

LIC ACT LICENSEE MPA 4 TITLE COMPLETE STATUS palf IAL NO.

M57198 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 06/01/87 M59077 A-20 10 CFR 50.62 OPERATING REACTOR REVIEHS N//S /

M59942 A-21 to CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M56274 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 07/11/85C M55276 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 01/02/86 M55278 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/26/85C M55279 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/05/85C M56282 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/26/85C M56'283 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 08/30/85 M56285 B-82 ITEM 4.5 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 03/13/85C M56275 B-85 SALEM ATHS 1.2 DATA CAPABILITY 04/01/86 M56277 B-86 SALEM ATHS 2.2 S-R COMPONENTS 01/02/86 M56280 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 09/26/85C M56281 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/05/85C M56284 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 M56785 B-90 SALEM ATHS 4.3 H AND S&W T.S. 01/02/86

'M56287 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/26/85C M55288 B-95 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES M58G46 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN M57199 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 03/27/86

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