ML20247J020
| ML20247J020 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/08/1988 |
| From: | SARGENT & LUNDY, INC. |
| To: | |
| Shared Package | |
| ML20247H448 | List: |
| References | |
| 8406-25, CID-MISC-08, CID-MISC-08-R00, CID-MISC-8, CID-MISC-8-R, NUDOCS 8906010014 | |
| Download: ML20247J020 (31) | |
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(, W Chicago, tilInois 606fo~. 0i67 ~ 4 gM%f l March 1, 1988 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mashington, DC 20555 i
Subject:
LaSalle county Station Units 1 and 2 Detailed Control Room Design Review (DCRDR) Implementation NRC Docket Nos. 50-373 and 50-374 References (a): Letter from D.R. Miller to L.D. Butterfield dated September 9, 1987 ) (b): Letter from C.M. Allen to L.D. Butterfield dated April 21, 1987
Dear sir:
This letter is in responda to the Safety Evaluation Report (SER) regarding the De.siled Control Room Design Review (DCRDR) transmitted in The response has been delayed in an attempt to obtain realistic Reference (a). This delay was discussed with members of your staff. implementatt~<n dates. 29, 1985 The SER commented on commitment dates provided in an October In Reference (b), new commitment dates letter from H.L. Massin to H.R. Denton. were provided with the caveat that work on Human Engineering Discrepancy (HEDs) requiring major changes would await NRC approval of proposed resolutions. Commonwealth Edison is continuing to work toward completion of HEDs on the schedule attached but needs closure with NRC on resolution of items still open. ) I 3 ff
US WRC MGrch 1, 1988 l The attachment to this letter includes all HED findings, responses, and' proposed schedules for implementation of the respective corrective L actions..This proposed schedule, is also predicated upon NRC approval of Ceco's disposition of each of the HEDS. This schedule is also subject to the availability of equipment, outage time availability at the applicable station, l and engineering design lead time. Some problems affecting more than one l emergency response activity will require an evaluation to assure that integrated corrective action is taken. The activities will also affect the proposed schedule. A meeting to work directly with members of your staff to disposition each of the open items is requested as soon as possible. If you have any i l further questions regarding this matter, please direct them to this office. v ry truly yours, s C. M. Allen Nuclear Licensing Administrator 1m Attachment cc:
- p. Shemanski - NRR Regional Administrator - RIII NRC Resident Inspector M.C. parker - IDNS
m I, f. C*f ' 72 West Adams Street. Chicago, Illinois ; c:mm:nwz!th t$ son. g Z \\ V 87 Address Reply to: Post Office Box 767 Chicago, Ilknois 60690-0767 Ag]z - p June 30, 1986 Mr. Harold R. Denton, Director Office of Nuclear. Reactor Regulation U.S. Nuclear Regulatory Commission Washington,.DC. 20555 ~
Subject:
LaSalle County Station Unts,1 and 2 Safety Parameter, Display System Human Factors Review and Parameter Selection verification NRC Docket Mos. 50-373 and 50-374 Refarences (a): LaSalle County Station Unit 2 License NPF-18, Facility Operating License (Att. 2) (b): Commonwealth Edison Campany (CECO) letter, C E. Swartz (Ceco) to H. Denton Nuclear Regulatory Commission (NRC) dated December 29, 1983 with attachment. (c): NRC. Safety Paramet'r Display System Safety Evaluation for Dresden, Quad Cities and LaSalle'to D. L. Farrar (CECO) from D. M. Crutchfield (NRC) dated June 23, 1984.
Dear Mr. Denton:
.anclosed is commonwealth Edison Company's document entitled " Final Summary Report of the Human Factors Review for the LaSalle Station Safety Parameter Display System" dated Jurse 26, 1986. We are transmitting.this information to you in response to the requirement contained in Attachment 2 of Reference (a), Itema 1.(a).ii nnd 1.(a).iii. This transmittal covers the human factors review of the SPDS data display and functions and provides -additional verification data supporting the SPDS parametcr selection. Commonwealth Edison initiaaly submitted our SPDS safety analysts and criteria for parameter selection for LaSalle County Station on December 29, 1983 (Reference (b)). Subsequently, the NRC issued a Safety Evaluation Report (Referersce (c)) which found the SPDS parameter selection process and variables acceptable and that the SPDR design should continue to be coordinated with the meergency Procedure cuidelines. Section 6.3 in the . enclosed report Giscusses at length the evaluation of SPDS parameters with This task analysis respect to the DCRDR Task Analysis and Validation Data. survey was based on the control room responses and actions required to y~
- effectively mitigate those emergency syniptoms identified in the GE BNROG EPG's.
l Mr. H. R. Denton June 30, 1986 In summary, the findings of this evaluation confirm that the parameters currently displayed on the SPDS are sufficient to aid the plant operator in accomplishing and maintaining the plant critical safety functions. i'ney also confirm that this SPDS effort has been sufficiently integrated with the other NURBG-0737, Supplement 1 initiatives. We also conclude that human factors engineering principles have been sufficiently addressed in the design and installation of this SPDS. 5ne haman factors deficiencies identified in this review will be resolved yr. a schedule consistent with the integration effort on the other NUERG 0737 Supplement 1 l l initiatives and completion of the SPDS Verification & Validation program. If you have any questions or comments relating to this information, please do not hesitate to contact me. V ery truly yours, c C. M. Allen Nuclear Licensing Administrator im Enclosures cc: Dr. A. Bournia LaSalle Resident Inspector i 1 l i l 1827K I 1 l I a----___-_______ _}}