ML20041G364
| ML20041G364 | |
| Person / Time | |
|---|---|
| Site: | LaSalle |
| Issue date: | 03/12/1982 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20041G365 | List: |
| References | |
| 3626N, NUDOCS 8203220135 | |
| Download: ML20041G364 (3) | |
Text
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Commonwealth Edison
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One First N; tion;l Pliza. Chicigo. Ilknois
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/ Chicago. Ilhnois 60690 A
March 12, 1982 4
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Mr. Harold R.
Denton, Director
{4 Of fice of Nuclear Reactor Regulation p
U.S.
Nuclear Regulatory Commission 14 Washington, DC 20555 f,
4
Subject:
LaSalle County Station Units 1 & 2 Amendment No. 60 to the Final Sa fety Analysis Report (FSAR).
NRC Docket Nos. 50-373 and 50-374
Dear Mr. Denton:
Attached is Amendment No. 60 to the LaSalle County Station Units 1 and 2 Final Safety Analysis Report.
This amendment provides documentary updates for many telephone staf f inquiries made during the drafting o f SER Supplement No.
2.
Examples are:
CSCS Pond surveillance interval Fa tigue evaluation o f Downcomers and SRV discharge piping Head cavity pressurization update Power source to TIP valve Correction to Table 6.2-21 notes for isolation valve leak testing Power source for RCSC Clarification o f ESF bus power loads Update on fire protection including fire door inspection Amplification of training program administration Small LOCA break methodology future evaluation Anticipated transients with failure, applicability for LaSalle MSIV-LCS update.
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H. R. Denton March 12, 1982 This amendment responds to questions on Technical Specifications raised by telephone inquiry to station personnel.
Examples are:
CRD scram time at test conditions Opening time for recirc pump trip motor breaker Isolation valve opening time Update on Suppression Pool temperature.
Additional details are provided on certain topics to clarify subjects where staf f understanding was incomplete or inaccurate.
Examples are:
Drywell surveillance during construction and operations Reformatting o f Class 1, 2 and 3 piping stresses Input signals for control of Reactor Building crane Rejection of incore themocouples for LaSalle Compliance with 10 CFR 50.46 Update of drawings in Se tion 1.7, Parts A and B Motor operated valves and controls.
Additionally, editorial corrections of typographical errors and obvious miswording was made for more accurate test.
Examples are:
Type of valve corrected to as-built situation LPCI actuated devices Fire detection definition more accurately given Preoperational test objective acknowledged on Reactor Building crane CSCS-ECCS preoperational test clarified Word correction in feedwater heater loss Correct RPT response time in accident sequences Restore misplaced footnote to bottom o f page Change legend block on Figure from % to degrees F.
H. R. Denton March 12, 1982 None of these changes are o f safety significance because none af fect the three barriers to radiological release nor does any change involve raciological consequences pertaining to public health and safety.
Aside from the drawing update, this information responds to inquiries by the staff, provides clarifications, and corrects editorial errors.
Responses to Questions 031.288 and 031.289 elaborate the details of prior system safety conclusions represented in Chapter 15 and in the " Justification for Interim Operation" previously provided a part o f the Environmental Qualification Program.
To tne best o f my knowledge and belief the statements contained in the attachment are true and correct.
In some respects these statements are not based or, my personal knowledge but upon information furnished by other Commonwealth Edison employees and consultants.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Three (3) signed originals and fif ty-seven (57) copies o f this transmittal are submitted for your review and approval.
Very truly yours, L. O. DelGeorge Director of Nuclear Licensing 1m Enclosure SUBSCRIBE 0 and SWORN to n'"lC"d1"dn"2 04aBA Nota ry Public 3626N t