ML20028G647

Forwards Amend 62 to FSAR

ML20028G647
Person / Time
Site:	LaSalle
Issue date:	02/04/1983
From:	Schroeder C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20028G648	List: ML20028G647
References
5874N, NUDOCS 8302170187
Download: ML20028G647 (4)

Text

Commonwealth Edison

{ N) v one First Nationsi Plaza. C_hicago, Illinois Addrzss Reply to: Post Offica Box 767 Chicago. Illinois 60690 February 4, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 4

Subject:

LaSalle County Station Units 1 and 2 Amendment No. 62 to the Final Safety Analysis Report (FSAR)

NRC-Docket Nos.'50-373-and-50-374-

Dear Mr. Denton:

This purpose of this letter is to provide you with Amend-ment No. 62 to the LaSalle County Station. This is an informational

, submittal for the following purposes:

a) Respond to station-identification error's in text and correct any typographical errors found, b) Incorporate the results of pre-operational test results into the text to brin systems performance;this g theincludes FSAR into consistencyof incorporation with plant previously approved Tech Spec. changes.

c) Clarify certain topics for regional inspectors where repetitive questions were asked.

d) Incorporate formal responses to NRC questions previously answered in earlier informational letters. (September and October 1982) e) Provide Unit 2 specific information to provide coverage for that unit where not identical with Unit 1.

None of these topics contains unreviewed safety items beyond those already reviewed and approved in the Safety Evaluation Reports for Unit 1. The attached summary sheet identifies each topic and the reason for updating the FSAR.

To the best of my knowledge and belief the statements con-tained herein and in the attachment and enclosures are true and correct. In some respects these statements are not based upon my personal knowledge but upon information furnished by other Commonwealth Edison employees. Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

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8302170187 830204 PDR ADOCK 050003 K

H. R. Denton February 4, 1983 Three (3) signed original and sixty (60) copies of this

, transmittal are submitted for your use.

If there are any questions in this matter, please contact this office.

Very truly yours, kN 2/Lplb3 C. W. Schroeder Nuclear Licensing Administrator 4 1m Attachment Enclosure cc: NRC Resident Inspector SUBSCRIBED AND SWORN to i before me this C/ d day o f M/h s , 1983 0h4au,$EA_r/f.: b Notary Public 5874N

Attachment,-Amendment 62 Transmital Letter PAGE ITEM REASON FOR UPDATE I

6.2-20 Operational recovery method 1) Clarify feed and bleed recovery for RW steam condensing mode operation in steam condensing mode per R III request.

6.2-62 Drywell net free volume 2) Typographical error corrected.

6.3-40, 40s, LPCS/LPCI injection valve 3) Design change required by NRC in SSER #2 43, 43a, 53, interlock Section 6.3.4 prior to fuel load of 54, 55, 57 Unit 2; CECO Design accepted.

6.5-1, 2, 7 SGTS pressure reduction 4) Incorporate pre-operational test results 8, 14, 19, 21 time internal into FSAR end 7.1-32 7.7-114 Table 7.7-7 cleanup 5) Typographical errors corrected 7.3-12, 13, LPCS/LPCI injection valve 6) See 3 above 16, 17, 18 interlock 7.3-49, 50 SGTS pressure reduction time 7) See 4 above-interval l 7.3-62, 70, LPCS/LPCI injection valve 8) See 3 above 114, 122, 123 124 7.7-53, 54 TIP subsystem figure and with 9) Typographical error corrected draw speed 8.2-1 Braidwood transmission line 10) Update transmission line data to as updated built condition 8.3-43, 44 416V ESF bus loads 11) To designate manual reset upon restoration of bus voltage, for clarity 8.3-55 250V battery load re- 12) Incorporates pre-operational test quirements results into FSAR 9.4-37, 38 R m service water pump 13) Clarify responses to regional inspectors cubicle fan - temperature questions to eliminate repetition.

14.2-132 Recirc flows test procedure 14) Clarify pre-operational test procedure for consistency with controller design.

15.0-15 RPT delay time 15) Incorporate pre-operational test results G.5.1-2 for consistency G.3.3-9, 10 H.4-1-245 Update fire hazard analysis 16) Provide Unit 2 information on safe for Unit 2 shutdown and Fire Hazard Analysis.

Y-.- . . - - _ - . - - - - _ .

, - . . . , . . , . . . . =,....,..>....:.n u w a.:.uu u z.u:w w w n w ~.=- w ..w. a a;.....:..--u PAGE ITEM REASON FOR UPDATE J.2-1; 3-1 Spray shield 17) Provide Unit 2 information on MELB end 5-1 fixes.

L.62-16-52 ADS logic modification 18) Incorporate prior informational submittal into formal FSAR report.

(See M.A CWS82-255)

Q 10.23-1; SGTS pressure reduction time 19) See 4 above 30.1 interval Q 21.24-3; SGTS pressure reduction time 20) See 4 above 43-1, and 68-2 interval Q 31.288-36 MCPR limit 21) Typographical error corrected Q 31.290-1-4 Control system failures 22) Provide re'sponses to NRC questions Q 31.291-1 previously answered via informational Q 31.292-1 letter. (See NCA CWS82-259)

Q 31.293-1 Q 31.294-1 Q 31.295-1 .

Q 040.74-1 SGTS pressure reduction time 23) See 4 above Q 111.39-1-59 Snubber list removed 24) Remove snubber list from FSAR because already in Tech. Specs.

Q 312.12-1; SGTS pressure reduction time 25) See 4 above 13-1; and 16-1 interval l

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