ML20024D054
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7 Address Reply to: Post Office Box 767
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,/ Chicago, Illinois 60690 July 25, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 & 2 FSAR Amendment 63 NRC Docket Nos. 50-373 and 50-374
Dear Mr. Denton:
The purpose of this letter is to provide you with Amendment No.
63 to the LaSalle County Station Final Safety Analysis Report.
This FSAR Amendment does the following:
1.
Provides updated C&I drawings for Unit 1 and an original C&I drawing set for Unit 2.
2.
Responds to NRC telecons for information on high energy line breaks (HELB) and their comparison to criteria issued after the original HELB evaluation; and incorporates fracture toughness data for the Unit 2 vessel to complete the record.
3.
Updates seismic / dynamic qualification data for reactor hardware to the final new loads results and fuel lift results from GE.
4.
Adds the description for the CRD charging water low pressure scram and for the ADS logic change.
Both were NRC imposed changes.
5.
Updates configurations to as built conditions, refines set points and scales, capacities and response times per results of pre-operational and start-up tests.
Brings the record into conformance to test results.
6.
Clarifles the table of containment penetrations, SGTS filter, m
cho post-accident monitors, HVAC, rad chem technicians, analytical R$'
RPV water levels used in safety analyses, QA references, Unit 2 structural response acceptance test results, etc. for accuracy en followinc inquiries from NRC on these points since OL was o-granted.
00 7.
Updates the Fire Hazards Analysis to incorporate NRC recommended field changes or test results following issuance of the OL.
8.
Improves the quality of the FSAR text by corrections, minor editorial improvements.
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H. R. Denton July 25, 1983 A table of contents by page number is attached to aid the recipient in identifying the particular page and its reason for inclusion in this Amendment.
Bulk-wise the major content is typographical corrections and editorial improvements to improve FSAR quality.
These changes had been saved up purposefully for a late amendment.
Enclosure of the seismic / dynamic update for Unit 2 is the next largest change.
Thirdly, updates to NRC telephonic and written requests for information and the update following pre-operational testing comprise almost all the remaining submittal.
-To the best of my knowledge and belief the statements contained herein and in the attachments are true and correct.
In.some respects these statements are not based on my personal knowledge but upon_infor-mation 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.
Enclosed for your use are three (3) signed originals and sixty (60) copies of this letter and the enclosures.
If there are any questions regarding this matter, please contact this office.
Very truly yours,
,hsls3 C. W. Schroeder Nuclear Licensing Administrator lm Attachment cc:
NRC Resident Inspector 1/0 SUBSCRIBED AND SWORN to before me.this 46+L day of O</a/
, 1983.
l5 Li Y Notary Public 7024N
LSCS - FSAR AMENDMENT 63 CONTAINS Page 1.2-16,17 Editorial corrections 1.7-1 thru 93 Updated list of EC&I drawings including Unit 2 2.4-6a,7,12 Typographical corrections 2.5-91 Typographical correction 3.1-7,27,42,49 Editorial and typographical corrections 3.2-16b,24a Classification of El. Penetration Pressurization System 3.5-1 Typographical corrections 3.6-2,4,8a,9,ll,17,19 Break criteria, stresses, break & restraint 25,30,32,33,34,35, locations revisions and typographical -
36,37 editorial corrections 3.7-16,17,30 Typographical and editorial corrections 3.8-15 Unit 2 containment structural acceptance test 3.8-30,31,48,61, Typographical and editorial corrections 69,70,71,72 3.9-1 Clarification for code service levels A,B,C,0 3,9-2,5b,7,10,ll,12 Update of seismic qualification (mechanical 13,18,19,20,21,23 systems and components) and typographical -
23,25,26,27,28,29 editorial corrections 30,31,32,33,34a, 36,27,42,44,45,46, 47,50,52,53,57,58, 59,60,61,62,64,65, 68,76,77,78,79,80, 141,2,83,120,121,145,187,190,191, 81 8 l
193,204 l
l 4.6-8,9,26,31 Low pressure charging water scram 5.2-7,8,8a,9, ADS safety / relief valve activation and 10,10a,19,23,23a typographical corrections.
Also RTNDT 23c,24,40,64,65 values and code case interpretation revisions 5.4-20 Typographical corrections 6.1-3 Editorial corrections
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6.2-2,13,30d,39 Editorial corrections 55,58a,60a 6.2-86,87,88,89 Containment penetrations (Table 6.2-21) 90,91,92,93 revisions
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LSCS - FSAR Page 2 6.3-20,24,37,38 Typographical corrections 6.3-41,58 6.5-6,11,12 SGTS filter clarifications 6.A-5,7,8,9,13 Typographical corrections 7.2-7,8,10 Isolation value setpoints 7,2-17,18,41,47, CRD low pressure charging water and 65,84,86,92,93,28 typographical corrections 7.3-10a,28,52b,53 Typograpical and editorial corrections 65,82 7.3-128 Switchgear temp. controller setpoint 7.4-11 Standby liquid storage tank high/ low setpoint 7.5-4,7,7a Postaccident monitoring and editorial corrections 7.6-2,7,17 Typographical corrections 7.7-3 Correct page mistake in Amendment 62 7.7-18,51,98 Low pressure charging water and typographical corrections 8.1-2,6,6a Unit 2 update and typographical corrections 8.3-7,9a,lla,26, Unit 2 update and typographical corrections 27,30,36,56,57 9.1-13 Typographical corrections 9.2-18 As built UHS capacity 9.2-20,22 Cycled condensate reserve capacity for HPCS, RCIC 9.3.7 Typographical correction 9.4-5,28,32,37,48, Control room HVAC and other HVAC update 49,62,64,76,80, 81,91,95,115,116,117 9.5.14h Rad-Chem personnel-fire brigade 12.1-6 Editorial and typographical corrections-12.2-3,5,6,7,28 clarifications
-12.3-1,7,10,16,17, 25,27 12.5-4 13.1-13,13a Health physics technician site presence and rad / chem qualifications 14.2-11,27,28,29,58a, Startup test updates - clarifications 115, 132,135,136,137 243,243a,270, 235,237a, 238
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LSCS - FSAR Page 3 15.0-la,3,7,8,15 Vessel level analytical / actual setpoints and typographical corrections 15.1-1,9,10,20 Typographical correctins 15.2-1,4,5,19,19a 21,43,46,47,48,50 15.3-3,4,16,19,20 15.4-4,5,42,50 15.6-2,21,30 15.7-25,26,27 17.0-1,2,2a Topical report CE-1-A update information 8.1-117a Update on Reg. Guide 1.97 positions w
C-3,4,5 Postulated pipe rupture break revision E.4-1 Structural steel bolted connections update H.3-61,98,104,105 Fire hazard analysis update 119,120,159,161 163,186,188 L.23-5 SRV setpoint verification device installation L.24-2,3 SRV setpoint verification device installation L.62-16 Typographical corrections Q10.56-5 Editorial correction Q10.74-1,2,3,4,5 Response to new question on fire protection Q31.ll5-1 Editorial Q31.132-1 Editorial Q31.193-1 Response time testing update Q31.261-1 Editurial Q31.285-4 Unit 2 update Q31.286-1 Unit 2 update Q40.84-1 Unit 2 update Q40.106-1 Unit 2 update Q40.106-2 Unit 2 update Qlll.1-1 Break location criteria revision Q111.2-1 Break location criteria revision Q111.44-1,2 Break location criteria revision Qll1.3-1 Break location criteria revision Q122.2-3,4 Beltline plate material - Unit 2 Q212.48-1 Unit 2 update Q212.78-2 Gamma detector range Q212.103-1 Unit 2 update Q331.10-1 Typographical corrections Q331.31-1 Typographical corrections Q510.1-1 Editorial corrections I
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