ML20078B927
| ML20078B927 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 09/23/1983 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20078B929 | List: |
| References | |
| 7349N, NUDOCS 8309270326 | |
| Download: ML20078B927 (12) | |
Text
N Commonwrith Edison s
C ) one First National Plaza Chicago, flhnois i
C Address Reply to: Post Othee Box 767 Chicago, liiinois 60690 September 23, 1983 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 G
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 FSAR Amendment 43 NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457
Dear Mr. Denton:
The application for construction permits and operating licenses for Byron Generating Station Units 1 and 2 and Braidwood Generating Station Units 1 and 2, docketed September 20, 1983, are hereby amended by submittal of Amendment 43 pursuant to 10 CFR 50.34.
Amendment 43 to the Byron /Braidwood FSAR consists of new responses to questions from the Materials Engineering Branch (121.0 series) the Structural Engineering Branch (130.0 series), the Reactor Systems Branch (212.0 series), the Equipment Qualification Branch (271.0 series), and the Siting Analysis Branch (330.0 series).
Also included are revised responses to Questions 010.19, 010.47, 010.57 010.59,1,022.16, 022.24, 022.30, 040.188, 110.18, 241.3(Br), 241.8(Br), 251.2, 270.
270.5, 270.8, 281.7, 362.l(Br), and 423.40, and voluntary text changes.
Attachment A to this letter is an itemized summary of changes contained in the amendment.
This summary is provided at the request of the NRC Staf f as an aid to the identification of FSAR changes requiring further evaluation by the NRC.
Three signed originals and fif ty-seven copies of this amendment are submitted for NRC use.
Please direct questions regarding these matters to this office.
Very truly yours, T(C/w T.
R.
Tramm Nuclear Licensing Administrator 1m SUBSCRIBED and SWORN to beforp me this JJn (day 00 of sdhh 1983 (0
/
Notary Public 8309270326 830923 PDR ADOCK 05000454 7349N K
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ATTACHMENT A
SUMMARY
OF CHANGES CONTAINED IN B/B-FSAR AMENDMENT 43
- Page, Figure, or Table Number Description of Change 1.1-2 Revised fuel load dates for Byron 1&2 2.2-5,5a (Byron)
Subsection 2.2.3.1.3 revised per NRC request relating to deletion of chlorine detectors 2.3-23a (Byron)
Revision to description of meteorological instrumentation F2.5-89,90 (Byron)
Editorial T2.5-24 (Byron)
Editorial 2.1-1 (Braidwood)
Change reflects current cooling pond surface area 2.1-8,23,28,32 Revised population data (Braidwood)
F2.1-2,6,8 (Braidwood)
Revised site boundaries 2.2-1,la,2,8a (Braidwood)
Revised per response to 0330.4 2.3-25a (Braidwood)
Revision to description of meteorological instrumentation 2.4-1,11,17 Revised cooling pond surface area 2.5-91 (Braidwood) 3.1-25,26 Editorial 3.2-4 Spent fuel pool liner declassified to Category
.'I (See also p.9.1-14, p.B.7-1) l 3.2-6 Changes reflect current design; (Shell side of seal water HX Quality Group C; Amendment 42 change was incorrect) 3.2-8,10 Changes per response to Q270.1 (p. 0270.1-5) _. _
ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 3.5-1 Editorial F3.6-48 through CV and SD breaks and restraint locations F3.6-78 0212.112 3.7-8,9,11 Editorial 3.7-20 Delineates responsibility for design of various piping systems 3.7-25 Description of WESTDYN added to Appendix D 3.7-30,31 Reflects current design of seismic instrumentation 3.8-25,28 Editorial 3.8-31a,34a Description of Braidwood ESWDS added per response to Q130.57 3.8-31 through Byron and Braidwood unique information 3.8-34e now printed on colored pages 3.8-37a Editorial 3.8-49,50 AISI. reference added 3.9-10,57,75,78,84,97 Editorial 3.9-108 Corrections per piping and instrumentation diagrams (active valves) l 3.10-6 AISI spec. edition date removed l
3.11-2 Editorial 3.11-3 Revised per response to 0270.5 (Equip.
[
Qual.)
3.11-4,6 Editorial -
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ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 4.1-2, 4.2-25 Editorial 4.3-9,10 Editorial 4.4-13,25 Editorial 5.4-49 Editorial 6.1-3 Editorial 6.2-2,9 Editorial 6.2-29,32 Name of RCFC backdraft dampers changed to RCFC check dampers 6.2-53 Editorial 6.2-161,162,163 Revised data per large break LOCA reanalysis 6.2-164 Revised containment spray and fan cooler start times (see Q22.24) 6.2-172 Table revised to reflect conformance of CCW line to general design criteria; FP valves are globe valves 6.2-173 Line size for lIA088 is 1/2-inch; 1MS101D and 1MS101B have 10 second closure times 6.2-174 1MS101A and C have 10 second closure times 6.2-175 Line size for 1PS231A and B is 3/4-inch 6.2-175a Closure times for 1RH8701A,B, 8702A,B are N/A; closure time for 1SI8880 is 10 sec.; closure times for 1SI8809A and B are 15 sec.; opening times for 1SI8811A and B are 90 sec.; ISI8812A and B deleted from table since they are not containment isolation valves 4
ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 6.2-175b Closure time for 1SI8840 is N/A; closure times for 1SI8825 and 1SI8843 are 10 sec.
F6.2-24 Revised per large break LOCA reanalysis F6.2-25 Curve revised using 45 F cooling water temperature (see Q22.24)
F6.2-26,27 Revised per large break LOCA reanalysis 6.3-35 Revised closure times for valves SI8809A and B 6.3-46a,46b Revision to cold leg-to-hot leg recircu-lation switchover steps F6.3-2; Valve alignment Revised to reflect current operational chart pages 2 and 3 modes F6.4-3 Control room has one foot minimum floor thickness 6.5-4,10 Changes reflect current design 6.5-12,15 Ed'*orial 6.5-16
- 1) Editorial, 2) Change reflects current design 6.5-21, 7.1-19,31 Editorial 7.2-7 Opening of any RCP breaker above P-8 will not trip reactor; (this was noted in Byron SER) 7.3-6,7,8,14,16 Changes reflect current design 7.3-17 Editorial 7.3-18,23,24 Changes reflect current design.
ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 7.3-30 Editorial 7.3-35,36 Changes reflect current design F7.3-3,4,5 Figures updated to reflect current design 7.6-1 Pressure setpoints revised to reflect current design and RHR valves identified 7.6-3 Added reference to F7.6-5 8.1-16 Added references 15 and 16 9.1-3 Changes reflect current design (new fuel storage rack construction) 9.1-7,7a Changes reflect current design (. fuel handling) 9.1-14,14a Spent fuel pool liner declassified to Category II (see also T3.2-1 and
- p. B.7-1) 9.1-17,20,21,22,23,24 Changes reflect current design (spent fuel pool cleanup) 9.1-26 Editorial i
I Changes reflect current design (fuel 9.1-28,28a,29 handling and storage) 9.1-32 Editorial 9.1-33,34 Changes reflect' current design (fuel handling and storage) 9.1-46 Changes reflect current design 9.2-34,35,36 Revised Braidwood ultimate heat sink analysis l
I
ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 9.2-40,47 Changes reflect current design 9.2-52 New reference for UHS analysis 9.2-53,54 Changes reflect current design for ESW heat loads 9.2-64,65,66 Changes reflect current design 9.4-1,2,29 Changes reflect current design 9.'
'l Editorial 9.4-44 RCFC backdraft dampers changed to RCFC check dampers 10.3-2,2b,2c "A" and "B"
trains changed to " Active" and " Standby" trains 10.4-2 Editorial 10.4-20,21,22 Changes reflect current design 11.2-5,10,13 Editorial 11.2-22,24; 11.3-25, Changes reflect current station cooling 27 (Braidwood) pond blowdown value of 43.2 cfs, new site survey data, and revised population and food production estimates 11.2-23 (Byron)
Editorial 11.3-8 Changes reflect current design (See Tll. 3-10 also) 11.3-12 Editorial 11.3-28 New Table 11.3-10 (See also p. 11.3-8) 12.2-4 Editorial 12.2-6 Changes reflect current design 12.2-6a Editorial -
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ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 12.2-11 Editorial 12.3-7 12.3-10 Change reflects current design (routing of radioactive piping) 12.3-13,23 Editorial 12.3-27
- 1) Editorial; 2) Change reflects current design (shielding) 12.3-29 Editorial i
F13.1-1 Figure revised to show current project organization 13A-25a,b,c,d Expanded resume of Braidwood Station Health Physicist (per NRC request) 14.2-17 Change reflects current test procedures (seismic instrumentation) 14.2-27 Change reflects current test procedure (Byron) 14.2-27a Braidwood ESW preop test to be discussed later 14.2-31 Change reflects current test procedure 14.2-98 Test objective is to maintain plant in hot standby from outside control room, not hot shutdown 15.0-2 Editorial 15.0-50 Revision per large break LOCA reanalysis 15.2-19; 15.3-10; Editorial 15.4-56; 15.6-11 - - _ _ _
ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change 15.6-16 through Revised per large break LOCA reanalysis 15.6-21 15.6-24 Editorial 15.6-29; 15.6-31 Revised per large break LOCA reanalysis through 15.6-32; 15.6-35,36 15.6-50 Editorial F15-6-7 through Figures revised per large break LOCA F15.6-33 reanalysis 15.7-4,5,7 Editorial 15.B-2 through 15.B-6 Revised per large break LOCA reanalysis A1.27-1 Editorial Al.67-1 Reg. Guide 1.67 was withdrawn A1.75-3,4,5 Editorial Al.ll6-1, AB.8-1 Editorial B.1-16 Editorial B.7-1 Spent fuel pool liner declassified to Category II (See also T3.2-1 and
- p. 9.1-14)
B.7-2 Editorial D.2-1 Editorial D.8-1,2 Description of WESTDYN computer program added to Appendix D D.15-2,3 Editorial ATTACHMENT A (Cont'd) 4 B/B e.
- Page, Figure, or Table Number Description of Change D.22-1,2 Description of COLID computer program added to Appendix D D.23-1,2,3,4 Editorial corrections, references added, and pages renumbered D.T-36 through Tables and figures added for description D.T-44, FD-66, FD-67 of COLID computer program i
E.0-1 Editorial E.17-1 through Description of plant safety parameter E.17-10; FE.17-1 display system added to Appendix E through FE.17-3 E.30-2, E.75-2, E.80-1 Editorial correction E.75-9 Change reflects current design 4
E.30-5,6,7 Description of containment hydrogen monitor added Q10.19-1 Spent fuel pool liner declassified to Category II (see also T3.2-1, p. 9.1-14,
- p. B.7-1) 4 j
Q10.47-5 Editorial Q10.59-1 Editorial Q10.57-1 through Revised response to question on fire protec-j Q10.57-5 tion (FPR has not been Amended, however, l
revised FPR pages were transmitted to NRC in advance)
Q22.16-1 Editorial Q22.24 Revised per large break LOCN reanalysis Q22.30-2 Revised to agree with Table 6.2-58 i
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ATTACHMENT A (Cont'd)
B/B
- Page, Figure, or Table Number Description of Change Q40.188 Revised response to question on fire protection (FPR has not been Amended, however, revised pages were transmitted to NRC in advance) 0110.18-3,4,6,7,8,10, Changes to reflect pump and valve 11,13,14,15,16 preservice inspection program Q110.63-3 Revised snubber test commitment Q121.5, Q121.6 Responses to questions on preservice weld inspections 0130.55 Response to recent Braidwood question on boxcar explosion study 0130.57 Response to recent Braidwood question on essential service water discharge structure 0212.112 New figures provided showing breaks and restraint locations for AF, CV, and SD 0212.160 Response to NRC question on use of PORVs as pressurizer vents, qualification of PORVs to withstand SSE, and use of PORVs following SGTR O241.3-1 Revised response to recent Braidwood question on backfill used for Category I structures Q241.8-2 Revisions to Braidwood question on stability of interior dike Q251.2-1,4,5 Braidwood 1 and 2 fracture toughness data provided 1.
ATTACHMENT A (Cont'd)
B/B o.
- Page, Figure, or Table Number Description of Change Q270.1-5, Editorial (Note:
All Q270 series responses Q270.5-1, apply to both Byron and Braidwood) 0270.8-2,3 Q271.1 Response to question on seismic and dynamic equipment qualification Q281.7-3,3a Description of containment hydrogen monitor added Q330.3 Response to recent Braidwood question on gas pipeline Q330.4 Response to recent Braidwood question on shipments of explosive material 0362.1-2,3,4,5, Revision to recent Braidwood questicn on settlement of Category I structures; new column added to TQ362.1-1 Figures 0362.1-10 Revisions made to indicate stabilized through 0362.1-12; elevations for settlement plots 0362.1-14 through (Braidwood)
Q362.1-18 0423.40-1 Revised per recent NRC concern regarding vortexing at Braidwood lake.- -
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