ML20211M753
| ML20211M753 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 02/18/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20211M758 | List: |
| References | |
| 2728K, NUDOCS 8702270352 | |
| Download: ML20211M753 (310) | |
Text
3 Commonwealth Edison
-' One First National Plaza. Chicago, Illinois
/ Address Reply to: Post Office Box 767 s(/ Chicago, Illinois 60690 - 0767 February 18, 1987 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC.
20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Fire Protection Report - Amendment 9 NRC Docket Nos. 50-454/455 and 50-456/457
Reference:
(a)
August 16, 1982 letter from T.R.
Tramm to H.R. Denton (b)
August 15,' 1986 letter from A.D. Miosi to H.R. Denton (c)
September 10, 1986 letter from A.D. Miosi to H.R. Denton (d)
September 22, 1986 letter from A.D. Miosi to H.R. Denton (e)
November 3, 1986 letter from S.C. Hunsader to H.R. Denton
Dear Mr. Denton:
This letter provides Amendment 9 to the Byron /Braidwood Fire Protection Report (FPR) which was submitted in Reference (a).
This amendment updates the FPR to incorporate new or revised information applicable to the Byron and Braidwood Stations.
These changes do not represent a decrease in the level of fire protection which require prior NRC approval according to the following:
a)
Condition 6 of the Byron Unit 1 Operating License, NPF-37: b)
Condition 3 of the Byron Unit 2 Operating License, NPF-60; or c)
Condition 3 of the Braidwood Unit 1 Operating License, NPF-59.
Many of the changes in this amendment have been previously docketed under separate cover letter.
References (b) through (e) provided this material.
Some of the Amendment 9 changes have been made in response to concerns identified during the pre-license fire protection site audits of both Byron Unit 2 and Braidwood Unit 1.
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Other miscellaneous changes can generally be categorized as either editorial in nature, or as changes to reflect the "as-built" condition of the plants.
Attachment-A to this letter provides an itemized summary and explanation of all changes included in this amendment.
It includes references to the site audits and to previously docketed letters, where appropriate, and is provided as an aid to the NRC in identification of changes.
Please direct any questions regarding this matter to this One signed original and forty (40) _ copies of this-letter, the attachments, and Amendment 9 are provided for your use.
Very truly yours, C.f -_=-!%
S.
C. Hunsader Nuclear Licensing Administrator
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2728K 4
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ATTACHMENT A
-Page No.
Description of Changes-2.1-10a Addition of paragraph explaining why Appendix R emergency lighting was removed from " Protection Criteria and Measures" section of Fire Hazards Analysis.
2.1-13 and 2.1-13a First change added paragraph to allow substitution of existing carpeting due to elimination of Bigelow Grograin II.
Second change added section on foam isolation materials to reflect as-built condition.
2.3-3 Appendix R emergency lighting removal.
See change on page 2-1.10a.
-2.3-5 and 2.3-5a Appendix R emergency lighting removal.
See che.nge on page 2-1.10a.
2.3-11
. Appendix R emergency lighting removal.
See change on page 2-1.10a.
2.3-53 Appendix R emergency lighting removal.
See change on page 2-1.10a.
2.3-55 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-58 and 2.3-58a Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-61 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-64 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-74 and 2.3-74a These changes update the Fire Hazards Analysis to include the Chemical Storage Rooms adjacent to the Auxiliary Boiler Room and were inserted at the request of the NRC.
Refer to CECO to NRC letter of 9/10/86, A. D. Miosi to H. R. Denton; Response to NRC Open Items.
2.3-85 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
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ATTACHMENT A ('ont'd)
C Page No.'
_ Description of Changes 2.3-87 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-101 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-102 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-105 Appendix R emergency lighting ~ removal. See change on Page 2.1-10a.
j 2.3-106 Editorial: Corrected RHR pump 18-to RHR pump 2A.
i 2.3-107 and 2.3-107a This-change updates the' Fire Hazards Analysis to include the upgrading of the fire barriers between the containment spray pumps.
2.3-109 Appendix R emergency lighting removal..See change on Page 2.1-10a.
2.3-110 and 2.3-110a Updates Fire Hazards Analysis to include caulking between removable concrete slabs.
1 2.3-111 Appendix R emergency light:ing removal. See change on Page 2.1-10a..
2.3-113 Appendix R emergency lighting removal. See change on Page 2.1-10a.
I 2.3-118 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-123, 2.3-124, and The first change on page 2.3-123 removes 2.3-124a Appendix R emergency lighting.
See change on page 2.1-10a.
The second change on page 2.3-123 and the change on page 2.3-124 updates the Fire Hazards Analysis to include caulking between removable concrete slabs.
2.3-125 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-128 Appendix R emergency lighting removal.
See change on Page 2.1-10a.
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ATTACHMENT A (Cont'd)
Page No.
Description of Changes
'2.3-130 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-131a Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-135 and 2.3-135a Updates Fire Hazards _ Analysis to include caulking between removable concrete slabs.
2.3-140 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-142 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-144 Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-147a Appendix R emergency lighting removal. See change on Page 2.1-10a.
2.3-148 Appendix R emerger.cy lighting removal. See change on Page 2.1-10a.
2.3-176 and 2.3-176a Appendix R emergency lighting removal.
See change on Page 2.1-10a.
2.3-199 Appendix R emergency lighting removal. See change on Page 2.1-10a.
+
2.3-200a Appendix R emergency lighting removal.
See change on Page 2.1-10a.
\\
2.3-217 Number of manual hose stations increased l
from 4 to 8.
t F2.3-15 The
'W' line wall between the containment spray pumps has been upgraded to a 2-hour fire barrier and has Label 8 doors installed.
2.4-9 (BY-2)
Added section detailing existing cabling in the Unit 2 Electrical Cable Tunnel to reflect as-built conditions.
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ATTACHMENT A (Cont'd)
Page No.
Description of Changes 2.4-21(BY-2)
Both changes made to. reflect as-built condition of plant on RHR heat exchanger outlet temperature transmitter cable location and to be consistent.with Table 2.4-2(BY-2).
2.4-36(BY-2),
Identification and Analysis of High-Low 2.4-46 (BY-2), and Pressure Interface. Refer.to CECO to NRC 2.4-46a(BY-2) letter of 11/3/86, S. C. Hunsader to H.-R.
Denton; Review of the Reactor Vent Valves for Spurious Operation.
2.4-41(BY-2)
Changed solenoid valve to air operated to reflect as-built condition of plant.
2.4-59 (BY-2)
Changed to reflect as-built condition. -See change on Page 2.4-21 (BY-2).
2.4-63 (BY-2)
Tables revised due to High-Low Pressure 2.4-64-(BY-2)
Interface Analysis. -Refer to CECO letter 2.4-70 (BY-2) to NRC of 11/3/86, S. C. Hunsader to.
2.4-139 (BY-2)
H. R. Denton; Review of the Reactor Vent 2.4-147 (BY-2 Valves for Spurious Operation.- Some changes 2.4-148 (BY-2 reflect as-built condition of plant.
-2.4-149 (BY_-2 2.4-175 BY-2 22.4-177 BY-2) 2.4-178 BY-2) 2.4-184 BY-2
-2.4-216 BY-2 2.4-222 BY-2 2.4-223 BY-2 2.4-9(BR-1)and2.4-9a(BR-1)
Added section detailing existing cabling in the Unit 1 Electrical-Cable Tunnel to reflect as-built conditions.
2.4-21(BR-1)
Both changes made to reflect as-built condition of plant on RHR heat exchanger outlet temperature transmitter cable location and to be consistent with Table 2.4-2 (BR-1).
2.4-23 (BR-1) and 2.4-23a (BR-1) Section added regarding cable wrap to reflect as-built condition of plant.
2.4-31(BR-1)
Added information regarding manual operation of valves in the Unit 1 VCT room. Added per NRC, comitment.
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n ATTACHMENT A (Cont'd)
Page No.
Description of Changes 2.4-35 (BR-1)
Identification and Analysis of High-Low Pressure Interface. Refer to CECO to NRC letter of 9/22/86, A. D. Miosi to H. R.
Denton; Fire Protection Audit Resolution of Issues.
2.4-39(BR-1)
Editorial: Corrected 1RM87028 to 1RH87028.
2.4-40(BR-1)
Changed solenoid valve to air operated to reflect as-built condition of plant.
2.4-44(BR-1),2.4-44a(BR-1),
High-Low Pressure Interface. See and2.4-44b(BR-1) description for Page 2.4-35 (BR-1).
2.4-57 (BR-1)
Changed to reflect as-built condition.
See description for Page 2.4-21 (BR-1).
2.4-61(BR-1),2.4-62(BR-1),
Tables revised due to High-Low Pressure 2.4-65 (BR-1), 2.4-139 (BR-1),
Interface Analysis and to reflect as-built 2.4-173 (BR-1), 2.4-174 (BR-1),
conditions. Refer to CECO to NRC letter of 2.4-200 (BR-1), 2.4-202 BR-1),
9/22/86, A. D. Miosi to H. R. Denton; Fire 2.4-203 (BR-1), 2.4-207 BR-1),
Protection Audit Resolution of Issues.
2.4-210 BR-1),2.4-212 BR-1),
2.4-216 BR-1),and 2.4-217 BR-1) 3.1-1(BY)
Deleted reference to BAP 1100-1.
3.1-2(BY)
Deleted reference to BAP's 200.42-3.1 and 1100-1.
3.1-5(BY)
Generalized reference to BAP's.
3.1-6(BY)
Generalized reference to BAP's.
3.1-7 (BY)
Generalized reference to BAP's and editorial changes. Changed reliability related to regulatory related.
3.1-8 (BY)
Deleted reference to BAP.
3.1-9 (BY)
Deleted reference to BAP.
3.1-13 (BY)
Generalized reference to Administrative Procedures.
3.2-2(BY)
Generalized reference to Administrative Procedures.
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r ATTACHMENT A (Cont'd)
Page No.
Description of Changes 3.3-6 (BY)
Generalized reference to Central File at Byron Station.
3.5-3 (BY)
Deleted reference to BOS 7.ll.2b-1.
3.5-13 (BY)
Deleted reference to 80P FP-27.
3.6-6 (BY)
Deleted reference to BMP's.
3.6-7 (BY)
Changes Halon concentration in upper cable room from over 7% to over 6%.
3.7-3 (BY)
Generalized reference to Administrative Procedures.
3.7-4 (BY)
Deleted OPM0lJ from list containing ceiling detector alarm.
3.7-6 (BY)
Halon and C02 systems installed at Byron now meet NFPA Code 12A.
3.7-8 (BY)
Generalized reference to Byron Abnormal Operating Procedures.
3.8-1 (BY)
Generalized reference to Administrative Procedures.
3.1-8 (BR)
Added information on fire brigade members capabilities.
3.7-6 (BR)
Changed reference from water to hose stations for cable spreading room use.
3-49 (BY-2), 3-50 (BY-2),
Updating report to include NFPA code and3-51(BY-2) deviations for Byron 2.
Cover Sheet and Pages 3-1 Updating report to include NFPA code through 3-47 (BR-1) deviation for Braidwood 1 AS.4-31 (BR-1) and Changes made to valve sizes as a result AS.4-32 (BR-1) of M&M coments to reflect as-built conditions.
FM-52 (BY & BR)
Update report to provide current P&ID's.
FM-58 (BY & BR) 6
ATTACHMENT A (Cont'd)
Page No.
Description of Changes A5.7-1 through A5.7-29 Revised Appendix AS.7 to include Braidwood. Refer.to CECO to NRC letter of 8/15/86, A. D. Miosi to H. R. Denton; Appendix R Conformance.
A5.8.7-1(BY-2)
Update deviation to include caulking of hatch cover.
A5.8.8-1 (BY-2) and Update deviation to reflect upgrading of A5.8.8-2(BY-2)
'W' line wall fire barrier between RHR pumps.
AS.8.15-1 (BY-2)
Update deviation to take credit for partial height walls between CC pumps per NRC request.
AS.8.30-1 (BY-2),
Update deviation to reflect design change to A5.8.30-2 (BR-2), and increase horizontal separation between FA5.8.30-1(BY-2) cables in response to NRC audit item.
A5.8.7-1(BR-1)
Update deviation to include caulking of hatch cover.
AS.8.B-1 (BR-1) and Update deviation to reflect upgrading of A5.8.8-2 (BR-1)
'W' line wall fire barrier between RHR pumps.
AS.8.15-1 (BR-1)
Update deviation to take credit for partial height walls between CC pumps per NRC request.
AS.8.16-1 (BR-1)
Clarification of reason for providing remote start switch.
A5.8.30-1 (BR-1),
Update deviation to reflect design change AS.8.30-2 (BR-1), and to increase horizontal separation between FA5.8.30-1 (BR-1) cables in response to NRC audit item.
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