ML20107F662
| ML20107F662 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 11/02/1984 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20107F666 | List: |
| References | |
| 9409N, NUDOCS 8411070150 | |
| Download: ML20107F662 (5) | |
Text
,,
7'yCommonwealth Edison
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). One First National Plaza Chicago. Illinois
~ Address Reply to: Post Office Box 767 yN
. Chicago, Illinois 60690 11 November 2, 1984 Mr.' Harold R.~Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Amendment 5 to Fire Protection Report NRC Docket Nos. 50-454/455 &-50-456/457 References (a):. August.16, 1982 letter from T. R. Tramm to H. R. Denton.
(b):
August 20, 1984 letter from T. R. Tramm to H. R. Denton.
(c):
October 11, 1984 letter from T. R. Tramm to H. R. Denton.
Dear Mr. Denton:
This letter provides Amendment 5 to the Byron /Braidwood Fire Protection Report (FPR) which was submitted in reference (a).
References
-(b) and (c) provided advance copies of FPR revisions which are included in this amendment!
Attachment A to this letter provides an itemized summary of the changes included with this amendment.
This attachment is being provided at the request of the NRC Staff as an aid to the identification of FPR changes requiring further evaluation by the Staf f.
One signed original and forty copies of this letter, the ettachment and Amendment 5 are being provided for your use.
Very truly yours, T/2.[W T. R. Tramm Nuclear Licensing Administrator
-lm Attachment p
N 8411070150 841102 9409N PDR ADOCK 05000454 F
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[ ATTACHMENT i A _:
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SUMMARY
JOF CHANGES-CONTAINED IN s
~ B/B'1FPR ' AMENDMENT r 5 s,
x Page : Number's !
Description R214 -A. clarification.regarding;the fuel 3
supply to the, diesel-driven.AFW-pump
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~ day tankais added'to Subsection 2.4.2.30.
-Also,:a clarificationfregarding alternate shutdown capability"following fire
' damage toLboth centrifugal charging pumps lube.oilLpumps is added to Subsection E
2.4.2.~33.
These changes were requested
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by the Auxiliary Systems Branch.-
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- 2J4-23; Tlua change to subsection 2.4.2.33 discussed above continues on this page.
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224-24 Subsection 2.4.2.37 was revised to add a,more. detailed; explanation'regarding
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the effect;on safe. shutdown capability 1.
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of fire damage to the main. steam atmos-i E
.pheric relief valves _and the component.
cooling 1 pumps.
These changes were
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. requested by the: Auxiliary Systems Branch.
~Also, the term " hot shutdown" was re-placed-by.-the term " hot standby""in three places on this page.
Hot standby, as defined *in,the Technical Specifications, 4
is"the' safe " hot shutdown" condition.for Westinghouse PWR's.
4
.2.4-26' Correction of typographical error.
~.2.4427; The' discussion.of isolation of controls andJinstruments between the control
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room and the remote shutdown' panels is revised to correctly state that instru-
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ments are isolated so that a fire in one zone will not affect instruments in the
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other.
Only' controls would'be affected.
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- 2.4-29' The commitment to provide an interim fire watch,in Fire' Zone 11.5-0 is deleted.
Credit is taken for utilizing reactor.
vessel' level instrumentation in place of
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RC hot leg temperature and incore
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thermocouples, and supporting information z,.
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is provided.
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h-Page Numbers Description
- 2'. 4 - 31 The commitment to provide ad interim fire watch in Fire Zone 11.6-0 is deleted.
Credit is taken for utilizing reactor vessel level instrumentation in place of RC hot leg temperature and incore thermocouples, and supporting information is provided.
2.4-33 The refueling water storage tank level instruments are deleted from the safe shutdown analysis.
2,4-53 Non-safety-related switchgear 143 is deleted from the safe shutdown support systems equipment list.
2,4-54 Non-safety-related switchgear 144 Is deleted from the safe shutdown support systems. equipment list.
2.4-55 The component description for equipment number LAP 92E is corrected.
2.4-70 The refueling water storage tank level instruments are deleted from the safe shutdown analysis.
2.4-75, 75a and 76 Table 2.4-6 is updated.
This update was inadvertently omitted from FPR' Amendment 3.
3.7-3 The commitment to include SCBA units inside containment is deleted.
Such units would become contaminated and would nct be usable.
3-5 thru 3-18, 3-20, The status and schedule for resolving 3-22 thru 3-29, NFPA code deviations are revised to 3-31 thru 3-38, 3-40, reflect the current status.
3-42 thru 3-45, 3-47 and 3-48
. Appendix 5.1 The resume of Thomas J. Kramer, fire protection consultant during the prepara-tion of the Fire Hazards Analysis, is deleted.
Resumes of three fire protection engineers currently empolyed by CECO, all of whom have some responsibility for the Byron /Braidwood fire protection program, are added.
This change is made in response to an NRC request.
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'Page Number Description
- A5.2-3 The manual-CO2_ backup capability for.the 1,2<=
lower cable spreading rooms is added to 6" Y a.
-the list of suppression systems provided.
i$k5.4-8 and 9
'The description of the Halon 1301 systems is revised to reflect recent design changes to the system.
.,,, A5.4-11 and.12
-The deEcription of the Cardox CO2 system 4'~
is revised to reflect recent design
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.p.
changes to the system.
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.A5.8.16-1 Correction of typographical error.
lAS.8.lE-1:
CThe " Justification for Deviation" is revised to more clearly explain the need for the modification described.
This clarification is made at the NRC Staff request.
AS.8.2'8-2 At the Staff's request, the " Justification for Deviation" is expanded to include a more detailed explanation.
AS.8.29-1, The term " hot shutdown" is replaced by A5.8.30-1,*
the more technically correct term " hot A5.8.31-1, and standby".
3 AT.'8. 3 2-1 1)-
At the St' f f's request, the " Justification AS.8.33-1 a
for Deviation" is expanded to include a more detailed explanation and to incor-porate a revised commitment for installa-tion of'the modification.
a a
Z;.
A5.8.34-1 and 2 The deviation has been revised to also include the incore thermocouples, and expanded " Description of Deviation" and y
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" Justification for Deviation" sections are provided.
A revised commitment for installation of the modification is also included-at the Staff's request.
A5.8.35-1 Recently identified Deviation A.28 is included in this Appendix.
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B/B AMENDMENT 5 if"'$
OCTOBER 1984
' Instructions:for-Updating 3
Changes;to'the-Byron /Braidwood Fire Protection Report are identified
,:byLthe' amendment number and datel.and by a_ vertical line in the right-imargin offthe page.
.To update your copy of the Byron /Braidwood Fire Protection Report, remove and destroy.the following pages and-figures:and insert-pages and figures as indicated.
. REMOVE INSERT
'I
' VOLUME 2
- Pages 2.4-22 through 2.4 Pages 2.4-22.through 2.4-24 Pages 2.4-26 and 2.4 ~
Pages 2.4-26 and 2.4-27
-Page 2.4-29 Page 2.4-29 LPage 2.4-31 Pagel2.4-31
'Page:2.4-33.
Page 2.4 Pages:2.4-53 through 2.4-55 Pages 2.4-53 through 2.4-55 Page 2.4-70 Page 2.4 Pages)2.4-75 and'2.4-76 Pages 2.4-75,-2.4-75a, and r
2.4-76 f,s A-Chaptier 3.0
-Page 3.7-3 Page 3.7-3 Pages 3-5 through 3-16 Pages 3-5 through 3-16
- Pagesc3-18 through 3-20 Pages 3-18'through 3-20 4 :Pages 3-221through 3-29 Pages 3-22 through 3-29 Pages.3-31 through13-38 Pages 3-31-through 3-38
-Page 3-40_-
.Page'3-40 LPages 3-42 throughE3-45 Pages 3-42'through 3-45 Pages 3-47 and 3-48' Pages 3-47 and 3-48
' Chapter 5.0
. Title sheet for-Appendix 5.1 Title sheet for Appendix 5.l~
and Page AS.1-1 and Pages AS.1-1 through AS.1-4 Page AS.2-3 Page A5.2-3 JPages A5.4-8'and A5.4-9.
Pages AS.4-8 and A5.4-9 Pages A5.4-ll'and'A5.4-12 Pages A5.4-11 and AS.4-12
.Page A5.8.16-1 Page A5.8.16-1 Page A5.8.18-1 Page AS.8.18-1
.Page-A5.8.28-2 Page AS.8.28-2 Page A5.8.29-1 Page AS.8.29-1 i
PageLA5.8.30 Page AS.8.30-1 Page AS.8.31-1.
Page A5.8.31-1 iy['_]/.
LPage A5.8.32-1 Pags A5.8.32-1 Page A5.8.33-1 Page A5.8.33-1
- Page A5.8.34-1 Pages A5.8.34-1 and A5.8.34-2 and A5.8.35-1
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