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| issue date = 10/03/1985 | | issue date = 10/03/1985 | ||
| title = Suppls Util 850904 Ltr Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl | | title = Suppls Util 850904 Ltr Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl | ||
| author name = | | author name = Keiser H | ||
| author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | ||
| addressee name = | | addressee name = Butler W | ||
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000387, 05000388 | | docket = 05000387, 05000388 | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:'REGULATOR INFORMATION DISTRIBUTION | {{#Wiki_filter:' | ||
Pennsylvania | REGULATOR INFORMATION DISTRIBUTION S STEM (RIDS) | ||
ACCESSION'BR o 8510.080410, OOC DATE! 65/10/03 NOTARIZED; NO cocKET e FACIL:50 387 Susquehanna Steam | |||
~ | |||
Electric Stationi Unit ii Pennsylva 05000387 50 386 Susquehanna BYNAME Steam Electric Stationi Unit 2'< Pennsylva 05000388 AUTH AUTHOR AFFILIATION KEISER<H,W. Pennsylvania Power 8'ight Co ~ | |||
RECIP ~ NAMKl RECIPIENT AFFILXATION BUTLERgW ~ Ri Licensing Branch 2 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Suppls uti] 650904 .ltr re resolution of fire~ protection concerns. Listed replacement pages- re sprinkler protection for control structure elevation 8 shutdown paths SIZE; encl'ISTRIBUTI N CODE: A0060 COPIES RECEIVED:L~TR. ENCL TITI E: OR Submittal: Fire Prote'ction NOTES: 1cy NMSS/FCAF/PM'PDR 2cys 05000387 07/17/62 Transcripts'L: | |||
icy NMSS/FCAF/PM'PDR 2cys Transcripts; 05000386 OLe03/23/84 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR LB2 BC 01 3 3 INTERNAL: ACRS 11 3 3 ADM/LFMB 0 ELD/HDS4 0 IE NHITNEYIL 1 1 NRR STANGrJ 07 2.' NRR ÃERMEILiJ06 1 0 NRR/DE/CEB 09'4 2 2 NRR/DL DIR 1 1 1 1 RGN1 1 1 EXTERNAL: 24X LPDR 03 NRC PDR 02" NSIC 05 1 1 NOTES: | |||
TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 22 | |||
Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/770.5151 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 OCT O3 1985 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION RESOLUTION OF FIRE PROTECTION CONCERNS ER 100450 FILE 841-2, 143 Docket Nos. 50-387 PLA-2541 50-388 | |||
== | ==Dear Dr. Butler:== | ||
This letter supplements PLA-2529, dated September 4, 1985. Enclosed are replacement pages as follows: | |||
3 | ~Pa e Descri tion of Chan e Page 3 of Concern 81 Revise Section 2.2 to clarify use of non-rated boundaries Page 2 of Request /f6 in Sprinkler protection for the Appendix A to Concern //1 Control Structure Elevation 754'-0" support steel is partial protection Figure 6 of Appendix B to Shutdown paths 3 6 4 were Concern 81 added to zone 1-6C Figure 9 of Appendix B to Shutdown paths 3 6 4 were Concern Pl added to zone 1-6C Figure 10 of Appendix B to Shutdown paths 3 & 4 were Concern 81 added to zone 1-6C Figure 11 of Appendix B to Added the amount of combustible Concern lI1 loading for zone 1-5C I | ||
" 851 0P FtaR ".OA80<>0 ADOCg "8Seoo3 (OO4 OSOOO3 . | |||
~ | ( l I DR | ||
Yes | |||
Page 2 SSES PLA-2541 Qg 08 1985 ER 100450 File 841-2, 143 Dr. W. R. Butler | |||
~Pa e Descri tion of Chan e Page 3 to Attachment 2 of Added notes to page regarding Appendix B to Concern //1 the control structure The above changes are editorial clarifications which do not affect the conclusions of the analysis. | |||
Should you have any questions please contact us. | |||
Very truly yours, H. W. Keiser Vice President-Nuclear Operations cc: M. J. Campagnone NRC R. H. Jacobs NRC | |||
iii) Identifying on a case by components which are not case the rated and specific barrier providing a justification for their use. | |||
/~ | Any additional fire rated protection required as a result of this redefinition will be in accordance with 10CFR50 Appendix R, Section III.G. | ||
~ | 2.2 Other Safety Related Buildings The methodology used in the Control Structure, the Diesel Generator buildings and the ESSW pumphouse was somewhat different since the majority of the fire zone boundaries are fire rated and, as a result, our fire zone boundaries are equivalent to fire area boundaries. For these buildings each fire zone was reviewed for its safe shutdown division. Fire zones having a common safe shutdown division were grouped into fire areas. Each fire area was reviewed to assure that all of its boundaries were fire rated construction, or if a non-rated boundary was acceptable. | ||
3.0 ASSUMPTIONS & NRC GUIDANCE 3.1 The analysis was performed in accordance with the following NRC guidance: | |||
: a. 10 CFR 50, Appendix R Section III.G. | |||
: b. Generic Lett'ers 83-33 and 85-01. | |||
I c~ NRC letter to PP&L dated April 18, 1985 which states: | |||
"The reassessment of non-rated construction should be in accordance with guidance presented at the site audit. That is, to provide reasonable assurance that fire propagation will not occur beyond non-fire-rated zone boundaries, the boundaries should be upgraded, to be continuous barriers with a fire rating sufficient to withstand the effects of a fire involving in-situ and transient combustibles, with conservative margin. If boundary construction is not upgraded, your reassessment should assume that fire spread will occur into the next most immediate fire zone (horizontally and/or vertically)." | |||
3.2 The analysis performed was based on the following assumptions: | |||
aO The concrete block or reinforced concrete used in the construction of walls, floors and ceilings are acceptable as being fire rated. | |||
, b. Evaluation of the fire rating of existing doors by Factory Mutual Research is acceptable to the NRC staff. | |||
C ~ The unprotected structural steel will be shown to be acceptable using a methodology acceptable to the NRC. | |||
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REQUEST NO. 6 PAGE 2 SPRINKLER FIRE ZONE BELOW/ PROTECTION BELOW FIRE ZONE ABOVE STRUCTURAL STEEL COMBUSTIBLE LOADING Unit 82 Reactor Building (Cont.) | |||
2-3B-N/2-4A-S Yes 16 min 2-3B-N/2-4G Yes 16 min 2-3B-W/2-4C Yes 16 min 2-3B-W/2-4D Yes 16 min 2-4A-S/2-5A-W Yes 15 min 2-4A-W/2-5A-N Yes 15 min 2-4A-W/2-5A-W Yes 15 min 2-4G/2-5B No 4 min 2-4A-W/2-5E Yes 15 min 2-4A-W/2-5F Yes 15 min 2-4A-W/2-5G Yes 15 min 2-5A-S/2-6A Yes 6 min 2-5C/2-6A No 6 min 2-6A/2-4G No 6 min Control Structure Elevation 754'-0 Yes (Part) 62 min Support Steel JUSTIFICATION: | |||
Unit 81 and I/2 Reactor Buildings: | |||
lt All fire zones have sprinkler protection below the exposed structural for Fire Zones l-lE, 1-1F, 2-1E, 2-1F 2-4G, 2-5C and 2-6A. In these steel'xcept fire zones the maximum combustible rating is 18 minutes, and minimal transient combustibles are expected. Finally, the in-situ combustibles in these fire zones are generally located near the floor at a distance from where the structural steel forming the fire area barrier is located. | |||
CONTROL STRUCTURE: | |||
Automatic detection and protection is provided below the exposed structural steel. The majority of the combustibles in the area below the exposed structural steel are cables. The majority of the cables are located either below the raised (computer type) floor in the Control Room or in 2 hour fire rated cable chases on the north and south walls of the control structure where only one structural member is effected. There is approximately 20 feet between the raised computer floor and the exposed structural steel supporting elevation 754'-0. Finally, the Control Room comprises the majority of the area beneath this steel and it is continually staffed. | |||
EXEMPTION RE UEST: | |||
Exposed structural steel supporting the identified fire area barriers is acceptable and does not requ9.re fire proofing. | |||
djk/h188c3:del | |||
CONTROL STRUCTURE FIRE AREA FIRE ZONE(S) | |||
CS-1 0-21B,029A CS-2 0-22B, 0-29C,D CS-3 0-21A, 0-22A, 0-22C, 0-23, 0-24A-G, 0-25A,E CS-4 0-24I,L CS-5 0-24K CS-6 0-24J, 0-25B, 0-26B,S, 0-27F, 0-28P CS-7 0-24L,M, 0-25C,D, 0-26C,D, 0-26T,V, 0-27G,H, 0-28Q,R CS-8 0-28S CS 9k* 0-26A,E-N,P,R CS-10~* 0-27A-E CS-11 0-28A Subzone I (Room C-613) | |||
CS-12 0-28C CS-13 0-28E CS-14 0-28G CS-15 0-28H CS-16 0-28J CS-17 0-28B Subzone I (Room C-604) | |||
CS-18 0-28M CS-19 0-28N CS-20 0-28A Subzone II (Rooms C-611, C-612) | |||
CS-21 0-28T CS-22 0-28D CS-23 0-28F n CS-24 0-28B Subzone II (Rooms 'C-605, C-606) | |||
CS-25 0-28I CS-26 0-28K CS-27 0-28L CS-28 0-29B, 0-30A,B* | |||
* These fire zones contain no safe shutdown cables and function as a stbu fferies fire zone | |||
** The floor/ceiling between Fire Area CS-9 and CS-10 has unprotected support steel. See Exemption Request Number 6. | |||
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ER-IZ, Q ER-SCALE-DATE-DRAWN-CHECKED- PINN$ Yl.VANIA POND.R a LIGHTS (ONPAHY LEADER- ALLENTOWN, PA. | |||
APPR'D. APPROVED I | |||
NO. DATE ER. REVISION CH. BY APPROVED APPR'D. | |||
77/5 DECIMAL RIACTIONAL LOCATION CODE DESCRIPTION | |||
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Latest revision as of 14:20, 3 February 2020
ML18040B123 | |
Person / Time | |
---|---|
Site: | Susquehanna |
Issue date: | 10/03/1985 |
From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
To: | Butler W Office of Nuclear Reactor Regulation |
References | |
PLA-2541, NUDOCS 8510080410 | |
Download: ML18040B123 (15) | |
Text
'
REGULATOR INFORMATION DISTRIBUTION S STEM (RIDS)
ACCESSION'BR o 8510.080410, OOC DATE! 65/10/03 NOTARIZED; NO cocKET e FACIL:50 387 Susquehanna Steam
~
Electric Stationi Unit ii Pennsylva 05000387 50 386 Susquehanna BYNAME Steam Electric Stationi Unit 2'< Pennsylva 05000388 AUTH AUTHOR AFFILIATION KEISER<H,W. Pennsylvania Power 8'ight Co ~
RECIP ~ NAMKl RECIPIENT AFFILXATION BUTLERgW ~ Ri Licensing Branch 2
SUBJECT:
Suppls uti] 650904 .ltr re resolution of fire~ protection concerns. Listed replacement pages- re sprinkler protection for control structure elevation 8 shutdown paths SIZE; encl'ISTRIBUTI N CODE: A0060 COPIES RECEIVED:L~TR. ENCL TITI E: OR Submittal: Fire Prote'ction NOTES: 1cy NMSS/FCAF/PM'PDR 2cys 05000387 07/17/62 Transcripts'L:
icy NMSS/FCAF/PM'PDR 2cys Transcripts; 05000386 OLe03/23/84 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR LB2 BC 01 3 3 INTERNAL: ACRS 11 3 3 ADM/LFMB 0 ELD/HDS4 0 IE NHITNEYIL 1 1 NRR STANGrJ 07 2.' NRR ÃERMEILiJ06 1 0 NRR/DE/CEB 09'4 2 2 NRR/DL DIR 1 1 1 1 RGN1 1 1 EXTERNAL: 24X LPDR 03 NRC PDR 02" NSIC 05 1 1 NOTES:
TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 22
Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/770.5151 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 OCT O3 1985 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION RESOLUTION OF FIRE PROTECTION CONCERNS ER 100450 FILE 841-2, 143 Docket Nos. 50-387 PLA-2541 50-388
Dear Dr. Butler:
This letter supplements PLA-2529, dated September 4, 1985. Enclosed are replacement pages as follows:
~Pa e Descri tion of Chan e Page 3 of Concern 81 Revise Section 2.2 to clarify use of non-rated boundaries Page 2 of Request /f6 in Sprinkler protection for the Appendix A to Concern //1 Control Structure Elevation 754'-0" support steel is partial protection Figure 6 of Appendix B to Shutdown paths 3 6 4 were Concern 81 added to zone 1-6C Figure 9 of Appendix B to Shutdown paths 3 6 4 were Concern Pl added to zone 1-6C Figure 10 of Appendix B to Shutdown paths 3 & 4 were Concern 81 added to zone 1-6C Figure 11 of Appendix B to Added the amount of combustible Concern lI1 loading for zone 1-5C I
" 851 0P FtaR ".OA80<>0 ADOCg "8Seoo3 (OO4 OSOOO3 .
( l I DR
Page 2 SSES PLA-2541 Qg 08 1985 ER 100450 File 841-2, 143 Dr. W. R. Butler
~Pa e Descri tion of Chan e Page 3 to Attachment 2 of Added notes to page regarding Appendix B to Concern //1 the control structure The above changes are editorial clarifications which do not affect the conclusions of the analysis.
Should you have any questions please contact us.
Very truly yours, H. W. Keiser Vice President-Nuclear Operations cc: M. J. Campagnone NRC R. H. Jacobs NRC
iii) Identifying on a case by components which are not case the rated and specific barrier providing a justification for their use.
Any additional fire rated protection required as a result of this redefinition will be in accordance with 10CFR50 Appendix R, Section III.G.
2.2 Other Safety Related Buildings The methodology used in the Control Structure, the Diesel Generator buildings and the ESSW pumphouse was somewhat different since the majority of the fire zone boundaries are fire rated and, as a result, our fire zone boundaries are equivalent to fire area boundaries. For these buildings each fire zone was reviewed for its safe shutdown division. Fire zones having a common safe shutdown division were grouped into fire areas. Each fire area was reviewed to assure that all of its boundaries were fire rated construction, or if a non-rated boundary was acceptable.
3.0 ASSUMPTIONS & NRC GUIDANCE 3.1 The analysis was performed in accordance with the following NRC guidance:
- a. 10 CFR 50, Appendix R Section III.G.
- b. Generic Lett'ers 83-33 and 85-01.
I c~ NRC letter to PP&L dated April 18, 1985 which states:
"The reassessment of non-rated construction should be in accordance with guidance presented at the site audit. That is, to provide reasonable assurance that fire propagation will not occur beyond non-fire-rated zone boundaries, the boundaries should be upgraded, to be continuous barriers with a fire rating sufficient to withstand the effects of a fire involving in-situ and transient combustibles, with conservative margin. If boundary construction is not upgraded, your reassessment should assume that fire spread will occur into the next most immediate fire zone (horizontally and/or vertically)."
3.2 The analysis performed was based on the following assumptions:
aO The concrete block or reinforced concrete used in the construction of walls, floors and ceilings are acceptable as being fire rated.
, b. Evaluation of the fire rating of existing doors by Factory Mutual Research is acceptable to the NRC staff.
C ~ The unprotected structural steel will be shown to be acceptable using a methodology acceptable to the NRC.
~h
~ P p
P D
N K
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REQUEST NO. 6 PAGE 2 SPRINKLER FIRE ZONE BELOW/ PROTECTION BELOW FIRE ZONE ABOVE STRUCTURAL STEEL COMBUSTIBLE LOADING Unit 82 Reactor Building (Cont.)
2-3B-N/2-4A-S Yes 16 min 2-3B-N/2-4G Yes 16 min 2-3B-W/2-4C Yes 16 min 2-3B-W/2-4D Yes 16 min 2-4A-S/2-5A-W Yes 15 min 2-4A-W/2-5A-N Yes 15 min 2-4A-W/2-5A-W Yes 15 min 2-4G/2-5B No 4 min 2-4A-W/2-5E Yes 15 min 2-4A-W/2-5F Yes 15 min 2-4A-W/2-5G Yes 15 min 2-5A-S/2-6A Yes 6 min 2-5C/2-6A No 6 min 2-6A/2-4G No 6 min Control Structure Elevation 754'-0 Yes (Part) 62 min Support Steel JUSTIFICATION:
Unit 81 and I/2 Reactor Buildings:
lt All fire zones have sprinkler protection below the exposed structural for Fire Zones l-lE, 1-1F, 2-1E, 2-1F 2-4G, 2-5C and 2-6A. In these steel'xcept fire zones the maximum combustible rating is 18 minutes, and minimal transient combustibles are expected. Finally, the in-situ combustibles in these fire zones are generally located near the floor at a distance from where the structural steel forming the fire area barrier is located.
CONTROL STRUCTURE:
Automatic detection and protection is provided below the exposed structural steel. The majority of the combustibles in the area below the exposed structural steel are cables. The majority of the cables are located either below the raised (computer type) floor in the Control Room or in 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire rated cable chases on the north and south walls of the control structure where only one structural member is effected. There is approximately 20 feet between the raised computer floor and the exposed structural steel supporting elevation 754'-0. Finally, the Control Room comprises the majority of the area beneath this steel and it is continually staffed.
EXEMPTION RE UEST:
Exposed structural steel supporting the identified fire area barriers is acceptable and does not requ9.re fire proofing.
djk/h188c3:del
CONTROL STRUCTURE FIRE AREA FIRE ZONE(S)
CS-1 0-21B,029A CS-2 0-22B, 0-29C,D CS-3 0-21A, 0-22A, 0-22C, 0-23, 0-24A-G, 0-25A,E CS-4 0-24I,L CS-5 0-24K CS-6 0-24J, 0-25B, 0-26B,S, 0-27F, 0-28P CS-7 0-24L,M, 0-25C,D, 0-26C,D, 0-26T,V, 0-27G,H, 0-28Q,R CS-8 0-28S CS 9k* 0-26A,E-N,P,R CS-10~* 0-27A-E CS-11 0-28A Subzone I (Room C-613)
CS-12 0-28C CS-13 0-28E CS-14 0-28G CS-15 0-28H CS-16 0-28J CS-17 0-28B Subzone I (Room C-604)
CS-18 0-28M CS-19 0-28N CS-20 0-28A Subzone II (Rooms C-611, C-612)
CS-21 0-28T CS-22 0-28D CS-23 0-28F n CS-24 0-28B Subzone II (Rooms 'C-605, C-606)
CS-25 0-28I CS-26 0-28K CS-27 0-28L CS-28 0-29B, 0-30A,B*
- These fire zones contain no safe shutdown cables and function as a stbu fferies fire zone
- The floor/ceiling between Fire Area CS-9 and CS-10 has unprotected support steel. See Exemption Request Number 6.
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ER-IZ, Q ER-SCALE-DATE-DRAWN-CHECKED- PINN$ Yl.VANIA POND.R a LIGHTS (ONPAHY LEADER- ALLENTOWN, PA.
APPR'D. APPROVED I
NO. DATE ER. REVISION CH. BY APPROVED APPR'D.
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