PLA-2541, Suppls Util Re Resolution of Fire Protection Concerns.Listed Replacement Pages Re Sprinkler Protection for Control Structure Elevation & Shutdown Paths Encl
| 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 FACIL:50 387 Susquehanna Steam Electric Stationi Unit ii Pennsylva 50 386 Susquehanna Steam Electric Stationi Unit 2'< Pennsylva AUTH BYNAME 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 encl'ISTRIBUTI N CODE:
A0060 COPIES RECEIVED:L~TR.
ENCL SIZE; TITI E:
OR Submittal: Fire Prote'ction NOTES: 1cy NMSS/FCAF/PM'PDR 2cys Transcripts'L:
07/17/62 icy NMSS/FCAF/PM'PDR 2cys Transcripts; OLe03/23/84 cocKET e
05000387 05000388 05000387 05000386 RECIPIENT ID CODE/NAME NRR LB2 BC 01 INTERNAL: ACRS 11 ELD/HDS4 NRR STANGrJ 07 NRR/DE/CEB 09'4 COPIES LTTR ENCL 3
3 3
3 0
2.'
2 2
1 1
RECIPIENT ID CODE/NAME ADM/LFMB IE NHITNEYIL NRR ÃERMEILiJ06 NRR/DL DIR RGN1 COPIES LTTR ENCL' 0
1 1
1 0
1 1
1 1
EXTERNAL: 24X NRC PDR NOTES:
02" LPDR NSIC 03 05 1
1 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 PLA-2541 Docket Nos.
50-387 50-388
Dear Dr. Butler:
This letter supplements PLA-2529, dated September 4,
1985.
Enclosed are replacement pages as follows:
~Pa e
Page 3 of Concern 81 Descri tion of Chan e
Revise Section 2.2 to clarify use of non-rated boundaries Page 2 of Request
/f6 in Appendix A to Concern
//1 Figure 6 of Appendix B to Concern 81 Sprinkler protection for the Control Structure Elevation 754'-0" support steel is partial protection Shutdown paths 3 6 4 were added to zone 1-6C Figure 9 of Appendix B to Concern Pl Shutdown paths 3 6 4 were added to zone 1-6C Figure 10 of Appendix B to Concern 81 Shutdown paths 3
& 4 were added to zone 1-6C Figure 11 of Appendix B to Concern lI1 Added the amount of combustible loading for zone 1-5C
" FtaR.OA80<>0 "8Seoo3 I
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" ADOCg OSOOO3
( l I DR (OO4
Qg 08 1985 Page 2
SSES PLA-2541 ER 100450 File 841-2, 143 Dr.
W. R. Butler
~Pa e Descri tion of Chan e
Page 3 to Attachment 2 of Appendix B to Concern
//1 Added notes to page regarding 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 case the specific barrier components which are not rated and providing a justification for their use.
Any additional fire rated protection required as a result of this redefinition willbe 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.
c ~
Generic Lett'ers 83-33 and 85-01.
I 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.
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The unprotected structural steel willbe shown to be acceptable using a methodology acceptable to the NRC.
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FIRE ZONE BELOW/
FIRE ZONE ABOVE SPRINKLER PROTECTION BELOW STRUCTURAL STEEL REQUEST NO.
6 PAGE 2
COMBUSTIBLE LOADING Unit 82 Reactor Building (Cont.)
2-3B-N/2-4A-S 2-3B-N/2-4G 2-3B-W/2-4C 2-3B-W/2-4D 2-4A-S/2-5A-W 2-4A-W/2-5A-N 2-4A-W/2-5A-W 2-4G/2-5B 2-4A-W/2-5E 2-4A-W/2-5F 2-4A-W/2-5G 2-5A-S/2-6A 2-5C/2-6A 2-6A/2-4G Yes Yes Yes Yes Yes Yes Yes No Yes Yes Yes Yes No No 16 min 16 min 16 min 16 min 15 min 15 min 15 min 4 min 15 min 15 min 15 min 6 min 6 min 6 min Control Structure Elevation 754'-0 Support Steel JUSTIFICATION:
Yes (Part) 62 min Unit 81 and I/2 Reactor Buildings:
lt All fire zones have sprinkler protection below the exposed structural steel'xcept for Fire Zones l-lE, 1-1F, 2-1E, 2-1F 2-4G, 2-5C and 2-6A.
In these 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.
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CONTROL STRUCTURE FIRE AREA CS-1 CS-2 CS-3 CS-4 CS-5 CS-6 CS-7 CS-8 CS 9k*
CS-10~*
CS-11 CS-12 CS-13 CS-14 CS-15 CS-16 CS-17 CS-18 CS-19 CS-20 CS-21 CS-22 CS-23 CS-24 CS-25 CS-26 CS-27 CS-28 FIRE ZONE(S) 0-21B,029A 0-22B, 0-29C,D 0-21A, 0-22A, 0-22C, 0-23, 0-24A-G, 0-25A,E 0-24I,L 0-24K 0-24J, 0-25B, 0-26B,S, 0-27F, 0-28P 0-24L,M, 0-25C,D, 0-26C,D, 0-26T,V, 0-27G,H, 0-28Q,R 0-28S 0-26A,E-N,P,R 0-27A-E 0-28A Subzone I (Room C-613) 0-28C 0-28E 0-28G 0-28H 0-28J 0-28B Subzone I (Room C-604) 0-28M 0-28N 0-28A Subzone II (Rooms C-611, C-612) 0-28T 0-28D 0-28F n
0-28B Subzone II (Rooms 'C-605, C-606) 0-28I 0-28K 0-28L 0-29B, 0-30A,B*
- These fire zones contain no safe shutdown cables and function as a
stbufferies 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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