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| issue date = 10/31/1986 | | issue date = 10/31/1986 | ||
| title = Forwards Rev to Deviation Request 6,addressing App R Re Nonfireproofing of Structural Steel,Including Issues & Concerns Raised by NRC During 860730 meeting.Thirty-two Oversize Drawings Encl | | title = Forwards Rev to Deviation Request 6,addressing App R Re Nonfireproofing of Structural Steel,Including Issues & Concerns Raised by NRC During 860730 meeting.Thirty-two Oversize Drawings Encl | ||
| author name = | | author name = Keiser H | ||
| author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | ||
| addressee name = | | addressee name = Adensam E | ||
| 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 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Pennsylvania Power 8 Light Company Two North Ninth Street~Allentown, PA 18101~215/770-5151 Harold W.Keiser'ice President-Nuclear Operations 21 5/770-7502 OCT 3 3 i986 Director of Nuclear Reactor Regulation Attention: | {{#Wiki_filter:Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/ 770-5151 Harold W. Keiser'ice President-Nuclear Operations 21 5/770-7502 OCT 3 3 i986 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Project Director BWR Project Directorate No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION APPENDIX R ADDITIONAL INFORMATION ON DEVIATION REQUEST NO. 6 NON-FIREPROOF STRUCTURAL STEEL Docket No. 50-387 PLA-2749 FILE P5-1, A17-15 and 50-388 | ||
Ms.E.Adensam, Project Director BWR Project Directorate No.3 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555 SUSQUEHANNA STEAM ELECTRIC STATION APPENDIX R | |||
==Dear Ms.Adensam:== | ==Dear Ms. Adensam:== | ||
Enclosed is our revision to Deviation Request Number 6 which addresses Non-Fireproofing of Structural Steel including issues and concerns raised by your staff during their meeting with us on July 30, 1986.In order to adequately address the issues and concerns raised by your staff, an extensive reanalysis of the Unit 1 and Unit 2 Reactor Buildings was performed. | |||
This effort required a detailed structural analysis in parallel with a fire protection evaluation in order to examine all areas of each building on a floor-by-floor, area-by-area, and case-by-case basis.Because of the shear magnitude of this effort, a substantial amount of time was required to complete it.Your staff expressed concern with our use of average combustible loadings in our previous analysis.Our reanalysis is based on fire test data (referenced in the attached summary report)and existing plant configurations. | Enclosed is our revision to Deviation Request Number 6 which addresses Non-Fireproofing of Structural Steel including issues and concerns raised by your staff during their meeting with us on July 30, 1986. | ||
If you have any questions regarding this submittal, please contact us.Very truly yours, | In order to adequately address the issues and concerns raised by your staff, an extensive reanalysis of the Unit 1 and Unit 2 Reactor Buildings was performed. This effort required a detailed structural analysis in parallel with a fire protection evaluation in order to examine all areas of each building on a floor-by-floor, area-by-area, and case-by-case basis. Because of the shear magnitude of this effort, a substantial amount of time was required to complete it. | ||
Your staff expressed concern with our use of average combustible loadings in our previous analysis. Our reanalysis is based on fire test data (referenced in the attached summary report) and existing plant configurations. | |||
FIRE ZONES AFFECTED:<'C-i Table 1.0 provides a list of the affected fire zones.This table,als'o.=reefs to a series of drawings associated with each fire rated floor',slab'o s6o'w'tfie extent of the required fire protection. | If you have any questions regarding this submittal, please contact us. | ||
REASON FOR DEVIATION RE UEST: I Within the Unit 1 and 2 Reactor Buildings and Control Structure, cert'ain floor/ceiling assemb'lies are to be upgraded to a 3 hour fire rating,',<t'o'eparate redundant safe shutdown equipment. | Very truly yours, H. W. | ||
The | qx Keiser Vice President-Nuclear Operations cc: M. C. Thadani NRC L. R. Plisco -'RC 8611060158- 861031 PDR 'DOCK 05000387 ':- | ||
F PDR | |||
APPENDIX R DEVIATION RE UEST E | |||
NON FIREPROOFED STRUCTURAL STEEL Deviation Request No. 6 Revised October'986 1 of 3 'age EIIATIOE EEIEII Exposed structural steel supporting the fire area barriers ident'ified below are acceptable and do not require fireproofing. | |||
FIRE ZONES AFFECTED: | |||
<'C- i Table 1.0 provides a list of the affected fire zones. This table,als'o.=reefs to a series of drawings associated with each fire rated floor',slab'o s6o'w'tfie extent of the required fire protection. | |||
REASON FOR DEVIATION RE UEST: | |||
I Within the Unit 1 and 2 Reactor Buildings and Control Structure, cert'ain floor/ceiling assemb'lies are to be upgraded to a 3 hour fire structural steel supporting rating,',<t'o'eparate redundant safe shutdown equipment. The these floors is not protected. | |||
JUSTIFICATION: | JUSTIFICATION: | ||
UNIT¹I AND¹2 REACTOR BUILDINGS: | UNIT ¹I AND ¹2 REACTOR BUILDINGS: | ||
Structural steel'associated with each of the Unit¹I and¹2 Reactor Building fire barriers required to be upgraded was examined and the evaluation criteria applied to demonstrate that fire proofing of this structural steel is not required was developed in the"Summary Report for Structural Steel Evaluation" documented as Engineering Study SEA-CE-003. | Structural steel 'associated with each of the Unit ¹I and ¹2 Reactor Building fire barriers required to be upgraded was examined and the evaluation criteria applied to demonstrate that fire proofing of this structural steel is not required was developed in the "Summary Report for Structural Steel Evaluation" documented as Engineering Study SEA-CE-003. To clearly demonstrate .the applicabi 1ity of this criteria to the fire area barriers in question:, | ||
To clearly demonstrate.the applicabi 1ity of this criteria to the fire area barriers in question:, | of each area, corresponding 'to the Fire Zones listed in .Tabl'e 1'.0, is a'rawing attached to this deviation request along with an area unique justification for each drawing. These drawings show the barrier area in question, the structural steel members supporting the barrier and the primary combustibles relevant to each area. Each drawing s corresponding unique justification references the section of the Summary Report for Structural Steel Evaluation that provides the basis for that justification. | ||
'to the Fire Zones listed in.Tabl'e 1'.0, is attached to this deviation request along with an area unique justification for each drawing.These drawings show the barrier area in question, the structural steel members supporting the barrier and the primary combustibles relevant to each area.Each drawing s corresponding unique justification references the section of the Summary Report for Structural Steel Evaluation that provides the basis for that justification. | |||
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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 | 's yf + | ||
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Deviation Request No. 6 Revised October of 1986'age 2 3 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. | |||
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* Deviation Request No. 6 Revised October 1986 Page 3 oE 3 TABLE 1.0 FIRE ZONE NFPA 13 BENEATH RATED TOP OF SLAB SPRINKLER PROTECTION DRAWING FLOOR SLAB ELEVATION PROVIDED REFERENCE Unit 1 Reactor Buil 1-1F 683'"0" No C-206006 Sht. 1 1-1E 683'" No C-206006 Sht. 2 1-3A 719'1" Partial C-206007-Shts. 1&2 1-3B-W 719'"1 Yes C-206021 Sht. 1 1-3B-W 719'"1 Yes C-206021 Sht. 2 1-4A-W 749 '-ln Yes C-206008 Shts. 1&3 1-4A-W '1" 1-4A-N 749 Yes C-206008 Sht. 2 1-4A-W 749'-1 Yes C-206008 Sht. 4 1"4A-S 1-4A-W 749 '1" Yes C-206008 Sht. 5 1-4A-N 1-4G 761'-3.0" C-206009 Shts. 1&2 1-5A-S 779'-1 Yes C-206010 Shts. 162 Unit 2 Reactor Build 2"1F 683'-00 No C-206011 Sht. 1 2-lE 683'-0" No C-206011 Sht. 2 2"3B-N 719'-1" Yes C-206012 Shts. 1&2 2-3B-W 719'-1" Yes C-206022 Sht. 1 2-3B-W 719<-l" Yes C"206022 Sht. 2 2-4A-S 749) "1u 2-4A-W Yes. C-206013 Sht. 1 2-4A-W 749'-1" Yes C-206013 Shts. 2&3 2-4A-W 749 '1" Yes C-206013 Sht. 4 2-4A-S 2-4A-W ,749 '1" Yes C-206013 SIlt. 5 2-4A-N 2-4G 761'"10" No C-206014 Shts. 1&2 2-5C 2-5A-S 779 1 Ill No C-206015 Shts.l,2&3 2-5B 2-6A 799'-1" C-206016 Sht. 1 Control Structure 0-26A) E-N) P) R 754'-0" Partial N/A dk/d205ai:mg}} | |||
Latest revision as of 14:24, 3 February 2020
| ML18040A816 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/31/1986 |
| From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17146A596 | List:
|
| References | |
| PLA-2749, NUDOCS 8611060158 | |
| Download: ML18040A816 (6) | |
Text
Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/ 770-5151 Harold W. Keiser'ice President-Nuclear Operations 21 5/770-7502 OCT 3 3 i986 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Project Director BWR Project Directorate No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION APPENDIX R ADDITIONAL INFORMATION ON DEVIATION REQUEST NO. 6 NON-FIREPROOF STRUCTURAL STEEL Docket No. 50-387 PLA-2749 FILE P5-1, A17-15 and 50-388
Dear Ms. Adensam:
Enclosed is our revision to Deviation Request Number 6 which addresses Non-Fireproofing of Structural Steel including issues and concerns raised by your staff during their meeting with us on July 30, 1986.
In order to adequately address the issues and concerns raised by your staff, an extensive reanalysis of the Unit 1 and Unit 2 Reactor Buildings was performed. This effort required a detailed structural analysis in parallel with a fire protection evaluation in order to examine all areas of each building on a floor-by-floor, area-by-area, and case-by-case basis. Because of the shear magnitude of this effort, a substantial amount of time was required to complete it.
Your staff expressed concern with our use of average combustible loadings in our previous analysis. Our reanalysis is based on fire test data (referenced in the attached summary report) and existing plant configurations.
If you have any questions regarding this submittal, please contact us.
Very truly yours, H. W.
qx Keiser Vice President-Nuclear Operations cc: M. C. Thadani NRC L. R. Plisco -'RC 8611060158- 861031 PDR 'DOCK 05000387 ':-
F PDR
APPENDIX R DEVIATION RE UEST E
NON FIREPROOFED STRUCTURAL STEEL Deviation Request No. 6 Revised October'986 1 of 3 'age EIIATIOE EEIEII Exposed structural steel supporting the fire area barriers ident'ified below are acceptable and do not require fireproofing.
FIRE ZONES AFFECTED:
<'C- i Table 1.0 provides a list of the affected fire zones. This table,als'o.=reefs to a series of drawings associated with each fire rated floor',slab'o s6o'w'tfie extent of the required fire protection.
REASON FOR DEVIATION RE UEST:
I Within the Unit 1 and 2 Reactor Buildings and Control Structure, cert'ain floor/ceiling assemb'lies are to be upgraded to a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire structural steel supporting rating,',<t'o'eparate redundant safe shutdown equipment. The these floors is not protected.
JUSTIFICATION:
UNIT ¹I AND ¹2 REACTOR BUILDINGS:
Structural steel 'associated with each of the Unit ¹I and ¹2 Reactor Building fire barriers required to be upgraded was examined and the evaluation criteria applied to demonstrate that fire proofing of this structural steel is not required was developed in the "Summary Report for Structural Steel Evaluation" documented as Engineering Study SEA-CE-003. To clearly demonstrate .the applicabi 1ity of this criteria to the fire area barriers in question:,
of each area, corresponding 'to the Fire Zones listed in .Tabl'e 1'.0, is a'rawing attached to this deviation request along with an area unique justification for each drawing. These drawings show the barrier area in question, the structural steel members supporting the barrier and the primary combustibles relevant to each area. Each drawing s corresponding unique justification references the section of the Summary Report for Structural Steel Evaluation that provides the basis for that justification.
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Deviation Request No. 6 Revised October of 1986'age 2 3 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.
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- Deviation Request No. 6 Revised October 1986 Page 3 oE 3 TABLE 1.0 FIRE ZONE NFPA 13 BENEATH RATED TOP OF SLAB SPRINKLER PROTECTION DRAWING FLOOR SLAB ELEVATION PROVIDED REFERENCE Unit 1 Reactor Buil 1-1F 683'"0" No C-206006 Sht. 1 1-1E 683'" No C-206006 Sht. 2 1-3A 719'1" Partial C-206007-Shts. 1&2 1-3B-W 719'"1 Yes C-206021 Sht. 1 1-3B-W 719'"1 Yes C-206021 Sht. 2 1-4A-W 749 '-ln Yes C-206008 Shts. 1&3 1-4A-W '1" 1-4A-N 749 Yes C-206008 Sht. 2 1-4A-W 749'-1 Yes C-206008 Sht. 4 1"4A-S 1-4A-W 749 '1" Yes C-206008 Sht. 5 1-4A-N 1-4G 761'-3.0" C-206009 Shts. 1&2 1-5A-S 779'-1 Yes C-206010 Shts. 162 Unit 2 Reactor Build 2"1F 683'-00 No C-206011 Sht. 1 2-lE 683'-0" No C-206011 Sht. 2 2"3B-N 719'-1" Yes C-206012 Shts. 1&2 2-3B-W 719'-1" Yes C-206022 Sht. 1 2-3B-W 719<-l" Yes C"206022 Sht. 2 2-4A-S 749) "1u 2-4A-W Yes. C-206013 Sht. 1 2-4A-W 749'-1" Yes C-206013 Shts. 2&3 2-4A-W 749 '1" Yes C-206013 Sht. 4 2-4A-S 2-4A-W ,749 '1" Yes C-206013 SIlt. 5 2-4A-N 2-4G 761'"10" No C-206014 Shts. 1&2 2-5C 2-5A-S 779 1 Ill No C-206015 Shts.l,2&3 2-5B 2-6A 799'-1" C-206016 Sht. 1 Control Structure 0-26A) E-N) P) R 754'-0" Partial N/A dk/d205ai:mg