ML20091H580
| ML20091H580 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/30/1984 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8406050215 | |
| Download: ML20091H580 (17) | |
Text
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'Af Telephone (412) 393-6000 Nuclear Division P.O. Box 4 Shippingport, PA 15077-0004 May 30, 1984 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Div!sion of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station Docket No. 50-334, License No. DPR-66 Appendix R - Revised Exemption Request for Structural Steel Gentlemen:
Enclosed is a revision to our requested exemption for Structural Steel previously submitted on December 16, 1983 as Attachment VII " Structural Steel, Se rvice Building Elev. 713 area below the Cable Spreading Room (CS-1)".
The steel stresses and reserve capacities have been recalculated, as noted on pages 5, 7 and 8 of the attachment, for greater accuracy compared to the more conse rvative estimates provided in the previous submittal. Since the steelwork supports an area that is normally unoccupied and does not serve as an access / egress route, live loads have been eliminated in the stress calculations.
Seismic loads are also totally excluded because the probability of a simultancous fire and a seismic event need not be postulated per the Appendix R guidelines.
The basis for the requested exemption from III.G.2a remains valid.
That is, all the steel beams still show a reserve capacity even though the new calculations show a slight decrease in value.
In addition, it can be concluded that the maximum beam stress remains lower than the postulated yield stress at 1100*F.
Please contact my staf f if additional information or clarification is necessary.
Very trul* yours, Carey Vice President, Nuclear a
e406050215 840530 1
PDR ADOCK 05000334 F
PDR i
- Be:vsr VallGy Pow;r Station Dock;t N3. 50-334, Licansa Na DPR-66 Appendix R - Revised Exemption Request for Structural-Steel
-Page 2 Enclosures cc:- Mr. W. M. Troskoski, Resident Inspector U._S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S.' Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Attn:
Dr. Thomas E. Murley, Regional Director Region I 631 Park Avenue King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Division of Licensing Attn:
D. C. Eisenhut, Director Washington, DC 20555 U. S. Nuclear Regulatory Commission Office of Nt: clear' Reactor Regulation Attn:
S. J. Chilk, Secretary of the Commission Washington, DC 20555 Mr. Peter Tam, Project Manager U. S. Nuclear Regulatory Commission
-Phillips Building Washington, DC 20555 Mail'Stop 438
=
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..,i ATTACHMENT VII EXEMPTION VII. (Structural Steel) Service Bldg.
EL.
713' area below the Cable Spreading Room (CS-1)
Fire Areas:
ES-1' West. Emergency-Switchgear Room ES-2 East Emergency Switchgear Room MG-1 Control Rod Drive Motor Generator Room
'CR-3 Communications Equipment and Relay Panel Room
.CR-4 Process Instrument'and Rod' Position Room (See Attached Figures 11.13-1 and 2)
A.
Discussion The structural steel located in the above fire areas, which he"ps to support the above floor area cable spreading room (CS-1),
is denoted in Figure 11.13-1.
Located in these areas are various safe shutdown cabling as discussed in Section D below.
An -exemption is requested from III.G.2a which requires that i
tstructural steel forming a part of or supporting -fire barriers I
separating redundant trains to. have a fire rating equivalent to -
the fire resistance-of the barrier.
A fire hazards-analysis. has 4
been performed and documented within this reque'st for exemption which justifies the acceptability of. the 'present plant design based on equivalent level of protection, and shows the maximum E
temperature the.s:*,el will reach during a fire in these areas and it's ability to cat y the required loads.
F B.
Boundaries
-The. construction af all of the above listed areas constitutes a 3-hour'raL4d fire L..t.;z Letween each of the adjacent fire areas i -
with the ageeption of the ceiling slab described below.
- 1. -
-Walls (Ref. Drawing 11700-RC-8A,1-8B)
Reinforced Concrete:
a.
North The. north wall faces the 4KV Normal Switchgear Room (NS-1), the pipe chase, and the-turbine building and is divided into 'two sections of different thicknesses.
(1) 2ft.0in reinforced concrete at the pipe chase and NS-1.
(2)~ Ift.61n.
reinforced concrete at the turbine building.
Page 1 Revision 1
- b, South The south ~ wall faces an unexcavated area, Primary Auxiliary building (PAB) and the A/C Equipment Room (CR-2) and is divided into two sections of different thicknesses.
.(1) 2ft0in.
reinforced concrete at that section which parallels the unexcavated area and the PAB.
(2) ift.0in. reinforced concrete at that section which parallels CR-2.
c.
East The east wall faces the Cable Tunnel (CV-3) and the A/C Equipment Room (CR-2) and is divided into two sections of different thicknesses.
(1) 2ft.0in. reinforced concrete at that section which parallels CV-3.
(2) ift.0in. reinforced concrete at that section which parallels CR-2.
d.
West 2ft.0in.
parallels an unexcavated area and the normal switchgear room (NS-1).
e.
' Intermediate walls' running north-south between areas ES-1 and ES-2, ES-2 and MG-1, MG-1 and CR-4, and CR-4 and CR-3 are all if t. 0 in,
reinforced concrete with
. qualified 3-hour fire rated penetration seals, as required, which constitutes a 3-hour fire barrier between these rooms.
l 2.
Ceiling (Ref. Drawing 11700-RC-7G)
Reinforced concrete- (5 1/2" max., 4" min.) on i 1/2 inches corrugated metal decking constitutes a minimum i 1/2-hour l
fire rated barrier per the fire resistance / concrete thickness curve (Figure 11.13-3)*.
See Figure 11.13-6 for details of ceiling slab.
(See Exemption Request for CS-1 area, ATTACHMENT XI) 3.
Floor (Ref. Drawing 11700-RC-8G,-8H)
Minimum 3 ft, reinforced concrete 4.
Room Volumes ES-1 29,220 cu.ft.
ES-2 28,220 cu.ft.
MG-1 17,160 cu.ft.
CR-4 65,880 cu.ft.
CR-3 10,980 cu.ft.
- Reference.
NFPA Fire Protection Handbook; 15th edition, 1983.
Figure 5-8R.
Page 2 Revision 1 u
C.
. Ventilation a
1.
The ventilation supplyandedhaustsystemfcrES-1,ES-2&
MG-1-are the same.
All areas are exhausted to an outdoor
' dis charge ~.
Venting of.
any of the areas could be accomplished by resetting the respective fire dampers, all of which are accessible from the Cable Spreading Room (CS-1).
The power and controls for this ventilation system are outside the CS-1 area.
2.
The air conditioning system is the same for CR-3 and CR-4 as that for CR-1 and CR-2.
The system is detailed on Figure 11.13-4.
D.
. Redundant Safe Shutdown Equiement ES-1 and.ES-2 house redundant safety-related 4KV switchgear and 480V substations and supply power to' Class 1E circuits required for safi shutdown.
'MG houses,both class 1E and non-class 1E equipment and cable.
4 The two rod drive motor generator sets and switchgear supply power-to the CRDM's and are located in this area. These power s
supplies are not required for safe shutdown.
CR-4 consists of the primary and secondary process racks, reactor protection racks. and thei emergency auxiliary shutdown panel located in CR-4 area.
CR-3 'contains 'the safe shutdown: diesel generator protection panels and the relay and communication panels.
E.
Fire Protection Existing 1.
' Fire Det'ection Systems Early warning -detection system consists of area coverage within each ~ applicable fire area by.
ionization type detectors provided with local alarm and control room alarm display in the fire detection panel..CR-4 additionally has ionization detectors located in the sub-flooring which' alarm locally and in the control room and activates the Halon Suppression System in the event of a cable fire in the' subfloor area.
(Figure 11.13-5) 2.
Fire Extinguishing Systems l
a.
Portable Carbon Dioxide extinguishers presently exist within all areas, with additional portable Carbon Dioxide extinguishers available'in adjacent and nearby areas.
Additionally, portable 150-lb. wheeled dry chemical extinguisher units are available in the adjacent area (NS-1) and at the S-4 stairwell entrance.
Standpipe hose racks stations are available at both stairwell entrances on this elevation, b..
Halon 1301 Suppression System installed in the subfloor
. cable area of CR-4.
(Figure 11.13-5)
Page 3 Revision 1
. ~. _ _._. _ _ _ _ _.._- ~,_ _.
3.
Propagation Ratardents All cables installed at Beaver Valley Power Station Unit I were fabricated to pass the vertical cable tray flame test with an oil and burlap flame source which was the accepted industry standard during the construction of BV-1 and is comparable to IEEE-383 tests.
F.
Fire Hazard Analysis 1.
Type / Quantity of combustibles in these areas are all for cable insulation as noted.
Fire Area Cable Insulation ES-1 5,920 lbs.
ES-2 5,665 lbs.
MG-1 5,575 lbs.
CR-4 24,060 lbs.
CR-3 4,750 lbs.
2.
Heat Release Potential from Cable Insulation
. Fire' (Btu)
(Sq.ft)
(Btu /sq.ft.)
Area Heat Load Area Heat Release Potential 7
'6.51.4 10 2,435 31,660 7
ES-2 6.23 x 10 2,350 26,380 7
MG-1 6.13 x 10 1,430 48,420 CR-4 2.65 x 10' 5,490 50,200 7
CR-3 5.22 x 10 9 15 58,550 Based on the heat release potentials, the required fire ratings
- for each of the areas is less than one hour.
G.
Justification of Area Acceptability 1.
The fire loading for each of.the areas that contsin structural steel was determined to be as noted below.
In all
- cases, the existing walls, floors, ceilings and doors exceed this rating.
Fire Area Fire Loading Barrier Required ES-1 24 min.
Determined from ES-2 20 min.
the STANDARD TIME-MG-1 36 min.
TEMPERATURE CURVE CR-4 38 min.
CR 44 min.
Page 4 Revision 1 au
All tha areas notad contain structural steel members supporting the floor above (CS-1).
Because of hangers and cable tray supports attached to various beams, the stresses i
vary.
A reserve capacity exists and varies from 39% to 49%
(Min. To Max.) under working stress conditions.
Fire Area Minimum Reserve Capacity ES-1 49%
ES-2 48%
MG-1 39%
CR-4 46%
-CR-3 40%
It is recognized that a rise in temperature reduces the yield
. stress in steel and that at 1100*F the yield stress may drop to 60% of.the_value at room temperature. The most highly stressed beam still has not reached the yield point per our calculations.-( See Attachment 1)
Because steel has a high thermal conductivity, it can transfer heat away from a localized heat source rather
.quickly.
Heat will be' transferred to cooler regions through the grid of steel beams supporting the entire CS-1 floor area.
.A cushion of time can be anticipated in such large areas of heat dissipation.
2.
A margin ;of. safety is provided 'by the vertical concrete columns that. support the _ horizontal steel beams and the floor-to-ceiling solid 12 inches reinforced concrete walls separating areas ES-1, ES-2, MG-1, CR-4 and CR-3.
In the event the horizontal ceiling beams start to weaken, the floor load would be distributed onto the partition concrete walls and the vertical concrete columns in the area.
ate'd doors are installed between each of 3.
Three hour. fire r
these areas except CR-3/CR-4 which are 1 1/2 hour fire -rated
- doors, and all penetrations are sealed with a qualified 3-
. hour fire rated material.
4.
Hazardous quantities of transient combustibles would not be.
expected in this area for the following reasons:
a)
The area is not adjacent to or near_any major plant traffic route.
b)
Storage of transient combustibles in this area is prohibited by plant administrative procedures, c)
Maintenance and operations activities in this area do not involve,the use of large quantities of combustible materials.
d).
The accessibil'ity to the switchgear area is restricted due to the security system card-key access.
Page 5 Revision 1
5.
Tho_ installed serly warning smoke dataccion system would promptly datect incipisnt fire conditions in this area and the separation of redundant trains will maintain integrity of the cables and equipment until the fire brigade personnel, responding from the control roem area two floors above this switchgear area, respond to extinguish the rire via the southeast stairwell.
The brigade should be capable of' reaching this area within minutes after an alarm is received in the Control Room.
- This exemption request is predicated upon an equivalent level of protection to that required based on the above considerations and modifications.
i r
Page 6 Revision 1
Duquesne Light Company Sheet 1 of 1 LOCATION SERVICE BUILDING COMPILED SUBJECT STEEL FRAMING AT E1.725'-6" BY:
S. Bose Date 5/29/84 REFERENCES / DESIGN BASIS Stone & Webster Engr. Corp. (SWEC) calculations #11700-S-5 and #13387.13-S-59 are used to determine the stress levels for the most highly stressed beams for the separate fire areas.
Stresses due to dead load only, including all cable tray and conduit cupport loads, are derived from the referenced SWEC calculations and listed in the Stress Summary.
Since the steelwork supports a floor area that is not normally occupied, live load is neglected.
Yield stress of A36 steel is F =36Ksi. Allowable stress per AISC
=.66F, =.j Sec. 1.5.1.4.1 is F 66x36 =24 Ksi b
Reserve capacity = 1-4 /F, Prstulated yield stress at 1100*F=.6F,, =.6x36 =21.6 Ksi STRESS
SUMMARY
FIRE MOST HIGHLY STRESSED MAX. BENDING STRESS RESERVE AREA BEAM PER SWEC CALC 3.
f (KSI)
CAPACITY
(
ES-1 B-16.#13387.13-S-59 12.22 1-12.22/24=49%
ES-2 B-15.#13387.13-S-59 12.48 1-12.48/24=46%
MG-1 F-10.#11700-S-5 14.62 1-14.62/24=39%
CR-4 B-12.#13387.13-S-59.
12.99 1-12.99/24=46%
CR-3 B-3. #13387.13-S-59 14.41 1-14.41/24=40%
CONCLUSIONS 1.
All beams have a reserve capacity.
2.
The maximum beam stress (f - highest value 14.62).
3 is lower than 21.6 Ksi, the postulated yield stress at 1100*F.
ATTACHMENT 1 Page 7 Revision 1
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