ML19318D018
| ML19318D018 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/30/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-12, TASK-06-02.D, TASK-3-12, TASK-6-2.D, TASK-RR NUDOCS 8007070210 | |
| Download: ML19318D018 (11) | |
Text
-
3 N
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Tp COR80m8f8 (t
j Power gc2; company General Off6ces: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 C
June 30, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Projects Branch No 5 U S Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - SEP TOPIC III-12 ENVIRONMENTAL QUALIFICATION: SUBMITTAL OF REQUESTED INFORMATION NRC letter dated March 28, 1980, requested specille information to support NRC review of the subject topic. Specifically, information necessary to calculate containment temperature and pressure after an accident, and data concerning predicted loss of woolant accident mass and energy release was requested. The requested information is transmitted herewith.
The analysis descrited in the Final Hazards Summary Report represents the only analysis of Big Rock Point containment response following an accident.
Data used in this analysis is not recoverable. A reanalysis is underway and is expect-ed to be completed in the near future. provides information from this reanalysis in response to the NRC request.
The most recent analysis of a loss of ecolant accident at Big Rock Point is des-cribed in Exxon Nuclear Company report :CT-NF-Tc-53 submitted for review by Con-sumers Power Company letter dated March 7,1979 provides mass and ener7 release data from this analysis.
e David P Hoffman (Signed)
David P Hoffman Nuclear Licensing Adninistrator CC JGKeppler, USNRC NRC Resident Inspector - Big Rock Point Attachments (5) 0 70 @p
l, e
A'ITACEMENT 1 DATA NECESSARY FOR THE STAFF CALCULATION OF CONTAINMENT TEMPERATURE AND PRESSURE DECAY TIME I.
A.
CONTAINMENT NET FREE VOLUME 3
V=912,900 ft B.
PASSIVE HEAT SINKS
" Identify structures, components and equipment that act as passive heat sinks within the containment. Provide the following informa-tion:"
"l)
Total exposed heat transfer surface area with clarification if the exposed area is for one or both sides of the material."
Attached is CONTEMPT input data providing the heat conductor parameters for surface area thickness and thermophysical properties.
"2)
Total equivalent thickness" See B-1 above.
"3) Thermophysical properties (ie, density, specific heat and thermal conductivity)."
See B-1 above.
C.
INITIAL CONTAINMENT CONDITIONS
" Initial containment atmosphere conditions for:"
"l) temperature" 100 F "2) pressure" 114.7 psia "3) relative humidity" 100%
D.
CONTAINMENT SPRAY SYSTEM "l) -Parameters and their setpoints to activate spray:"
High containment pressure; 2.2 psig and time delay of 15 minutes initiates valve opening.
2 "2)
Spray sy3 tem activation time:"
The time associated with each of the following is needed (indicate whether or not they are additive):
"a) time elapsed until signal to activate spray system is reached:"
i l
l approximately one (1) second l
l "b) time elapsed between reaching signal to activate spray and contact closure (total instrumentation lag time):"
l 15 minute time delay "c) time required for diesel generator to attain full oper-ating speed:"
l 39 3 seconds (based on Technical Specification change i
request dated February 25,1980)
"d) time required for loading of containment spray pump:"
l Containment spray water is provided by the fire system.
Starting of electric and diesel fire pump is initiated on low steam drum level. Fire pumps are also source of core spray water. Pumps vill be in operation for l
core spray requirements prior to expiration of the 15 minute time delay for containment spray valve opening.
"e) time required to open isolation valve:"
No time requirements have been set. Tests have shown approximately 45 seconds are needed to open the valves.
"f) time required for containment spray pump to achieve full speed:"
The containment sprays are initially supplied by the fire system pumps which are in operation at full speed prior to containment spray initiation time.
"g) time required to fill spray system piping and deliver l
vater to spray header:"
Approximately 33 seconds at rate of 285 gym.
The time to deliver containment spray flow following a large break
' is the summation of items a, b, e, and g which total about 161/3 minutes.
L "3)
Identify the spray heat exchanger type, such as U-tube, crossflov or counterflow:"
U-tube; two passes on shell side and four passes on tube side.
l L_
3 E. FAN COOLER SYSTEM Not applicable to Big Rock Point.
"F.. Identify any other containment heat removal system that affects the con-tainment temperature response. Provide the same type of information as in Item D above."
Cooling through the containment vall is another method of contairJnent heat removal.
Big Rock Point's containment building is a spherical steel vessel 130 feet in diameter; approximately 27 feet extend below grade. The vessel vall is nominally 0.7 inches and is coated on its exterior by a cork mastic insulation of approximately 3/8 inch thickness. In addition, the top half of the sphere has an additional 1/h inch of foamglass insula-tion covering the mastic.
Some amount of heat is expected to conduct through the vall and insula-tion and be lost.to the atmosphere by convective heat transfer. Except for modeling the containment vessel as a heat sink with one side insulat-ed, no credit has been taken for cooling of the containment shell by con-vection to the outside atmosphere.
"G. Provide a discussion of the single failure assumed in the analysis."
The assumed single failure in the attsched flow diagrams is failure of a fire pump. This provides the lowest contair;nent spray flow.
It is different from the LOCA analysis which assumes diesel generator failure.
H. MASS AND ENERGY RELEASE DATA
" Provide the mass and energy release rate data for the postulated pipe break considered."
Data from a Relap 4 Thermal Hydraulic Analysis dated January 30, 1979, for a Double-ended Cold Leg Guillotine Break is included in Attachment 2.
The end of blevdown occurs at 27.7 seconds, when essentially all the water from the primary system is released to the containment atmosphere.
The total flow rate is the sum of the absolute values of the given flow rates. The heat released from the metal in the primary system is not included in the energy. release data.
"II.
Figure 1 and 2 represent typical ECCS and spray systems relied on to mitigate the consequences of a pipe break.. Provide the information indicated in the figures..If the plant specific systems differ from the attached figuru, revise the drawings to represent your facility and provide the appropr ate information.
When providing system parameters, indicate whether the values given assume a single failure and specify the single failure assumption."
? Attached are' completed figures 1 and 2.
4 For the injection mode, failure at a fire pump is assumed. Du2_ng injection, the core. sprays and containment spray are supplied from Lake Michigan via the fire system. Flows are given for the time before the containment spray initiates and after the 15 minute time delay for these sprays.
Containment pressure is assumed to be equal to reactor pressure at the containment design of 27 psig.
The break is assumed to be in a non-ECCS line break which results in the worst case for containment spray flow that is consistent with the blowdown data for the large break LOCA. However, an ECCS line break with the single failure of one pump would result in a smaller flow rate from the containment sprays. Both the core sprays are operational, thereby limiting the amount of water available to the containment spray. Since the backup containment spray valve is electri-cally inoperable in the closed position, only the primary containment spray is
{
assumed operable.
For the recirculation mode, the containment spray is expected to be intermittent as the operator may procedurally close the isolation valve when pressure drops i
to below approximately 1 1/h psi. During recirculation also, the backup core spray is procedurally isolated. The flows given in figure 2 reflect plant pro-cedures which call for the operation of the primary core spray and intermittent use of the containment spray, and only one core spray pump at a time. Thc core spray pump supplies both sprays. If there is no containment spray flow, all i
flow would be directed to tSe core at a rate of approximately 380 gym. Contain-ment and reactor pressure is again assumed to be 27 psig for the flows given.
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- F Spill GPM Temp FIGURE 1 - INJECTIctt PHASE S
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BTU Contairracnt Spray ID: UA O.2 x 10 hr *F Cooling Water Temp 70 F
Recirculation Fnase Figure 2 F6CIRCULATIO I FIL4SE t
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ATTACIIMENT 2 l
t/. ASS AIID ENERGY RELEASE DATA BRP I/ ass and Energy Release Data for Double Ended Cold Leg Guillotine
/
Break from Relap 4 Thermal Hydraulic Analysis (Ref: XN-UF-70-53 submitted for NRC review March 7,1979).
TIIG FLOW (38)*
FLOW (39)*
ENTHALPY(38)
EImIALPY(39)
- SEC.
Ib./sec.
Ib./sec.
BTU /lb.
BTU /lb.
.1 7,786
-13,587 561 563
/
r
.2 6,566
-12,054 559 562 j
.h 6,049
- 9,911 557 561
.6 6,827
- 8,311 559 560
.8 7,687
- 7,499 561 561 1.0 8,o18
--7,057 563 562
,2 6,623
- 6,211 566 566 5
5,617
- 5,847 564 570 4
2,620
- 5,342 747 572 5
2,461
- 4,493 757 578 6
2,330
- 3,517 731 598 7
1,979
- 2,675 722 628 8
1,649
- 2,c62 722 649 9
1,365
- 1,586 732 668 10 1,144
- 1,223 751 666 11 851 932 766 696 12 658 761 782 694 13 508 628 808 679 14 391 533 837 656 452 874 63h 15 315 16 239 382 909 612 325 945 586 17 197 18 153 279 950 543 19 127 237 913 527 20 103
- - - 200 876 522 21 S6 169 861 519 22 83 144 841 510 123 818 303 23 71 24 66 Ic6 810
'o 25 61 90 716 26 67 83 6c6 5
27 77 75 527
'; 36 2'/.7 73 73 S19 51h
- !!cdalization diagram is Figure 2.1 of the reference