ML20030A790
| ML20030A790 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/16/1981 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20030A789 | List: |
| References | |
| NUDOCS 8107290040 | |
| Download: ML20030A790 (4) | |
Text
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LIMITING CONDITIONS IUR OPERATION SURVLILLANCE REQUIREMENTS 3.7 Containment Systems 4.7 Containment Systems A plicability:
Applicability:
P Applies to the operating status of Applies to the primary and secondary the primary and seconda ry contain-containment integrity.
ment systems.
Obj ect tve :
Objective:
To assure the integrity of the pri-To verify the integrity of the primary mary and secondary containment systems.
Spe ci fica t ion:
Specification:
A.
Primary Containmett_
1.
At any time that the nuclear system 1.a. The suppression pool water level is pressurized above atmospheric and temperature shall be checked pressure or work is being done once per day, which has the potential to drain
- b. Whenever there is indication of the vessel, the suppression pool water volume and temperature shall relief valve operation or. testing which adds heat to the suppression be maintained within the following limits except as specified in pool, the pool temperature shall 3.7. A.2. and 3.5. F.5.
be continually monitored and also observed and logged every 5-3 a.
Minimum water volume - 87,650 ft minutes until the heat addition t
is terminated.
b.
Maximum water volume - 91,000 ft
- c. Whenever there is indication of c.
Maximum suppression pool temperature relief valve operation with the k
during normal power operation - 90 F.
temperature of the suppression For 45 days, commencing July 16, 1981, pool reaching 160 F or more and the suppression pool temperature may the primary coolant system pres-be increased to 95 whenever the sure greater than 200 psig, an external visual examination of river water temgerature cannot be main-the suppression chamber shall tained below 90 F.
be conducted before resuming 4
d.
During testing which adds heat to power operation.
{
the suppression pool, the water temperature shall not exceed 10 F
- d. A visual inspection of the above the normal power operation suppression chamber interior, limit specified in c. above.
In including water line regions, connection with such testing, the shall be made at each major pool temperature must be redt.ced to refueling outage.
below the normal power operation limit specified in c. above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e.
The reactor shall be scrammed from any operating condition if the pool temperature reaches 110 F.
Power operation shall not be resumed until the pool temperature is reduced below the normal power ope ration limit specif Led in c.
above.
8107290040 810716 PDR ADOCK 05000298 9_
MoTL m
GENER AL Q ELECTRIC
'""^""' " ^ "
SERVICE ENGINEERING GENERAL ELECTRIC COMPANY SWANSON BL DG. SUITE 122.8401 WEST DODGE ROAo DIV1SION OMAHA NEBRASKA 68114. Phone 2402) 399-6249 G-HP-1-78 July 16, 1931 Mr. J.fl. Pilant Director of Licensing and Quality Assurance Cooper Nuclear Station Nebraska Public Power District P.O. Box 499 Columbus, Nebraska 68601
SUBJECT:
RESULTS OF SUPPRESSION POOL TEliPERATURE ANALYSIS FOR COOPER
Dear Mr. Pilant:
In response to your inquiry we have perfonned a suppression pool tempera-ture analysis for the Cooper Nuclear Power Station. Attached is a table of preliminary results from the analysis.
For all cases, an initial supgression pool temperature at normal power operation is assumed to be 95 F.
The case with the highest calculated local pool temperature is Case 2A (reactor rapid depressurization at iso-lated hot shutdown with one RHR loop available).
The maximum local pool g
temperature of 199 F is compared to the present limit of 200F specified in NUREG-0661.
Verified results of maximum local pool temperatures are not yet available for Case lA and Case 3B.
However, the maximum local pool temperatures for these cases are not expected to exceed Case 2A for the following reasons:
- 1) Case 1 A (SORV at Power and one RHR Loop Failure) has only one RHR loop available for heat transfer and pool mixing as in Case 2A.
Thus local to bulk pool temperature differences between Case l A and Case 2A are similar. However, the main condenser is available as an extra heat sink for the reactor vessel for Case 1 A, thus re-ducing its maximum bulk pool temperat ure relative to Case 2A.
- 2) Case 3B (SBA-Shutdown Cooling Failure) has 2 RHR loops available which provides very efficient pool heat transfer and mixing.
This in turn results in low bulk to local pool temperature differences.
The maximum local pool temperature is not expected to be above 190 F for this case.
GENER AL Q ELECTRIC G-HP-1-78 J.M. Pilant Page 2 Therefore, with an initial pool temperature of 95 F, preliminary suppression pool temperature analysis resul+.s show that local pool temperatures are below the specified pool temperature limit of 200 F.
If you have any questions on this matter, please contact me.
Very r y rs,
.fk Lube Gervice Supervisor-r;uclear RHK:JFK:jww Attachment cc:
L.C. Lessor /w. att.
W. Rushton /w. att.
L. _
.... = _ _ _ _ _ - _ _ _ _ _ = _ _ _
p.
l SUFNARY OF RESULTS COOPER P0OL TEMPERATURE RESPONSE (PRELIMINARY)
Initial Pool Temperatue = 95 F 1
- of SRV's Maximum Maximum Bulk Maximum (OF)
Case #
Event fianually Opened Cooldown Rate (OF/Hr)
Pool Temperature (UF) local Pool Temperature 1A SORV at Power 2
995+
169 1 RHR Loop 1B SORV at Power, 1
503 170 196 Sparious Iso-lation 2 RHR Loops 2A Rapid Depres-5 900 172 199 surization at Isolated Hot Shutdown 1 RHR Loop 2B SORV at Isolated 1
503 161 183 Hot Standby 2 RHR Loops 2C Normal Depres-5 100 171 189 surization at Isolated Hot Shutdown 2 RHR Loops 3A SBA-Accident !" ode 6 (ADS) 4600 171 195 1 RHR Loop 3B SBA-Shutdown 5
100 170 Cooling Failure 2 RHR Loops
+Where bypass valves open to help depressurize RPV
-