ML17326B285
| ML17326B285 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/10/1987 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17326B284 | List: |
| References | |
| NUDOCS 8702180406 | |
| Download: ML17326B285 (13) | |
Text
ATTACHMENT 2 TO AEP:NRC:0967H REVISED PAGES FOR THE DONALD C.
COOK NUCLEAR PLANT UNIT 1 TECHNICAL SPECIFICATIONS Szaaiaoeoa moaia PDR ADOCN 050003i5 PDR
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INSTRUHENT TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL CHECK CHANNEL CALIBRATION O
1.
Containment Pressure 2.
Reactor Coolant Outlet Temperature - TROT (Wide Range) 3.
Reactor Coolant Inlet Temperature -
TCOLD (Wide Rancge) 4.
Reactor Coolant Pressure - Mide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Harrow Range 8.
RMST Mater Level 9.
Boiic Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Ileactor Coolant System Subcooling Hargin Honitor 12.
PORV Position Indicator - Limit Switches 13.
PORV Block Valve Position Indicator - Limit Switches 14.
Safety Valve Position Indicator - Acoustic Honi tor R
R
- The provisions of Specification 4.0.6 are applicable.
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued At least once per 18 months by:*
1.
Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600"psig.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets axe not restricted by debris and that the sump components (trash racks,
- screens, etc.)
show no evidence of structural distress or abnormal corrosion.
e.
At least once per 18 months, during shutdown, by:*
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:
a)
'entrifugal charging pump b)
, Safety injection pump c)
Residual heat removal pump f.
By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5 at least once per 31 days on a STAGGERED TEST BASIS.
1.
Centrifugal charging pump 2.
Safety Injection pump
> 2405 psig
> 1445 psig 3.
Residual heat removal pump 195 psig g.
By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
The provisions of Specification 4.0.6 are applicable.
D.
C.
COOK - UNIT 1 3/4 5-5 Amendment No.
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued shall be constituted of one basket each from Radial Rows 1, 2, 4, 6,
8 and 9 (or from the same row of an adjacent bay if a basket from a designated row cannot be obtained for weighing) within each bay. If any basket is found to contain less than 1220 pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed.
The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1220 pounds/
basket at a 95% level of confidence.
The ice condenser shall also be subdivided into 3 groups of
- baskets, as follows:
Group 1 - bays 1 through 8, Group 2
bays 9 through 16, and Group 3
- bays 17 through 24.
The minimum average ice weight of the sample baskets from Radial Rows 1, 2, 4, 6,
8 and 9 in each group shall not be less than 1220 pounds/basket at a 95% level of confidence.
The minimum total ice condenser ice weight at a 95% level of confidence shall, be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,371,450 pounds.~
Verifying, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of 3/8 inches.
If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a
representative sample of 20 additional flow passages from the same bay shall be visually inspected.
If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.~
At least once per 40 months by lifting and visually inspecting the accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear,
- cracks, corrosion or other damage.
The ice baskets shall be raised at least 12 feet for this inspection.
The provisions of Specification 4.0.6 are applicable.
D.
C.
COOK - UNIT 1 3/4 6-27 Amendment No.
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ATTACHMENT 3 TO AEP:NRC:0967H DESCRIPTION OF ICE CONDENSER SUBLIMATION CALCULATION
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Attachment 3 to AEP:
RC:0967H Descri tion of Calculation This section summarizes calculations done in support of our surveillance extension request.
The details oE these calculations are available upon request.
The ice loss per basket was calculated from the data of the past five surveillance intervals.
Ice losses per basket per year were calculated for each bay and row-group using small sample "statistics using average expected values and at the lower 95 percent confidence level.
This ice loss rate was applied to the "as-left" ice weights of the latest surveillance (June 1986) for the length of the current surveillance interval, including the extension period (estimated to be thirteen months), for each bay and row-group combination.
These results were then compared to the T/S acceptance criteria.
Results Summar All results are presented in the form of tables providing both a best estimate oE ice weights and the results of calculations performed at the lower 95 percent confidence level.
The best-estimate results are shown fo' inEormation purposes.
We believe that the lower 95 percent confidence level data provide a suitable basis for regulatory approval of this T/S change request. 'he bay and row-group designations are in accordance with information presented in Attachment 4.
Table 1 lists the June 1986 "as-left" average ice basket weight for each bay and the expected weights in July 1987.
All bays except bays 1,
7, and 24 are expected to have average basket weights above 1220 pounds at the lower 95 percent conEidence level.
Bays 1,
7, and 24 are expected to have average basket weights above 1098 pounds at the lower 95 percent confidence level.
Table 2 lists the "as-left" average ice basket weight for each row-group required to be weighed by T/S 4.6.5.1.b.2 and the expected weight in July 1987 at the lower 95 percent confidence level.
All row-groups except Row 1 Group 2, Row 4 Group 3, and Row 9 Group 3 are expected to have average basket weights above 1220 pounds at the lower 95 percent confidence level.
Row 1 Group 2, Row 4 Group 3, and Row 9 Group 3 are expected to have average basket weights above 1098 pounds at the lower 95 percent confidence level.
Table 3 lists the expected overall ice weight.
As can be seen, the entire ice condenser is expected to have 2,545,376 pounds of ice with at least 95 percent confidence in July 1987, well above the 2,371,450 pound limit of T/S 4.6.5.1.b.2.
The total ice weight was calculated using the average of the basket weights calculated for the row-groups at the lower 95 percent confidence level.
The data for Rows 3, 5,
and 7 for all groups was estimated as the average of the two adjacent row groups.
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a Attachment 3 to AEP:
C:0967H TABLE 1 Average Ice Weights per Basket by Bay
~Ba Na.
1 2
3 4"
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 Average Ice Weight/
Basket As Left June 1986
~lb s 1387 1480 1483 1471 1407 1391 1380 1434 1436 1410 1472 1423 1433 1435 1452 1440 1451 1469 1456 1491 1432 1454 1482 1430 Expected Ice Weight/
Basket July 1987
~lbs 1337 1478 1479 1440 1362 1360 1307 1378 1377 1362 1455 1382 1395 1399 1428 1387 1403 1444 1447 1463 1386 1414 1446 1304 Expected Ice Weight/
Basket at Lover 95%
Conf. Level July 1987
~lbs 1202 1471 1468 1391 1277 1304 1155 1287 1302 1300 1420 1319 1321 1353 1401 1326 1329 1386 1431 1413 1318 1369 1296 1134
~ s Attachment 3 to AEP:
C:0967H 0,
TABLE 2 Expected Average Ice Weights per Basket by Row-Group Row No.-
~Gsou No 1-1 1-2 1-3 2-1 2-2 2-3 4-1 4-2 4-3 6-1 6-2 6-3 8-1 8-2 8-3 9-1 9-2 9-3 Average Ice Weight/
Basket As Left June 1986
~lb s 1397 1437 1578 1392 1439 1467 1356 1353 1391 1469 1502 1446 1451 1430
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1441 1447 1484 1450 Expected Ice Weight/
Basket July 1987
~lbs 1328 1349 1539 1359 1394 1427 1300 1308 1315 1447 1487 1413 1395 1377 1376 1409 1403 1335 Ice Weight/
Basket at Lower 95%
Conf. Level July 1987
~lbs.
1250 1212 1430 1312 1314 1384 1224 1236 1206 1419 1462 1366 1332 1292 1263 1351 1291 1162
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Attachment, 3 to AEP: RC:0967H Page 4
TABLE 3 Total Ice Weight Expected in July 1987 Based on Average Ice Basket Wei hts Based on Average IceBasket Weights at the Lower 95%
Confidence Level 2,692,440 2,546,640
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ATTACHMENT 4 TO AEP:NRC:0967H DRAWING OF ICE CONDENSER BAY AND ROW-GROUP LAYOUT
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AEP:NRC:0967H ICE CONDENSER BAY AND ROW-GROUP CONFIGURATION DONALD C.COOK NUCLEAR PLANT
'roup 1
- Bays 1-8 Row 1 IQ STEAM GKNERATOR STKAM GKNKRATQR Group 2
Bays 9-16 CRANK WALL l2 l3 PRESSURIZER REACTOR R EFUKLING CANAL l4 l5 Row 9 Group 3
l6 l7 Ia STEAM GKNERATQR STEAM GENERATOR 22 23 24 CQNTAINMKNT WALL I9 20 2I Row 1
Group 3 - Bays 17-24