ML17326B416
| ML17326B416 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/09/1988 |
| From: | AMERICAN ELECTRIC POWER SERVICE CORP. |
| To: | |
| Shared Package | |
| ML17326B415 | List: |
| References | |
| NUDOCS 8808160161 | |
| Download: ML17326B416 (21) | |
Text
b.
Surveillance intervals speci.fied in Saccion XT. of the ASME Boiler and Pressure Vessel Code and applicable Addenda f'r tha inservice inspection and testing activities required by che ASME B~er and Pressure Vessel Coda and applicable Addenda snail be applicable as follovs in these TechnicaL Specifications:
ASME Boil.er and Pressure Vassal Coda and applicable Addenda cerminology for inservica
"'o and ca t'"
c 'ce"'
'~aekly Monthly Quarterly or evarv 3 months Samiannua' r or era. r 6 monchs Year y or annual.v Ac l.east once per 7 days Ac least once per 31 days Ac lease once per 92 days Ac 'east once per 184 days Ac least once per 366 days The provis'ons of Speci.icac'on 4.0.2 are applicable co the above required:raquancias "or performing inservica inspec" i.on and cescing acti r ='as.
Performance o=
che above inservice
'nspeccion and casting acciviti.as snail be 'n addition co other specified Surviellanca Requirements.
clothing i.n the ASMK Boiler and Pressure Vessel Code shal.l be construed co supersede cha raqui amen=s of any Technical Specification.
4.0.6 By speci.fic reference co this sect'on, "hose surveillances which must be performed on or before July 31,
- 1987, and are designated as 18-month surveillances (or required as outage-related surveillances) may hy delayed until che and of the Cycle 9-10 refueling outage (currently schedul.ed co begin during cha second
'uarter of 1987).
For these specific surveillances under ch's secci.on, the specified time 'ncarval.s raqui.red by Specificat'on 4.0.2 vilL be decermined vich che nev inic'ation data escabl'shed by tha surveiLl.ance date during cha Unit 1 l987 refueling outage.
4.0.7 By '.speci;fic reference to this specification, thos'e surveillances which must be performed on or before April 1, 1989, may be delayed until the end of the Cycle 10-11 refueling outage (currently scheduled to begin during the latter part of the first quarter of 1989.)
For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1989 refueling outage.
88081,60161 880800>15 PDR ADOCQ 05000315 P
D. C. Cook - Unit 1 amendment No,
3/4.3 INSTRUMENTATIQN 3 4 3
1 REACTQR TRIP SYSTEM(
INSTRUMENTATION LIMITINt3 CQNQITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrument~
channels and interlocks of Table 3.3-1 shall be OPERABLE, with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE RECUIRcvENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstra.ed OPERABLE by the performance of'he CHANNEL CHECK, CHANNEL CAL[BRATION and CHANNEL FUNCTIONAL TEST operations for the NODES and at the freouenc:es shown in Table 4.3-1,+
4.3.1.1.2 he logic f'r the interlocks snail be demonstra:ed QPEP~3LE prior.o eacn reactor startup unless per'".rmed during tne preceding g2 days.
The tata) inter lock function shall oe demonstrated OpcR"BLE at least once per IB months during CHANNEL C;L[BRATION testing of each channel arfec:ed by inter lock operation.
4,3.1.1,3 The REACTOR TRIP SYSTEM RESPQNSc, T[HE'f each reactor trio unction shall be demonstrated to be within its limit at least :nce oer 18 months.
each test shall include at least one logic train sucn that both logic trains are tested at least once per 36 months and one channel "er funCtiOn SuCn that all ChannelS are teS:ed at leaSt OnCe eVery N
times 18 months where N is the total number of redundant channels in a
specific reactor trip func:ion as shown in the "Total No. of "hannels" column of'able 3.3-1.
The provisions of Soecification 4.0.6 are applicable.
+
The provisions of Specification 4.0.7 are applicable.
Q.
C.
C"QK-N.-
3/4 3-1 Amendment lo
TABLE 4.3-1 AoO pq w4 FUNCTIONAL UNIT 1.
Manual Reactor Trip A. Shunt Trip Function B. Undervoltage Trip Function CHANNEL CHECK N.A.
N.A.
CHANNEL CALIBRATION N.A.
N.A.
CHANNEL FUNCTIONAL TEST S/U(1) (10)
S/U(1) (10)
MODES IN NHXCH SURVEILLANCE RE UIRED 3* 4* 5*
1,2,3*,4*,5*
2.
Power Range, Neutron Flux D(2,8),M(3,8)
M and 8/U(1}
1, 2 and * ~
and Q(6,8) 3.
Power Range, Neutron Flux, High Positive Rate 4.
Power Range, Neutron Flux(
High Negative Rate 5.
Intermediate
- Range, Neutron Flux N.A.
N.A.
R (6)
R (6)
R(6,8)
S/U (1) 1, 2
1, 2
1, 2and+
6.
Source
- Range, Neutron Flux R(6,8)
+ **
7.
Overtemperature hT S
R(9)
G.
Overpower hT S
R(9)
M(8) and S/U (1) 2(7) ( 3(7) I 4 and 5
2 1,
2 P4 t40 9.
Pressurizer Pressure Low
- 10. Pressurizer Pressure High ll. Pressurizer Hater LevelHigh
- 12. Loss of Flow-Single Loop R(8) 1, 2
1(
2 1(
2 The provisions of Specification 4.0.6 are applicable.
- The provisions of Specification 4.0.7 are applicable.
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INSTRUMENTATION 3/4.3.2 EHGIHEEREO SAF'ETY FEATURE ACTUATION SYSTEH INSTRIPfENTATION LIMITIHG COHOITIOH FOR OPERATION 3.3.2.1 The Engineered Safety Feature ACtuatiOn $yStan (ESFAS) inSt tion channels and interlocks shown in Table 3.3 3 shall be OPERABLE with their trip setpoints set consistent with the vaIues shown in the Trip Setpoint co1umn of Table 3.3-4 and with RESPONSE TINES as shown in Tab1e 3.3-5.
APPL I CABILITY:
As shown in Ta bl e 3. 3-3.
ACTION:
a.
Wi th an ESFAS instrumentation channel trip setpoint less conserva-tive tnan the value shown in the Allowable Values column of Table 3.3-4, decla.-e
.he channel inoperable and apply the applicable ACTIOH requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint ad)usted consistent with tne Trip;Setooint value.
b.
Qi th an ESF45 inatrumentatiOn Channel inOperable.,
take the ACTION sno~n in zoic 3.3-3.
SURV "LLAHCE REQLI IREh EHTS
~ 4.3. 2. 1. 1 Each ESFAS instrumentation channel shall be 'demonstrated OPERABLE by the performance of the CHANNEL CNECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations fox zhe NODES and at rhe frequencies shown in Table 4.3-2.+
4.3. 2,1. 2 The logic for the interlocks shall be demonstrated OPERABLE duri ng the automatic actuation logic test.
The total interlock function shal'I be dmaonstrated ooERASLE at least onoe oer 18 months during citaNNEL CALIBRATION testing of each channel affected by interlock operation"'" +
4.3.2.1,3 The KHGINEEREQ SAFETY FEATURKS RESPONSE TINE of each ESFAS function sha11 be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function sucn that all channels are tested at least once per N times 18 nonttiS where H iS tne tOtal number Of redundant Channe1S in a SpeCifiC ESFAS function as shown in the "Total No. of Channels" Column of Tab1e 3.3 3.
m m The provxsxons of Specxfxcarxon 4.0.6 are applicable.
+ The rbrovisions of Specification 4.0.7 are applicable.
0.
C.
COOK-UNIT 1
hmendisenr Ho.
TABLE 4..3-.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS OOO I
Q I
FUNCTIONAL UNIT CHANNEL CHECK 1.
SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS a.
Manual Initiation N.A.
b.
Automatic Actuation Logic N.A.
c.
Containment Pressure-High S
d.
Pressurizer Pressure Low S
e.
Differential Pressure Between Steam LinesHigh f.
Steam Flow in Two Steam LinesHigh Coincident with T
Low;Low or Steam Line PM%sure Low CHANNEL CALIBRATION N.A.
N.A.
CHANNEL FUNCTIONAL TEST M(1)
M(2)
M(3)
MODES IN WHICH SURVEILLANCE RE UI ED 1, 2, 3, 4
1, 2, 3,
4 1,
2(
3 1( 2, 3
1, 2, 3
li 2s 3
2.
Manual Initiation N.A.
b.
Automatic Actuation Logic N.A.
c.
Containment Pressure High-S High N.A.
N.A M(1)
M(2)
M(3) 4 2r 3t 4
1, 2, 3
The provisions of Specification 4.0.6 are applicable.
- The provisions of Specification 4.0.7 are applicable.
TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Aoo I
FUNCTIONAL UNIT 4.
STEAM LINE ISOLATION CHANNEL CHECK CHANNEL CALIBRATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE a.
Manual b.
Automatic Actuation Logic c.
Containment Pressure High-High'.
Steam Flow in Two Steam LinesHigh Coincident with T
Low-Low PNRsure Low N.A.
N.A.
N.A.
N.A.
R+
M(1)
M(2)
M(3) 1, 2, 3
1, 2,
3 1,
2, 3
1, 2, 3
5.
TURBINE TRIP AND FEEDWATER ISOLATION a.
Steam Generator Water S
LevelHigh-High 6.
MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS 1, 2, 3
a.
Steam Generator Water S
LevelLow-Low 1,
2, 3
O b.
4 kv Bus Loss of Voltage c.
Safety Injection d.
Loss of Main Feed Pumps N.A.
N-A.
N.A.
N.A.
M(2)
R+
1, 2,
3 1,
2 The provisions of Specification 4.0.6 are applicable. "
- The provisions of Specification 4.0.7 are applicable.
If)STRUt<ENT%TION POST-ACC IOEt(T I t/STRUt]Et(TAT ION LIIIITIlIGCO')OITIOtl FOR OPERATION 3,3,3.8 The post-accident monitorinp instrumentation channels shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY:
t10OES 1, 2, and 3, ACTIOII:
he Mith the number of OPERABLE post-accident monitorino channels less than required by Table 3.3-11, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTOOtlN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURYEILLAttCE REOUIR t1EtlTS 4.3.3.8 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHAtNEL CHECK and CHAtltJEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
- The provisions of Speci@cation 4.0.7 are applicable.
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Coor, - WIT 1
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3I4 3-54 Amendmont No 4>
POST-hCCIDENT MONITORING INSTAUHENThTION SURVEILIhNCE R UIREHENTS n
IHSTRUHEHT n
8 1.
Containaent Pressure 2.
Reactor Coolant Outlet Teaperature
- T (Mida Range)
HOT Q
3.
Reactor Coolant Inlot Teaperature
- T (Mido Range)
COLD 4.
Reactor'oolant Pressure
- Mide Range 5.
Pressurizer Mater Level 6.
Steaa Line Pressure Steaa Generator Mater Level - Narrow Range RMST Mater Level CHhNNEL CHECK H
CllhNNEL ChLIBRhTION R*
a 9.
iO:
an 11.
12.
13.
15.
16.
17.
Buric hcid Tank Solution Level huxiliary Feedwater Flow Rate Reactor Coolant Systea Subcooling Hargin Honitor PORV Position Indicator - Liait Switches PORV Block Valve Position Indicator - Liait Switches Safety Valvo Position Indicator - hcoustic Honitor Incore Theraocouples (Core Exit Theraocouples)
Reactor Coolant Inventory Tracking Systea (Reactor Vessel Level Indication)
Containaent Suap Level*+
Containaent Mater Level**
H(2)
R*
R(1)
R(3)
(1) 'artial range channel calibration for sensor to be perforaed below P-12 in MODE 3.
(2)
Mith one train of Reactor Vessel Level Indication inoperable, Subcooling Hargin Indication and Core Ex t p
Theraocouples aay be used to erfora a Q a
e, coo ng arg n n ication and Core Exit OPERhBLE.
o per ore a QNHNEL CHECK to verify the reaaining Reactor Vessel ndication train (3)
Coapletion of channel calibration for sensors to b o
sensors to e porforaed below P-12 in HODE 3.
- The provisions of Specification 4.0.6 are appli bl app ca o ~
The requireaents for these instruaents will beco e
rep ace an ecoae operational.
The schedule for ecoae effoctiva after the level transaitters are aodified or in the Bases.
u e or aodification or raplaceaent of the transaittors is described gnen~nt Ho. ypy., lip (Effective before start up following the refueling outage currently scheduled in 8(89}
+The provisions of Specification 4.0.7 are applicable.
CO Sb V
C R
"AGENTS Continued>
shall be consti-uted o= one base,e each from Radial Rows',
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 i.s 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 mini.mum total ice condenser ice wei.ght 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,*
3.
Verifying, by a visual inspection of at lease 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 i.nches.
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.*
Co 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 i.ce 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 Specifi.cation 4.0.,7 are applicable.
D.
C.
COOK - UNIT 1 3/4 6-27 Amendment No.
P
CM C
COND "f 00 Y<ITTNG CQN I
'ON OP.
OP 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPEPASLE.
Pith one or more ice condenser doors open or othervise inoperable, PQ'~'ZR OPERATION may continue for up to 14 days provided the ice. bed temperature is monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the maximum ace bed temperature 0
~ is maintained
< 27 F; othervise, restore the doors to their 'closed positions or OPERABLE status (as applicable) Within 4S hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDORY with n the.
'following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C RE 4.6.5.3.1 Inlet Doors
- Ice condenser inlet doors shall be:
& ~
Continuously monitored and determined closed by the inlet door position monitoring system, and b.
Demonstrated OPERABLE during shutdown at least once per 9 months by 1.
Verifying that the torque required to initially open each door is < 675 inch pounds.
2.
Verifying that opening of each door is not impaired by ice, frost or debris.
3.
Testing a sample of at least 50% of the doors and verifying that the torque required to open each door is less than 195 inch-pounds
@hen the door is 40 degrees open.
This torque is defined as the "door opening torque" and is equal to the nominal door torque plus a frictional "The provisions of Specification 4.0.I are applicable.
D.
C.
COOK
- UNIT 1 6-30 Amendment No. '
I
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Attachment 3 to AEP:NRC:0967L Description of Ice Condenser Sublimination Calculation
Attachment 3 to AEP:NRC:0967L Page 1
Descri tion of Calculation This section summarizes the calculations done in support of t~
surveillance extension request.
The details of these calculations are available upon request.
A pictorial description of the ice condenser arrangement is provided in Attachment 4.
The ice loss per basket was calculated from the data of the past seven surveillance intervals.
Ice losses per basket per year were calculated for each bay and row-group.
Using small sample statistics, average expected ice loss values at the lower 95 percent confidence level were calculated.
This 'ice loss rate was applied to the "as-left" ice weights of the latest surveillance (March 1988) 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 of ice weights and the results of calculations performed at the lower 95% level.
The best-estimate results are shown for information purposes.
We believe that the lower 95 percent confidence level data provide a suitable basis for regulatory approval of this T/S change request.
Table 1 lists the March 1988 "as-left" average ice basket
- weight, for each bay and the expected weights in April 1989.
All bays except bay 24 are expected to have average basket weights above 1220 pounds at the lower 95 percent confidence level.
Bay 24 is expected to have an average basket weight above 1098 pounds at the 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.l.b.2 and the expected weight in April 1989 at the lower 95 percent confidence level.
All row-groups except Row 8 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 8 Group 3 and Row 9 Group 3 are expected to have average basket weights above 1098 pounds at the lower 95 percent'onfidence level.
Table 3 lists the expected overall ice weight.
As can be seen, the entire ice condenser is expected to have 2,518,128 pounds of ice with at least 95 percent confidence in April 1989, 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.
A weight factor of two was used for Rows 4, 6, and 8 for all groups to incorporate the weights of Rows 3, 5, and 7.
Attachment 3 to AEP:NRC:0967L Page 2
TABLE 1 Average Ice Weights per Basket by Bay
~Ba No.
Average Ice Weight/
Basket As Left March 1988
~lbs.
Expected Ice Weight/
Basket April 1989
~lbs ExpectecL Ice Weight/
Basket Lower 95%
Conf. Level April 1989
~lbs.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 1375 1414 1440 1393 1431 1362 1404 1372 1385 1405 1417 1417 1411 1412 1451 1436 1418 1377 1372 1355 1435 1425 1445 1410 1327 1401 1421 1334 1382 1330 1331 1320 1328 1367 1392 1372 1374
'373 1432 1398 1384 1355 1344 1306 1401 1384 1389 1315 1245 1382 1381 1247 1321 1291 1231 1263 1274 1326 1358 1323 1327 1335 1413 1354 1334 1319 1305 1235 1355 1348 1313 1200
Attachment 3 to AEP:NRC:0967L Page 3
Row No.-
~Gzou No Average Ice Weight/
Basket As Left March 1988
~lbs.
Expected Ice Weight/
Basket April 1989
~lbs.
TABLE 2 Expected Average Ice Weights per Basket by Row-Group Ice Weight/
Basket at Lower 95%
Conf. Level April 1989
~lbs.
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 1416 1438 1417 1451 1453 1483 1364 1363 1374 1408 1441 1383 1378 1373 1342 1392 1448 1393 1359 1368 1361 1426 1417 1452 1323 1331 1317 1376 1419 1348 1329 1325 1275 1326 1368 1283 1307 1278 1273 1394 1366 1422 1270 1283 1244 1336 1400 1319 1283 1273 1206 1252 1288 1166
Attachment 3 to AEP:NRC:0967L Page 4
TABLE 3 Total Ice Weight Expected in April 1989 Based on Average Ice Basket Wei hts Based on Average Ice Basket'eights at the Lower 95%
Confidence Level 2,624,000 2,518,000
i to AEP:NRC:0967L Drawing of Ice Condenser Bay and Row-Group Layout
ICE CONDENSER BAY AND ROM-GROUP CONFIGURATION DONALD C. COOK NUCLEAR PLANT Group 1 - Bays 1-8 Row 1 Group 2
Bays 9-16 IO CRANK WALL STEAM G KNERATO R STEAM GENERATOR l2 l3 PRESSURIZER R EACTOR R EFUELING CANAL l4 l5 Row 9 Group 3
l6 STEAM G KNERATOR STEAM GENERATOR CONTAINMKNT WALL Ia I9 20 2l 22 23 Row 1
Group 3 - Bays 17-24