ML17326B416

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Proposed Tech Specs Reflecting Request for Extension Until Projected Mar 1989 Refueling Outage for Performing Certain Surveillances,Including Revised Table 4.3-2, ESF Actuation Sys Instrumentation Surveillance Requirements.
ML17326B416
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 08/09/1988
From:
AMERICAN ELECTRIC POWER SERVICE CORP.
To:
Shared Package
ML17326B415 List:
References
NUDOCS 8808160161
Download: ML17326B416 (21)
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b. Surveillance intervals speci.fied in Saccion XT. of the ASME Boiler f'r and Pressure Vessel Code and applicable Addenda 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

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'~aekly Ac l.east once per 7 days Monthly Ac least once per 31 days Quarterly or evarv 3 months Ac lease once per 92 days Samiannua' r or era. r 6 monchs Ac 'east once per 184 days Year y or annual.v 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 05000315 PDR ADOCQ P

- Unit amendment No, D. C. Cook 1

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 CHANNEL MODES IN NHXCH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE UIRED oA O

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1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. S/U(1) (10) 3* 4* 5*

w4 B. Undervoltage Trip Function N.A. N.A. S/U(1) (10) 1,2,3*,4*,5*

2. Power Range, Neutron Flux D(2,8),M(3,8) and Q(6,8)

M and 8/U(1} 1, 2 and *

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3. Power Range, Neutron Flux, N.A. R (6) 1, 2 High Positive Rate
4. Power Range, Neutron Flux( N.A. R (6) 1, 2 High Negative Rate
5. Intermediate Range, R(6,8) S/U (1) 1, 2and+

Neutron Flux

6. Source Range, Neutron Flux R(6,8) M(8) and 2(7) ( 3(7) I S/U (1) 4 and 5

+ **

7. Overtemperature hT S R(9) 2 G. Overpower hT S R(9) 1, 2
9. Pressurizer Pressure Low 1, 2
10. Pressurizer Pressure High 1( 2 Hater Level P4 t4 0

ll. Pressurizer High 1( 2

12. Loss of Flow-Single Loop R(8)

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 CAB IL ITY: 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 CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE O

O FUNCTIONAL UNIT CHECK CALIBRATION TEST RE UI ED O

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1. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR Q DRIVEN AUXILIARY FEEDWATER PUMPS I a. Manual Initiation N.A. N.A. M(1) 1, 2, 3, 4
b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3, 4
c. Containment Pressure-High S M(3) 1, 2( 3
d. Pressurizer Pressure Low S 1( 2, 3
e. Differential Pressure 1, 2, 3 Between Steam Lines High
f. Steam Flow Lines in Two Steam High Coincident with li 2s 3 T Low;Low or Steam Line PM%sure Low
2. CONTAINMENT SPRAY
a. Manual Initiation N.A. N.A. M(1) 4
b. Automatic Actuation Logic N.A. N.A M(2) 2r 3t 4
c. Containment Pressure High- S M(3) 1, 2, 3 High 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 A SURVEILLANCE RE UIREMENTS oo CHANNEL MODES IN WHICH I

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST

4. STEAM LINE ISOLATION
a. Manual N.A. N.A. M(1) 1, 2, 3
b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3
c. Containment Pressure M(3) 1, 2, 3 High-High'.

Steam Flow in Two Steam R+ 1, 2, 3 Lines High Coincident with T Low-Low PNRsure Low

5. TURBINE TRIP AND FEEDWATER ISOLATION
a. Steam Generator Water S 1, 2, 3 Level High-High
6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water S 1, 2, 3 Level Low-Low O b. 4 kv Bus 1, 2, 3 Loss of Voltage
c. Safety Injection N.A. N.A. M(2)
d. Loss of Main Feed Pumps N-A. N.A. R+ 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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3I4 3-54 Amendmont No 4>

POST-hCCIDENT MONITORING INSTAUHENThTION SURVEILIhNCE R UIREHENTS CHhNNEL CllhNNEL n

IHSTRUHEHT CHECK ChLI BRhT ION n

8 1. Containaent Pressure H

2. Reactor Coolant Outlet Teaperature - THOT (Mida Range)

Q 3. Reactor Coolant Inlot Teaperature - TCOLD .

(Mido Range)

4. Reactor'oolant Pressure - Mide Range
5. Pressurizer Mater Level R*
6. Steaa Line Pressure Steaa Generator Mater Level - Narrow Range RMST Mater Level a 9. Buric hcid Tank Solution Level iO: huxiliary Feedwater Flow Rate an 11. Reactor Coolant Systea Subcooling Hargin Honitor
12. PORV Position Indicator - Liait Switches
13. PORV Block Valve Position Indicator - Liait Switches Safety Valvo Position Indicator - hcoustic Honitor R*
15. Incore Theraocouples (Core Exit Theraocouples) R(1)
16. Reactor Coolant Inventory Tracking Systea H(2) R(3)

(Reactor Vessel Level Indication)

17. Containaent Suap Level*+

Containaent Mater Level**

(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, arg n Indication coo ng Hargin a e, Subcooling Ex t n ication and Core Exit p Theraocouples aay be used too pererfora ore a QNHNEL Q CHECK to verify the reaaining Reactor Vessel ndication train OPERhBLE.

(3) Coapletion of channel calibration for o sensors to b e porforaed below P-12 in HODE 3.

  • The provisions of Specification 4.0.6 are appli app ca bl o ~
    • The requireaents for these instruaents will beco ecoaee effoctiva after the level transaitters are aodified or rep ace an ecoae operational. The schedule or aodification or raplaceaent of the transaittors is described u e for in the Bases.

before start up following the refueling outage currently scheduled in 8(89}

gnen~nt Ho. ypy., lip (Effective

+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 4, 6, 8 and 9 (or from the same row of an adjacent bay Rows',

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

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is maintained < 27 0 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. '

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Attachment 3 to AEP:NRC:0967L Description of Ice Condenser Sublimination Calculation to AEP:NRC:0967L Page 1 Descri tion of Calculation This section summarizes the calculations done in support of surveillance extension request. The details of these calculations are t~

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 level. percent'onfidence 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.

to AEP:NRC:0967L Page 2 TABLE 1 Average Ice Weights per Basket by Bay ExpectecL Average Ice Weight/

Ice Weight/ Expected Basket Basket Ice Weight/ Lower 95%

As Left Basket Conf. Level March 1988 April 1989 April 1989

~Ba No . ~lbs. ~lbs . ~lbs.

1 1375 1327 1245 2 1414 1401 1382 3 1440 1421 1381 4 1393 1334 1247 5 1431 1382 1321 6 1362 1330 1291 7 1404 1331 1231 8 1372 1320 1263 9 1385 1328 1274 10 1405 1367 1326 11 1417 1392 1358 12 1417 1372 1323 13 1411 1374 1327 14 1412 '373 1335 15 1451 1432 1413 16 1436 1398 1354 17 1418 1384 1334 18 1377 1355 1319 19 1372 1344 1305 20 1355 1306 1235 21 1435 1401 1355 22 1425 1384 1348 23 1445 1389 1313 24 1410 1315 1200 to AEP:NRC:0967L Page 3 TABLE 2 Expected Average Ice Weights per Basket by Row-Group Average Ice Weight/

Ice Weight/ Expected Basket at Basket Ice Weight/ Lower 95%

As Left Basket Conf. Level Row No.- March 1988 April 1989 April 1989

~Gzou No ~lbs. ~lbs. ~lbs .

1-1 1416 1359 1307 1-2 1438 1368 1278 1-3 1417 1361 1273 2-1 1451 1426 1394 2-2 1453 1417 1366 2-3 1483 1452 1422 4-1 1364 1323 1270 4-2 1363 1331 1283 4-3 1374 1317 1244 6-1 1408 1376 1336 6-2 1441 1419 1400 6-3 1383 1348 1319 8-1 1378 1329 1283 8-2 1373 1325 1273 8-3 1342 1275 1206 9-1 1392 1326 1252 9-2 1448 1368 1288 9-3 1393 1283 1166 to AEP:NRC:0967L Page 4 TABLE 3 Total Ice Weight Expected in April 1989 Based on Average Ice Basket'eights Based on Average at the Lower 95%

Ice Basket Wei hts 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 PLANT DONALD C. COOK NUCLEAR Group 1

- Bays 1-8 Row 1 STEAM STEAM G KN ERATO R GENERATOR IO Group 2 CRANK WALL Bays 9-16 l2 R EFUELI NG PRESSURIZER R EACTOR CANAL l3 l4 Row 9 Group 3 l5 STEAM STEAM l6 G KN ERATOR GENERATOR 23 Ia 22 I9 2l Row 1 CONTAI NM KNT 20 WALL Group 3

- Bays 17-24

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