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{{#Wiki_filter:ATTACHMENT NO.2 TO AEP:NRC:0659D DONALD C.COOK NUCLEAR PLANT UNIT NO.2 REASONS AND 10 CFR 50.92 JUSTIFICATIONS FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGES Attachment 2 Page For clarity the Unit 2 T/S proposed changes are grouped into several categories. | {{#Wiki_filter:ATTACHMENT NO. 2 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 REASONS AND 10 CFR 50.92 JUSTIFICATIONS FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGES | ||
Many of these changes are to achieve consistency with the Unit 1 T/S and the STS.Page references to these documents are given where appropriate. | |||
A)The purpose of the first group of proposed changes is to make the Unit 2 Action Statements 2 and 6 like the Unit 1 T/S and the STS.Specifically we would like to change the phrase"one additional" to"the inoperable." This change is one that constitutes an additional restriction not presently included in the T/S.Therefore this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.Page | Attachment 2 Page For clarity the Unit 2 T/S proposed changes are grouped into several categories. Many of these changes are to achieve consistency with the Unit 1 T/S and the STS. Page references to these documents are given where appropriate. | ||
A) The purpose of the first group of proposed changes is to make the Unit 2 Action Statements 2 and 6 like the Unit 1 T/S and the STS. Specifically we would like to change the phrase "one additional" to "the inoperable." | |||
This change is one that constitutes an additional restriction not presently included in the T/S. Therefore this change does not involve a significant hazards consideration as defined in 10 CFR 50.92. | |||
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==References:== | ==References:== | ||
Action Statement 2;Unit 2 3/4 3-5 Unit 1 3/4 3-6 STS 3/4 3-7 Action Statement 6;Unit 2 3/4 3-6 Unit 1 3/4 3-7 STS 3/4 3-8 B)The second group of proposed changes to Unit 2 T/S requests an extension to the period of time in which one channel of our solid state protection system can be bypassed for surveillance testing.Specifically, we are requesting the one-hour time limit be extended to two hours in Action Statement 1 and Action Statement 13.The reasons for these changes are the same as those proposed for Unit 1 Category C.Although the changes may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, the results of the change are clearly within all acceptable criteria with respect to the systems specified in the STS.Therefore, we believe that these changes do not involve significant, hazards considerations as defined by 10 CFR 50.92.Page | Action Statement 2; Unit 2 3/4 3-5 Unit 1 3/4 3-6 STS 3/4 3-7 Action Statement 6; Unit 2 3/4 3-6 Unit 1 3/4 3-7 STS 3/4 3-8 B) The second group of proposed changes to Unit 2 T/S requests an extension to the period of time in which one channel of our solid state protection system can be bypassed for surveillance testing. Specifically, we are requesting the one-hour time limit be extended to two hours in Action Statement 1 and Action Statement 13. The reasons for these changes are the same as those proposed for Unit 1 Category C. Although the changes may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, the results of the change are clearly within all acceptable criteria with respect to the systems specified in the STS. Therefore, we believe that these changes do not involve significant, hazards considerations as defined by 10 CFR 50.92. | ||
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==References:== | ==References:== | ||
Action Statement 1;Unit 2 3/4 3-5 STS 3/4 3-9 (Action Statement 12)Action Statement 13;Unit 2 3/4 3-21 STS 3/4 3-29 (Action Statement 14)C)The third proposed change to the Unit 2 T/S is an editorial change to Action Statement 2, part C on page 3/4 3<<5.This change adds a reference clearly defining the specification by which the quadrant power tilt ratio is to be measured.This change is purely administrative in nature and is intended to achieve consistency with the Unit 1 T/S and with the STS.Therefore, we believe this change does not involve significant hazards consideration as defined in 10 CFR 50.92.Page | Action Statement 1; Unit 2 3/4 3-5 STS 3/4 3-9 (Action Statement 12) | ||
Action Statement 13; Unit 2 3/4 3-21 STS 3/4 3-29 (Action Statement 14) | |||
C) The third proposed change to the Unit 2 T/S is an editorial change to Action Statement 2, part C on page 3/4 3<<5. This change adds a reference clearly defining the specification by which the quadrant power tilt ratio is to be measured. This change is purely administrative in nature and is intended to achieve consistency with the Unit 1 T/S and with the STS. | |||
Therefore, we believe this change does not involve significant hazards consideration as defined in 10 CFR 50.92. | |||
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==References:== | ==References:== | ||
Unit 1 3/4 3-6 STS 3/4 3-7 | |||
Attachment 2 Page D) The fourth proposed change to the Unit 2 T/S is a change to Action Statement 16 on page 3/4 3-21. This change updates the T/S regarding the conditions under which operation may proceed with the number of operable channels less than total number of channels. The proposed change will achieve consistency with the STS. Although it is a change which may result in some increase to the probability or consequence of a previously analyzed accident or may reduce in some way a safety margin, the result of the change is clearly within all acceptable criteria with respect to the systems specified in the STS. Therefore, we believe that this change does not involve significant hazard consideration as defined by 10 CFR 50.92. | |||
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==Reference:== | ==Reference:== | ||
STS 3/4 3-29 (Action 17) | |||
ATTACHMENT NO. 3 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 THE PROPOSED REVISIONS TO UNIT NO. 1 TECHNICAL SPECIFICATIONS | |||
3/4, 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM IN TRUMENTATiON LIMIT'.NG CONOITION FOR OPERATION 3.3.1,1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE . | |||
IMES as shown in Table 3.3-2. | |||
APPLICABILITY: As shown in Table 3.3-1. | |||
AC i!QN: | |||
As snown in Table 3.3-1. | |||
5URV E | |||
' LANG E RE".U I R EMENTS 4.3.1.1.1 Each reac"or trip system instrumentation channel shall be demonstra.ed OP RABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNFL FUNCTIONAL TEST operat>ons for ghe gooses end at tne frequencies snown in .able 4.3-1. | |||
m 4.3.1.1.2 The logic for the interlocks shall be demonstrated. OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be deronstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. | |||
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at, leas: once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at Ieas once per 36 months and one channel per func;ion such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1. | |||
: 0. C. COOK-UNIT I 3/4 3-1 Amendment No. | |||
l ABLE 3. 3-2 RLAC'IOR l'RII'YSTL'M INSTRUHENTATION Rl'.SPONSE TIHLS FUNCT IONAI UN I I RLSPONSE T1HE | |||
: 1. Hanual Reactor'riir NOT API'L I CABLE | |||
: 2. I'ower Rarrge, Nr.'utrorr I'lux O. 5 secollds* | |||
: 3. I'ower Rarrge, Neutrorr I lux, Iliglr Vositive Rate NOT A VI'L ICAIILE Power Range, Neutron Flux, lliglr Negative Rate < 0.5 seconds'OT | |||
: 5. Inteorrediate Range, Neutrorr Flux API'L ICAIILE | |||
: 6. Source Rarrge, N<<ut.run I Iux NOT APPL ICAIIIE | |||
/. Overterrrl)erature hT < 6.0 seconds'OT | |||
: 0. Overpower hT Al'VLI CABLE 1.0 seconds flurry | |||
: 9. Vressur iz<<r I'ressure--Low < | |||
: 10. I'ressurizer Vressur e--lliglr < 1.0 seconds ll. Pressurizer Water Level--lliglr NOT AVVI.ICAOLE Neutron d<<tectors are exellll)t lr'olll I'espollse tinre testing. Resporrse tirrre of the neutron signal portion of the channel shall be measured from detector output or input of first electronic component in channel. | |||
0 | |||
TABLE 4.3-1 (Continued) | |||
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. | NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. | ||
(1) | (1) If not performed in previous 7 days. | ||
>2 percent.(3)Compare incore to excore axial imbalance above 15%"of RATED THERtlAL POWER.Recalibrate if absolute difference | (2) Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference > 2 percent. | ||
>3 percent.(4) | (3) Compare incore to excore axial imbalance above 15% "of RATED THERtlAL POWER. Recalibrate if absolute difference > 3 percent. | ||
Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP)setpoint.D.C.COOK-UNIT 1 3/4 3-14 Amendment No. | (4) Manual ESF functional input check every 18 months. | ||
INSTRUMENTATION 3/4.3.2 ENGINEEREQ SAF" I Y FEATUR ACTUATION SYST"M INSTRI | (5) Each train tested every other month. | ||
(6) Neutron detectors may be excluded from CHANNEL CALIBRATION. | |||
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall 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 such tnat all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the"Total No.of Channels" Column of Table 3,3 30 0.C.COOK-UNIT 1 3/4 3-15 Amendment No. | (7) Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint. | ||
TABLE 3.3-3 ENGItfEERED SAFETY FEATURE ACTUATIOtl SYSTBI I tlSTRU!1EtlTATIOfl | D. C. COOK-UNIT 1 3/4 3-14 Amendment No. | ||
ENGINEEREI) | |||
SAFETY FEATURE ACTUA110N SYSTFH INSTRUMENTATION | INSTRUMENTATION 3/4.3.2 ENGINEEREQ SAF" I Y FEATUR ACTUATION SYST"M INSTRI'ENTAT LIMITING CQNOiTION FOR OPERA iON 3.3.2.1 The Engineered Safety Feature Actuation Systen (ESFAS) insttumen a-tion channels and int . locks snown in Table 3.3-3 shall be OPE."-'BLE with their trip setooints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown | ||
I | --in Table 3.3-5. | ||
APPLICAB!LITY; As shown in Table 3.3-3. | |||
ACTION: | |||
II I cJII-II)cJh | : a. IAlith an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERASL= status with the trip setpoint adjusted consistent with the Trip Setpoint value. | ||
ii1 IJtl- | : b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3. | ||
SURVEIL'NCE RENDU'.R"".EN ~ | |||
4.3.2.1.1 Each ESFAS instrumentation channel shall be demons. rated OPERABLE by the pe. formance of the CHANNEL CHECK, CHAI4NEL CALIBRATION and CHAN l- FUNCTiONAL TEST operations zox the MQDEs and at the frequencies shown in Table 4.3-2. | |||
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock -unction shall be demonstrated OPERABLE at least once per 18 months durina CHANNEL CALIBRATiON testing of each channel affected by interlock operation. | |||
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall 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 such tnat all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3,3 30 | |||
: 0. C. COOK-UNIT 1 3/4 3-15 Amendment No. | |||
TABLE 3.3-3 ENGItfEERED SAFETY FEATURE ACTUATIOtl SYSTBI I tlSTRU!1EtlTATIOfl illill l'lUf1 TOTAL NO. CffANtfCI.S ClfAHtlELS APPLICABLE FUNCTIONAL UNIT OF CIIAflfll:LS TO 1 ff IP OI'CIIAOLE NODES ACTIOII SAFETY INJECTION; TURBINE .TRIP, FECDWATER ISOLATION, ArfD HOTOR DRlVE!f f'EEDWATER PUtfPS | |||
: a. tlanua I Initiation 1,2,3,4 | |||
: b. Automatic Actuation 1,2,3,4 13 Logic C. Containment 1,2,3 14" Pressure-lliqh | |||
: d. Pressurizer Pressure Low 1, 2, 38k'8 3!I | |||
: e. Differential 1, 2, Pressure Between Steam Lines - lligh Four Loops 3/s team 1 ine 2/steam line 2/steam line Operating any steam line Tllree Loops 3/operating 1 /steam 2/operating Operating steam line line, any steam line operating 5 tealll 1 lne | |||
TAIII E 3.3-3 (Contirrueri} | |||
ENGINEEREI) SAFETY FEATURE ACTUA110N SYSTFH INSTRUMENTATION Hl N IHUH TOThl. NO. CIIANNELS CIIANNELS Al'Pl I CABLE FUNCTIONAL UNIT OF CIIANNLLS TO TRIP OPERABLE HOOES ACTION | |||
: f. Steam Flow in Two 3lP Steam Lines-lligh Four Loops 2/steam line 1/steam line 1/steam line Operating arry 2 steam 1 irres Ttrree Loops 2/operating I /any I/opera t ing 15 OIrerati>>g stearo li>>e operating steam line steam line CO I NC I BENT Mi lll E I I llf.R T --l.ow-Low avg I our Loops 1 T avrJ | |||
/loop 2 T | |||
, | |||
any 1 T avg any Operati>>g loops loops 3 1trree I.ooirs I T in 1 T in any 15 avg avg avg Operati>>g two operating operating any operating loop loop loops | |||
IAIII.L 3.3-3 (Conti>>ued) | |||
I,.NhltILI'IIEI) SAI:I fY Fl.hfUllf ACI'UATION SYSlfH ItISTIIUHLNTATION Hl N I HUH TOTAL NO. CIIANNELS CIIANNELS APPI. I CAOLf FtINCTIONAL UNI r Ol'IIANtlf.l.S TO TIIIP OI'l:IIAOL f HODES ACTION 0th, COlNCll)ENT MITII Steam Line Pressure-Low Four Loops I I>>'essure/ 2 pressures 1 pressure 1 4* | |||
Operat.ing loop a>>y loops any 3 loops Tl~ree Loops 1 pressure/ 1 pressure 1 pressure 15 Opelat,)ncJ operdt.lncJ in a>>y oper- in any 2 loop ating loop operating loops | |||
: 2. CON fAINHLNI Sl'IIAY | |||
: a. Ha>>ual 1.2,3,4 10 | |||
: b. Au toe>>a t 1 c Ac t ua t, i o>> l. 2,3,4 13 LocJ ) c | |||
: c. Co>>ta i>>ment I'ressure-- 1,2,3 16 II I cJII-II ) cJh | |||
IAULL 3.3-3 Continued FNGINEEREO SAFETY FEATURE ACTUATION SYSTFH INSTRUHENTATION Hl NIHUH TOTAL NO. CHANNELS CHANNELS APPLICAOLCX FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HOOES ACTION | |||
: 4. STEAH LINE ISOLATION | |||
: a. Hanual 1/steam line 1/steam line 1/operating 1, 2, 3 )8 steam line | |||
: b. Au toma t i c Actuation Logic 2 l 2 - 1,2,3 IS ~ | |||
: c. Conta inment Pressure-- 1,2,3 16 ii1 IJtl-III IJIl = | |||
: d. Steam Flow in Two 2 Steam L i ties- High Four Loops 2/steam line l/steam line 1/steam line )4* | |||
Operating any 2 steam lines | |||
'iiree Loops 2/operating )"']any 1/operating )5 OiIerating steam line operating steam line steam line | |||
TABLE 3.3-3 Continued EHGIHEERED SAFETY FEATURE ACTUATIOH SYSTEM IHSTRUMEHTATIOH I | |||
MI ttIMUM TOTAL HO. CtNHHELS CHAHHELS APPLICABLE FUNCTIONAL UNIT OF C}tAHttELS TO TRIP OPERABLE MODES ACTION COINCIDENT WITH EITHER T --Low-Low 1, 2, 3" avg Four Loops 1 Tav /loop 2T any 1 T avg any 14* | |||
Operating loops 3 loops Three Loops 1 Tav /oper- avg in 1 T in any 15 Operating operating ating loop any operating two loop loops OR, COINCIDENT WITH 3PP Steam Line Pressure-Low Four Loops 1 pressure/ 2 pressures 1 pressure 14* | |||
Operating loop any loops any 3 loops Three Loops 1 pressure/ 1 pressure 1 pressure in 15 Operating operating loop in any oper- any 2 oper-ating loop ating loops | |||
: 5. 'CARBINE TRIP 5 FEE DMATER I SOLATIOH | |||
: a. Steam Generator 3/loop 2/loop in 2/loop in 1, 2, 3 14* | |||
Mater Level any oper- each oper-High-High ating loop -ating loop. | |||
TABLE 3.3-3 (Continued) | |||
TABLE NOTATION | |||
¹Trip function may be bypassed in this MODE below P-ll. | |||
¹¹Trip function may be bypassed in this MODE below P-12. | |||
¹¹¹The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode. | |||
*The provision of Specification 3.0.4 are not applicable. | |||
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. | |||
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours; however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specif'cation 4.3.2.1.1. | |||
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
D. C. COOK-UNIT 1 3/4 3-22 Amendment No. | |||
TABLE 3.3-3 (Continued) | TABLE 3.3-3 (Continued) | ||
ACTION 17 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed. | |||
ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. | |||
ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | |||
a ~ The inoperable channel is placed in the tripped condition within 1 hour. | |||
: b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1. | |||
ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels >1915 manual block of safety psig ~ injection actuation on low pressurizer pressure. | |||
ACTION 17 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | P-12 With 3 of 4 T channels P-12 prevents or defeats 544oF, manual block of safety injection actuation high steam line flow and low steam line pressure. | ||
a~The inoperable channel is placed in the tripped condition within 1 hour.b.The Minimum Channels OPERABLE requirements is met;however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer | With 2 of 4 T channels Allows manual block of 540oF ~ safety injection actuation on high steam line flow and low steam line pressure. | ||
ATTACHMENT NO.4 TO AEP:NRC:0659D DONALD C.COOK NUCLEAR PLANT UNIT NO.2 THE PROPOSED REVISIONS TO UNIT NO.2 TECHNICAL SPECIFICATIONS TABLE 3.3-1 (Continued TABLE NOTATION Kith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal. | Causes steam line isolation on high steam flow. Affects steam dump blocks. | ||
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop.shall be placed in the tripped condition. | D. C. COOK-UNIT 1 3/4 3-23 Amendment No. | ||
ATTACHMENT NO. 4 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 THE PROPOSED REVISIONS TO UNIT NO. 2 TECHNICAL SPECIFICATIONS | |||
TABLE 3.3-1 (Continued TABLE NOTATION Kith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal. | |||
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop. shall be placed in the tripped condition. | |||
SThe provisions of Specification 3.0.4 are not applicable. | SThe provisions of Specification 3.0.4 are not applicable. | ||
ftHigh voltage to detector may be de-energized above P-6.ACTION STATEMENTS ACTION 1-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours;however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | ftHigh voltage to detector may be de-energized above P-6. | ||
ACTION 2-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | ||
a.The inonerable channel is placed in the tripped condition within 1 hour.b.The Minimum Channels OPERABLE requirement is met;however, the inoperable channel may be bypassed for up to 2 hours for surveillance testi ng per Specification 4.3.1.1.1. | ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | ||
c.Either, THERMAL POWER is restricted to~75%of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to~85%of RATED THERMAL POWER within 4 hours;or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.c..ACTION 3-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: D.C.COOK-UNIT 2 3/4 3-5 Amendment No. | : a. The inonerable channel is placed in the tripped condition within 1 hour. | ||
, 4HLE 3.3-1'.Con t inued)Below p 6, restore the inooerable channel to OPERABLE status prior o increasing HER."AL CMER above:he~-6 Setpoint.b.Above rr-5 but below="i of~ATED:HERBAL PCMER, res.ore the incoerable channel=o CPERAHLE status prior to increasing THERMAL POWER above 5."i of MATEO THERMAL POWER.c.Above S'.of RATED THERMAL POWER, POWER OPERAT'.ON may continue.AC, IQN 4-With:he number of channels OPERABLE one less than required by the.'4linimum Channels GPERA8LE reauirement and with the ,HERBAL POWER level: | : b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testi ng per Specification 4.3.1.1.1. | ||
AC,:"ON 6-Mith the number of OPERABL=channels one less than the Total'fumber of Channels, ARTUP and/or POWER OPERATICt~ay proceed provided the following condit ons are satisfied: | : c. Either, THERMAL POWER is restricted to ~ 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to ~ 85% of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.c.. | ||
a..ne inooerable channel is placed in".he triooed condition within 1 hour.he Minimum Channels CP RABLE reouiremer.t is met;however, the inoperable channel may be bypassed ror uo to 2 hours for surveillance testing of the other channels per Specification 4.3.1.1.1. | ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: | ||
AC-.:QN 7-With the number of OPERABLE channels one less than:he.otal Number of Channels, STARTUP and/or POWER OPERA ION may oroceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tr.'oped condition within | D. C. COOK - UNIT 2 3/4 3-5 Amendment No. | ||
TABLE 3.3-3 Continued) | |||
TABLE NOTATION Trip function may be bypassed in this MODE below P-11.Trip function may be bypassed in this MODE below P-12.The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.*The provision of Specification 3.0.4 are not applicable. | , 4HLE 3. 3-1 '.Con t inued) | ||
ACTION 13 | Below p 6, restore the inooerable channel to OPERABLE status prior o increasing HER."AL CMER above :he ~-6 Setpoint. | ||
With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed unti 1 performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour.With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours;however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | : b. Above rr-5 but below ="i of ~ATED :HERBAL PCMER, res.ore the incoerable channel =o CPERAHLE status prior to increasing THERMAL POWER above 5."i of MATEO THERMAL POWER. | ||
D.C.COOK-UNIT 2 3/4 3-21 Amendment No. | : c. Above S'. of RATED THERMAL POWER, POWER OPERAT'.ON may continue. | ||
ATTACHMENT NO.3 TO AEP:NRC:0659D DONALD C.COOK NUCLEAR PLANT UNIT NO.1 THE PROPOSED REVISIONS TO UNIT NO.1 TECHNICAL SPECIFICATIONS 8504050157 850329 PDR ADOCK 05000315 P PDR 0 L J) 3/4.3 INSTRUMENTATION 3/4,3.1 REACTOR TRIP SYST"M INTRUMENTAT:ON LIMITING CONDITION FOR OPERATION 3.3,1.1 As a m'nimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OP RABL with RESPONSE TIMES as shown in Table 3.3-2.APPLICABILITY: | AC, IQN 4 - With :he number of channels OPERABLE one less than required by the .'4linimum Channels GPERA8LE reauirement and with the | ||
As shown in Table 3.3-1.AC i!QN: As shown in Table 3.3-1.SUR'/E;Li ANCE RE"UiRcMENTS 4.3.1.1.1-Each reac or trip system instrumentation channel shall be demonstra.ed OP BABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNC IONAL TEST operations for the Moops at tne frequencies snown in able 4.3-1.4.3.1.1.2 The logic for the interlocks shall be demonstrated. | ,HERBAL POWER level: | ||
OPeRABLE prior to each reactor star tup unless performed during the preceding 92 days.The total interlock function shall be demonstrated OPERABLE't least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. | 3elow P-6, restore the nooerable channel to OPERAHLE status pr .or to increasing .HERBAL POWER above the P-6 Setpoint. | ||
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TiNE of each reactor trip function sha11 be demonstrated to be within its limit at, least once per 18 months.Each test shall include at least one logic train such tha.both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the"Total No.of Channels" column of Table 3.3-1.0.C.COOK-UN I T 1 3/4 3-1 Amendmene go. | : b. Above P-6, ooeration may continue. | ||
1'ABLE 3.3-2 RL'AC IOR 1 R I I'YSTLH INSTRUHL' | ACi;ON 6 - With the numoer of channels OPERABLE one less than required by he Min mum Channels ~".PERAHLE requirement, verify compliance with the SriUTi QWN ~ARCsi",l reouirements of Speci "ication 3.1.1.1 or 3.1.1.2, as aoolicable, with..n 1 hour and at least once oer 12 hours thereafter. | ||
UNI I RLSPONSE TIHE 1.Hanual Reactor Trip | AC,:"ON 6 - Mith the number of OPERABL= channels one less than the Total 'fumber of Channels, ARTUP and/or POWER OPERATICt | ||
~ay proceed provided the following condit ons are satisfied: | |||
: a. .ne inooerable channel is placed in ".he triooed condition within 1 hour. | |||
he Minimum Channels CP RABLE reouiremer.t is met; however, the inoperable channel may be bypassed ror uo to 2 hours for surveillance testing of the other channels per Specification 4.3.1.1.1. | |||
AC-.:QN 7 - With the number of OPERABLE channels one less than :he | |||
.otal Number of Channels, STARTUP and/or POWER OPERA ION may oroceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tr.'oped condition within hour . 1 | |||
: 0. C. COOK - UNIT 2 3/4 3-6 Amendment No. | |||
TABLE 3.3-3 Continued) | |||
TABLE NOTATION Trip function may be bypassed in this MODE below P-11. | |||
Trip function may be bypassed in this MODE below P-12. | |||
The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode. | |||
* The provision of Specification 3.0.4 are not applicable. | |||
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours and in COLD SHUTDOWN. wi thin the fol lowing 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed unti 1 performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. | |||
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours; however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2. 1. 1. | |||
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for su; veillance testing per Specification 4.3.2.1.1. | |||
D. C. COOK - UNIT 2 3/4 3-21 Amendment No. | |||
ATTACHMENT NO. 3 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 THE PROPOSED REVISIONS TO UNIT NO. 1 TECHNICAL SPECIFICATIONS 8504050157 850329 PDR ADOCK 05000315 P PDR | |||
0 L J | |||
) | |||
3/4. 3 INSTRUMENTATION 3/4,3.1 REACTOR TRIP SYST"M INTRUMENTAT:ON LIMITING CONDITION FOR OPERATION 3.3,1.1 As a m'nimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OP RABL with RESPONSE TIMES as shown in Table 3.3-2. | |||
APPLICABILITY: As shown in Table 3.3-1. | |||
AC i!QN: | |||
As shown in Table 3. 3-1. | |||
SUR'/E;Li ANCE RE"UiRcMENTS 4.3.1.1.1 - | |||
Each reac or trip system instrumentation channel shall be demonstra.ed OP BABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNC IONAL TEST operations for the Moops at tne frequencies snown in able 4.3-1. | |||
4.3.1.1.2 The logic for the interlocks shall be demonstrated. OPeRABLE prior to each reactor star tup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE't least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. | |||
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TiNE of each reactor trip function sha11 be demonstrated to be within its limit at, least once per 18 months. Each test shall include at least one logic train such tha. | |||
both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1. | |||
: 0. C. COOK-UN I T 1 3/4 3-1 Amendmene go. | |||
1'ABLE 3.3-2 RL'AC IOR 1 R I I'YSTLH INSTRUHL'NTATION RLSVON'SL TIHLS FUNCTIONAI. UNI I RLSPONSE TIHE | |||
: 1. Hanual Reactor Trip NOT AI'I'LI CAIILE | |||
: 2. I'owens Ra>>ge, Neutro>> I'lux < 0.5 seconds'. | |||
I'ow<<r Ra>>ge, Neutron I Iux, lligli I'os itive Rate NOT AVI'LI CAIILE | |||
: 4. Power Ra>>ge, Neutron .Flux, Iligli N<<gative Rate < 0.6 seconds" | |||
: 5. Inteonediate Range, N<<ut.ro>> I'lux NOT API'L I CAIILE | |||
: 6. Source Ra>>ge, Neutro>> I Iux NOT APPL ICAIII E Over tenq)era ture hI < 6.0 seconds'OT | |||
: 0. Overpower AT Al'VLI CABLE | |||
- | |||
: 9. I'ressu> izer I'ressure--Low 1.0 seconds | |||
: 10. Pressurizer Vressu~ e--ll igl> < 1.0 seco>>ds Pressurizer Water Level--lligl> NOT AVI'I.I CABLE 11. | |||
Neutron d<<tectors are exellli)t trolll lespo>>se tlllle testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel. | |||
0 | |||
TABLE 4.3-1 (Continued) | |||
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. | NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. | ||
(1) | (1) If not performed in previous 7 days. | ||
>2 percent.(3)Compare incore to excore axial imbalance above 15%of RATED THERl1AL POWER.Recalibrate if absolute difference | (2) Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference > 2 percent. | ||
>3 percent.(4) | (3) Compare incore to excore axial imbalance above 15% of RATED THERl1AL POWER. Recalibrate if absolute difference > 3 percent. | ||
(7)-Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP)setpoint.D.C.COOK-UNIT 1 3/4 3-14 Amendment No. | (4) Manual ESF functional input check every 18 months. | ||
(5) Each train tested every other month. | |||
(6) Neutron detectors may be excluded from CHANNEL CALIBRATION. | |||
(7) - Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint. | |||
D. C. COOK-UNIT 1 3/4 3-14 Amendment No. | |||
INSTRUMENTATION 3/4.3.2 ENGINEERE0 SAFE,Y FEATURE AC UATION SYST=M INSTR"," NTAT'.CN LIMITING CONOITION FOR OPERA; ION 3.3,2,1 The Engineered Safety Feature Actuation System (ESFAS) instrumen a-tion channels and inte. locks shown in Table 3.3-3 shall be OPERABLE with their trip setooints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5. | |||
APPLICAB!LITY: As shown in Table 3.3-3. | |||
ACTION: | |||
: a. With an ESFAS instrumentation channel trip setpoint less corse.va-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OpERASLE status wi th the trip setpoint adjusted consistent with the Trip Setoint value. | |||
: b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3. | |||
SURVEIL'NCE REOUIRE"ENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERASLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODEs and at the frequencies shown in Table 4.3-2. | |||
4.3.2.1.2 The logic for the interlocks shall be denonstrated OPERABLE during the automatic actuation logic test. The total interlock funct'on shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. | |||
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall 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 such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3~3 3 ~ | |||
: 0. C. COOK-UNIT 1 3/4 3-15 Amendment No. | |||
TABLE 3. 3-3 ENGItlEEREO SAFETY FEATURE ACTUATIOtl SYSTBI ItfSTRUHEtlTATIOll I I I I I I I'fUt1 TOTAL NO. CIIANtlCI.S CllANtlELS APPLICABLE FUtlCTIONAL UNIT Of'llAllllELS TO 1RIP OVERAfJLE HOOES ACTIOtl SAFETY INJ ECTION; TURBINE .TR I P, FEEDWATER ISOLATION, AND HOTOR DR IVEtf I:EEOtCATER PUtlPS | |||
. a. !Ianua I Inil.iation 1,2,3,4 18 | |||
: b. Automatic Actuation 1, 2, 3, 4 13 Logic c Containment 1,2,3 14* | |||
Pressure-lliqh | |||
: d. Pressurizer 1,2,3lt Pressure - Low | |||
: e. Oifferential 1, 2, 3df Pressure Between Steam Lines - lligh Four Loops 3/s team 1 ine 2/steam line 2/steam line 14" Operating any steam line Three Loops 3/operating 1 /steam 2/operating 15 Operating steam line line, any steam line operating steam line | |||
TABI f. 3.3-3 (Continued} | |||
ENGINEEREI) SAFETY FEATURI'. ACTUA1ION SYSTFH IHSTRUHLNTATION n HINIHUH TOTAL HO. CIIAHNEI. S CIIANNELS APPI.ICADLE C3 C) FUNCTIONAL UNIT OF CIIANHEI.S TO TRIP Of'ENABLE HOnI:S ACTION 7C I | |||
: f. Steam Flow in Two Steam Lines-lligh Four Loops 2/sl.earn line 1/steam line 1/steam line 14* | |||
Operating any 2 steam lines Tliree Loops 2/operating I /any 1/opera t ing 15 Operating s team I I ne operating steam line steam line COIHC II)fNT Milli L I I IIER T --l.ow-Low avg I our Loops Operating 1 T,avg | |||
/loop 2 T avg, any 14* | |||
loops 3 loops lhree l.oops fNI in any 1 T in 1 T avg 15 Operating two operating operating any operating loop loop loops Q | |||
Q 9 | |||
6 0 | |||
fhlII.L 3.3-3 (Cr)r)tlrrrred) | |||
, ~ | |||
ltttilNLf'ILff)SAI t fY FI.Aftlltf; ACI'IIATION SYSlfH lNSTIIUHLNTATION n HlNlHIIH TOTAL NO. CIIANNLLS CIIANNf:LS AVPIICAIILE I:IINCTIONAL UNlr t)f CIIANNfl.S TO TltlP OPLItAIILE HOIIES ACTION Olt, COlNCII)KNT WITII S tear)) L ine I'res sure-I. ow | |||
'f:our Loops 1 pr'essure/ ? pressures 1 pressure 14* | |||
Operating 1oop arly 100ps any 3 loops INN TI)ree Loops 1 pressure/ 1 pressure 1 pressure 15 Operating oiler dtillg in ar)y oper- in any 2 loop a tir)g loop operating loops | |||
: 2. CONIAlNHI.NI Sf ftAY L) | |||
: a. Harrua1 1,2,3,4 | |||
: b. Autorr)at fc Actuat.io<< 1, 2, 3, 4 13 Logic | |||
: c. Cor) ta inment f'ressure-- 1,2,3 16 lligl)-lligh R | |||
0 | |||
inULL 3.3-3 Continued FNGINEERED SAFfTY FEATURf ACTUATION SYSTFH INSTRUMENTATION HINIHUH 10TAL NO. CHANNELS CHANNELS AAPCICAOLEX FUNCTIONAL UNIT OF CIIANNELS TO TRIP OPERABLE HOOTS ACTION | |||
: 4. STfAH LINf ISOLATION | |||
: a. Hanual 1/steam line l/steam line 1/operating 1, 2, 3 18 steam line | |||
- | |||
: b. Automatic 2 1 2 1,2,3 Actuation Logic | |||
: c. Containm<<nt Pressure-- 1,2,3 16 lligi>-Iligl) | |||
: d. Steam Flow in Two Steam Lines- lligh Four Loops 2/steam 1 ine 1/s team 1 ine 1/steam 1 ine 14* | |||
Operating any 2 steam 1 ines Tliree Loops 2/operating I /any 1/opera t ing 15 OiIera t ing steam line operating steam line steam line | |||
TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION HIHIHUlh TOTAL HO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UHIT OF CHANNELS TO TRIP OPERABLE NODES llCTI OH COINCIDENT MITH EITHER T --Low-Low avg Four Loops /loop 14* | |||
any 1 T 2 T 1 T any Operating loops 3 loops Three Loops 1 T | |||
/oper-1"'T 'n n 1T avg in any 15 Operating ating loop any operating two operating loop loops OR, COIHCIOEHT WITH Steam Line Pressure-Low | |||
. Four Loops 1 pressur e/ 2 pressures 1 pressure 14* | |||
Operating loop any loops any 3 loops Three Loops 1 pressure/ 1 pressure 1 pressure in Operating operating loop in any oper- any 2 oper-ating loop ating loops | |||
: 5. 'TURBINE TRIP 5 FEEDWATER ISOLATION | |||
: a. Steam Generator 3/loop 2/loop in 2/loop in 1.2,3 14* | |||
Water Level any oper- each oper-High-High ating loop 'ating loop | |||
TABLE 3.3-3 (Continued) | |||
TABLE NOTATION gTrip function may be bypassed in this MODE below P-ll. | |||
55Trip function may be bypassed in this MODE below P-12. | |||
TABLE 3.3-3 (Continued) | PHOThe channel(s) associated with the protective functions derived from the out of service Reactor Coolant L'oop shall be placed in the tripped mode. | ||
TABLE NOTATION gTrip function may be bypassed in this MODE below P-ll.55Trip function may be bypassed in this MODE below P-12.PHOThe channel(s) associated with the protective functions derived from the out of service Reactor Coolant L'oop shall be placed in the tripped mode.*The provision of Specification 3'.4 are not applicable. | *The provision of Specification 3 '.4 are not applicable. | ||
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours;however, one channel may be bypassed for up to 2 hours for surveillance-testing per Specification 4.3.2.1.1. | ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance-testing per Specification 4.3.2.1.1. | ||
ACTION 14 With the number oz OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour.ACTION 15 With a channel associated with an operating loop inoperable, restore 0he inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours;however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specif'cation 4.3.2.1.1. | ACTION 14 With the number oz OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. | ||
ACTION 16'With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met;one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | ACTION 15 With a channel associated with an operating loop inoperable, restore 0he inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours; however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specif'cation 4.3.2.1.1. | ||
D.C.COOK-UNIT 1 3/4 3-22 Amendment No. | ACTION 16 'With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | ||
TABLE 3.3-3 (Continued) | D. C. COOK-UNIT 1 3/4 3-22 Amendment No. | ||
ACTION 17 | |||
a~The inoperable channel is placed in the tripped condition within 1 hour.b.The Minimum Channels OPERABLE requirements is met;however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer | TABLE 3.3-3 (Continued) | ||
ATTACHMENT NO.4 TO AEP:NRC:0659D DONALD C.COOK NUCLEAR PLANT UNIT NO.2 THE PROPOSED REVISIONS TO UNIT NO.2 TECHNICAL SPECIFICATIONS TABLE 3.3-1 (Continued TABLE NOTATION+Mith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal. | ACTION 17 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed. | ||
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop.shall be placed in the tripped condition. | ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. | ||
ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed prov'ded the following conditions are satisfied: | |||
a ~ The inoperable channel is placed in the tripped condition within 1 hour. | |||
: b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1. | |||
ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-ll prevents or defeats pressure channels >1915 manual block of safety pslgi injection actuation on low pressurizer pressure. | |||
P-12 With 3 of 4 T channels P-12 prevents or defeats | |||
> 544'F. manual block of safety injection actuation high steam line flow and low steam line pressure. | |||
With 2 of 4 T channels Allows manual block of | |||
<540oF, safety injection actuation on high steam line flow and low steam line pressure. | |||
Causes steam line isolation on high steam flow. Affects steam dump blocks. | |||
D. C. COOK-UNIT 1 3/4 3-23 Amendment No. | |||
ATTACHMENT NO. 4 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 THE PROPOSED REVISIONS TO UNIT NO. 2 TECHNICAL SPECIFICATIONS | |||
TABLE 3.3-1 (Continued TABLE NOTATION | |||
+Mith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal. | |||
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop. shall be placed in the tripped condition. | |||
8The provisions of Specification 3.0.4 are not applicable. | 8The provisions of Specification 3.0.4 are not applicable. | ||
HHigh voltage to detector may be de-energized above P-6.ACTION STATEMENTS ACTION 1-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours;however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | HHigh voltage to detector may be de-energized above P-6. | ||
ACTION 2-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | ||
a.The inonerable channel is placed in the tripped condition within 1 hour.b.The Minimum Channels OPERABLE requirement is met;however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: | ||
c.Either, THERMAL POWER is restricted to~75%of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to~85K of RATED THERMAL POWER within 4 hours;or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.c.ACTION 3-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: D.C.COOK-UNIT 2 3/4 3-5 Amendment No. | : a. The inonerable channel is placed in the tripped condition within 1 hour . | ||
,ABLE 3.3 1!Continued) a.Below?-6, restore the inoaerabie c.",anne1 to OPERABLE sta us"r',or o increasing HER"AL~OWER above he~-6 Setaoint.b.Above>-6 but below 5"i of?ATEO THERMAL?OWER, res ore the incoerable channel:o OPERABLE status arior a incr eas ng THERMAL POWER above 5,.of MATEO THERMAL?OWER.c.Above"".'l of RATED HERMAL POWER, POWER QPERAT'.ON may continue.AC,IQN 4-Mith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE reauirement and with the THERMAL?OWER 1evel: | : b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1.1. | ||
AC,'.QN 6-Mi h the~umber af OPERABLE channels one less than.he Total Numoer of Channels, STARTUP and/or POWER OPERATION i'ay oraceed provided the following candit';ons are satisfied: | : c. Either, THERMAL POWER is restricted to ~ 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to ~ 85K of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.c. | ||
a..ne inooerabie channel is olaced in he triooed condition within 1 hour.b.'he Minimum Channels t'PERABLE reauiremer,t is met;however, the inoperable channel may be byoasseh for uo to 2 hours for surveillance testing of the other channels per Specification 4.3.l.l.l. | ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: | ||
AC".:QN i-With the number of OPERABLE channels one less than".he ,otal Number of'hannels, STARTVP and/or POWER OPERATiON may oraceed until Performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is Placed in the triooed condition within | D. C. COOK - UNIT 2 3/4 3-5 Amendment No. | ||
TABLE 3.3-3 Continued) | |||
TABLE NOTATION Trip function may be bypassed in this MODE below P-11.Trip function may be bypassed in this MODE below P-12.The channel(s) associated wi th the protective functions derived from the out, of service Reactor Coolant Loop shall be placed in the tripped mode.*The provision of Specification 3.0.4 are not applicable. | ,ABLE 3. 3 1 !Continued) | ||
ACTION 13 | : a. Below?-6, restore the inoaerabie c.",anne1 to OPERABLE sta us "r',or o increasing HER"AL ~OWER above he ~-6 Setaoint. | ||
With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour.With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours;however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | : b. Above >-6 but below 5"i of ?ATEO THERMAL ?OWER, res ore the incoerable channel :o OPERABLE status arior a incr eas ng THERMAL POWER above 5,. of MATEO THERMAL ?OWER. | ||
With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel i s placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met;one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | : c. Above "".'l of RATED HERMAL POWER, POWER QPERAT'.ON may continue. | ||
D.C.COOK-UNIT 2 3/4 3-21 Amendment No.}} | AC,IQN 4 - Mith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE reauirement and with the THERMAL ?OWER 1evel: | ||
3elow ?-6, restore the inooer able channel to OPERABLE status ar.'.or to ir creasing .HER.",AL POWER above the P-6 Setpoint. | |||
: b. Above ?-6, ooerat'.on may continue. | |||
ACT'.ON 5 - Mith the numaer of channels OPERABLE one less t?'an required by he .colin mum Channels OPERABLE requirement, verify compliance wl h he SHUTDOWN ~ARCiIN requirements of Soeci fication 3. 1. 1, 1 or 3.1. 1.2, as aool',cable, with.'n 1 hour and at least once aer 12 hours thereafter. | |||
AC,'.QN 6 - Mi h the ~umber af OPERABLE channels one less than .he Total Numoer of Channels, STARTUP and/or POWER OPERATION i'ay oraceed provided the following candit';ons are satisfied: | |||
: a. .ne inooerabie channel is olaced in he triooed condition within 1 hour. | |||
: b. 'he Minimum Channels t'PERABLE reauiremer,t is met; however, the inoperable channel may be byoasseh for uo to 2 hours for surveillance testing of the other channels per Specification 4.3.l.l.l. | |||
AC".:QN i - With the number of OPERABLE channels one less than ".he | |||
,otal Number of'hannels, STARTVP and/or POWER OPERATiON may oraceed until Performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is Placed in the triooed condition within hour. 1 | |||
: 0. C. COOK - UNIT 2 3/4 3-6 Amendment No. | |||
TABLE 3.3-3 Continued) | |||
TABLE NOTATION Trip function may be bypassed in this MODE below P-11. | |||
Trip function may be bypassed in this MODE below P-12. | |||
The channel(s) associated wi th the protective functions derived from the out, of service Reactor Coolant Loop shall be placed in the tripped mode. | |||
* The provision of Specification 3.0.4 are not applicable. | |||
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours and in COLD SHUTDOWN. within the following 30 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. | |||
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in HOT SHUTDOWN within the following 12 hours; however, one channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel i s placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. | |||
D. C. COOK - UNIT 2 3/4 3-21 Amendment No.}} |
Revision as of 11:46, 22 October 2019
ML17334A871 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 03/29/1985 |
From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | |
Shared Package | |
ML17334A869 | List: |
References | |
NUDOCS 8504050157 | |
Download: ML17334A871 (37) | |
Text
ATTACHMENT NO. 2 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 REASONS AND 10 CFR 50.92 JUSTIFICATIONS FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGES
Attachment 2 Page For clarity the Unit 2 T/S proposed changes are grouped into several categories. Many of these changes are to achieve consistency with the Unit 1 T/S and the STS. Page references to these documents are given where appropriate.
A) The purpose of the first group of proposed changes is to make the Unit 2 Action Statements 2 and 6 like the Unit 1 T/S and the STS. Specifically we would like to change the phrase "one additional" to "the inoperable."
This change is one that constitutes an additional restriction not presently included in the T/S. Therefore this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.
Page
References:
Action Statement 2; Unit 2 3/4 3-5 Unit 1 3/4 3-6 STS 3/4 3-7 Action Statement 6; Unit 2 3/4 3-6 Unit 1 3/4 3-7 STS 3/4 3-8 B) The second group of proposed changes to Unit 2 T/S requests an extension to the period of time in which one channel of our solid state protection system can be bypassed for surveillance testing. Specifically, we are requesting the one-hour time limit be extended to two hours in Action Statement 1 and Action Statement 13. The reasons for these changes are the same as those proposed for Unit 1 Category C. Although the changes may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, the results of the change are clearly within all acceptable criteria with respect to the systems specified in the STS. Therefore, we believe that these changes do not involve significant, hazards considerations as defined by 10 CFR 50.92.
Page
References:
Action Statement 1; Unit 2 3/4 3-5 STS 3/4 3-9 (Action Statement 12)
Action Statement 13; Unit 2 3/4 3-21 STS 3/4 3-29 (Action Statement 14)
C) The third proposed change to the Unit 2 T/S is an editorial change to Action Statement 2, part C on page 3/4 3<<5. This change adds a reference clearly defining the specification by which the quadrant power tilt ratio is to be measured. This change is purely administrative in nature and is intended to achieve consistency with the Unit 1 T/S and with the STS.
Therefore, we believe this change does not involve significant hazards consideration as defined in 10 CFR 50.92.
Page
References:
Unit 1 3/4 3-6 STS 3/4 3-7
Attachment 2 Page D) The fourth proposed change to the Unit 2 T/S is a change to Action Statement 16 on page 3/4 3-21. This change updates the T/S regarding the conditions under which operation may proceed with the number of operable channels less than total number of channels. The proposed change will achieve consistency with the STS. Although it is a change which may result in some increase to the probability or consequence of a previously analyzed accident or may reduce in some way a safety margin, the result of the change is clearly within all acceptable criteria with respect to the systems specified in the STS. Therefore, we believe that this change does not involve significant hazard consideration as defined by 10 CFR 50.92.
Page
Reference:
STS 3/4 3-29 (Action 17)
ATTACHMENT NO. 3 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 THE PROPOSED REVISIONS TO UNIT NO. 1 TECHNICAL SPECIFICATIONS
3/4, 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM IN TRUMENTATiON LIMIT'.NG CONOITION FOR OPERATION 3.3.1,1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE .
IMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
AC i!QN:
As snown in Table 3.3-1.
5URV E
' LANG E RE".U I R EMENTS 4.3.1.1.1 Each reac"or trip system instrumentation channel shall be demonstra.ed OP RABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNFL FUNCTIONAL TEST operat>ons for ghe gooses end at tne frequencies snown in .able 4.3-1.
m 4.3.1.1.2 The logic for the interlocks shall be demonstrated. OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be deronstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at, leas: once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at Ieas once per 36 months and one channel per func;ion such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.
- 0. C. COOK-UNIT I 3/4 3-1 Amendment No.
l ABLE 3. 3-2 RLAC'IOR l'RII'YSTL'M INSTRUHENTATION Rl'.SPONSE TIHLS FUNCT IONAI UN I I RLSPONSE T1HE
- 1. Hanual Reactor'riir NOT API'L I CABLE
- 2. I'ower Rarrge, Nr.'utrorr I'lux O. 5 secollds*
- 3. I'ower Rarrge, Neutrorr I lux, Iliglr Vositive Rate NOT A VI'L ICAIILE Power Range, Neutron Flux, lliglr Negative Rate < 0.5 seconds'OT
- 5. Inteorrediate Range, Neutrorr Flux API'L ICAIILE
- 6. Source Rarrge, N<<ut.run I Iux NOT APPL ICAIIIE
/. Overterrrl)erature hT < 6.0 seconds'OT
- 0. Overpower hT Al'VLI CABLE 1.0 seconds flurry
- 9. Vressur iz<<r I'ressure--Low <
- 10. I'ressurizer Vressur e--lliglr < 1.0 seconds ll. Pressurizer Water Level--lliglr NOT AVVI.ICAOLE Neutron d<<tectors are exellll)t lr'olll I'espollse tinre testing. Resporrse tirrre of the neutron signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
0
TABLE 4.3-1 (Continued)
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1) If not performed in previous 7 days.
(2) Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference > 2 percent.
(3) Compare incore to excore axial imbalance above 15% "of RATED THERtlAL POWER. Recalibrate if absolute difference > 3 percent.
(4) Manual ESF functional input check every 18 months.
(5) Each train tested every other month.
(6) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.
D. C. COOK-UNIT 1 3/4 3-14 Amendment No.
INSTRUMENTATION 3/4.3.2 ENGINEEREQ SAF" I Y FEATUR ACTUATION SYST"M INSTRI'ENTAT LIMITING CQNOiTION FOR OPERA iON 3.3.2.1 The Engineered Safety Feature Actuation Systen (ESFAS) insttumen a-tion channels and int . locks snown in Table 3.3-3 shall be OPE."-'BLE with their trip setooints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown
--in Table 3.3-5.
APPLICAB!LITY; As shown in Table 3.3-3.
ACTION:
- a. IAlith an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERASL= status with the trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEIL'NCE RENDU'.R"".EN ~
4.3.2.1.1 Each ESFAS instrumentation channel shall be demons. rated OPERABLE by the pe. formance of the CHANNEL CHECK, CHAI4NEL CALIBRATION and CHAN l- FUNCTiONAL TEST operations zox the MQDEs and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock -unction shall be demonstrated OPERABLE at least once per 18 months durina CHANNEL CALIBRATiON testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall 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 such tnat all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3,3 30
- 0. C. COOK-UNIT 1 3/4 3-15 Amendment No.
TABLE 3.3-3 ENGItfEERED SAFETY FEATURE ACTUATIOtl SYSTBI I tlSTRU!1EtlTATIOfl illill l'lUf1 TOTAL NO. CffANtfCI.S ClfAHtlELS APPLICABLE FUNCTIONAL UNIT OF CIIAflfll:LS TO 1 ff IP OI'CIIAOLE NODES ACTIOII SAFETY INJECTION; TURBINE .TRIP, FECDWATER ISOLATION, ArfD HOTOR DRlVE!f f'EEDWATER PUtfPS
- a. tlanua I Initiation 1,2,3,4
- b. Automatic Actuation 1,2,3,4 13 Logic C. Containment 1,2,3 14" Pressure-lliqh
- d. Pressurizer Pressure Low 1, 2, 38k'8 3!I
- e. Differential 1, 2, Pressure Between Steam Lines - lligh Four Loops 3/s team 1 ine 2/steam line 2/steam line Operating any steam line Tllree Loops 3/operating 1 /steam 2/operating Operating steam line line, any steam line operating 5 tealll 1 lne
TAIII E 3.3-3 (Contirrueri}
ENGINEEREI) SAFETY FEATURE ACTUA110N SYSTFH INSTRUMENTATION Hl N IHUH TOThl. NO. CIIANNELS CIIANNELS Al'Pl I CABLE FUNCTIONAL UNIT OF CIIANNLLS TO TRIP OPERABLE HOOES ACTION
- f. Steam Flow in Two 3lP Steam Lines-lligh Four Loops 2/steam line 1/steam line 1/steam line Operating arry 2 steam 1 irres Ttrree Loops 2/operating I /any I/opera t ing 15 OIrerati>>g stearo li>>e operating steam line steam line CO I NC I BENT Mi lll E I I llf.R T --l.ow-Low avg I our Loops 1 T avrJ
/loop 2 T
,
any 1 T avg any Operati>>g loops loops 3 1trree I.ooirs I T in 1 T in any 15 avg avg avg Operati>>g two operating operating any operating loop loop loops
IAIII.L 3.3-3 (Conti>>ued)
I,.NhltILI'IIEI) SAI:I fY Fl.hfUllf ACI'UATION SYSlfH ItISTIIUHLNTATION Hl N I HUH TOTAL NO. CIIANNELS CIIANNELS APPI. I CAOLf FtINCTIONAL UNI r Ol'IIANtlf.l.S TO TIIIP OI'l:IIAOL f HODES ACTION 0th, COlNCll)ENT MITII Steam Line Pressure-Low Four Loops I I>>'essure/ 2 pressures 1 pressure 1 4*
Operat.ing loop a>>y loops any 3 loops Tl~ree Loops 1 pressure/ 1 pressure 1 pressure 15 Opelat,)ncJ operdt.lncJ in a>>y oper- in any 2 loop ating loop operating loops
- 2. CON fAINHLNI Sl'IIAY
- a. Ha>>ual 1.2,3,4 10
- b. Au toe>>a t 1 c Ac t ua t, i o>> l. 2,3,4 13 LocJ ) c
- c. Co>>ta i>>ment I'ressure-- 1,2,3 16 II I cJII-II ) cJh
IAULL 3.3-3 Continued FNGINEEREO SAFETY FEATURE ACTUATION SYSTFH INSTRUHENTATION Hl NIHUH TOTAL NO. CHANNELS CHANNELS APPLICAOLCX FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HOOES ACTION
- 4. STEAH LINE ISOLATION
- a. Hanual 1/steam line 1/steam line 1/operating 1, 2, 3 )8 steam line
- b. Au toma t i c Actuation Logic 2 l 2 - 1,2,3 IS ~
- c. Conta inment Pressure-- 1,2,3 16 ii1 IJtl-III IJIl =
- d. Steam Flow in Two 2 Steam L i ties- High Four Loops 2/steam line l/steam line 1/steam line )4*
Operating any 2 steam lines
'iiree Loops 2/operating )"']any 1/operating )5 OiIerating steam line operating steam line steam line
TABLE 3.3-3 Continued EHGIHEERED SAFETY FEATURE ACTUATIOH SYSTEM IHSTRUMEHTATIOH I
MI ttIMUM TOTAL HO. CtNHHELS CHAHHELS APPLICABLE FUNCTIONAL UNIT OF C}tAHttELS TO TRIP OPERABLE MODES ACTION COINCIDENT WITH EITHER T --Low-Low 1, 2, 3" avg Four Loops 1 Tav /loop 2T any 1 T avg any 14*
Operating loops 3 loops Three Loops 1 Tav /oper- avg in 1 T in any 15 Operating operating ating loop any operating two loop loops OR, COINCIDENT WITH 3PP Steam Line Pressure-Low Four Loops 1 pressure/ 2 pressures 1 pressure 14*
Operating loop any loops any 3 loops Three Loops 1 pressure/ 1 pressure 1 pressure in 15 Operating operating loop in any oper- any 2 oper-ating loop ating loops
- 5. 'CARBINE TRIP 5 FEE DMATER I SOLATIOH
- a. Steam Generator 3/loop 2/loop in 2/loop in 1, 2, 3 14*
Mater Level any oper- each oper-High-High ating loop -ating loop.
TABLE 3.3-3 (Continued)
TABLE NOTATION
¹Trip function may be bypassed in this MODE below P-ll.
¹¹Trip function may be bypassed in this MODE below P-12.
¹¹¹The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.
- The provision of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specif'cation 4.3.2.1.1.
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
D. C. COOK-UNIT 1 3/4 3-22 Amendment No.
TABLE 3.3-3 (Continued)
ACTION 17 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.
ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a ~ The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels >1915 manual block of safety psig ~ injection actuation on low pressurizer pressure.
P-12 With 3 of 4 T channels P-12 prevents or defeats 544oF, manual block of safety injection actuation high steam line flow and low steam line pressure.
With 2 of 4 T channels Allows manual block of 540oF ~ safety injection actuation on high steam line flow and low steam line pressure.
Causes steam line isolation on high steam flow. Affects steam dump blocks.
D. C. COOK-UNIT 1 3/4 3-23 Amendment No.
ATTACHMENT NO. 4 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 THE PROPOSED REVISIONS TO UNIT NO. 2 TECHNICAL SPECIFICATIONS
TABLE 3.3-1 (Continued TABLE NOTATION Kith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop. shall be placed in the tripped condition.
SThe provisions of Specification 3.0.4 are not applicable.
ftHigh voltage to detector may be de-energized above P-6.
ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inonerable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testi ng per Specification 4.3.1.1.1.
- c. Either, THERMAL POWER is restricted to ~ 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to ~ 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.c..
ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
D. C. COOK - UNIT 2 3/4 3-5 Amendment No.
, 4HLE 3. 3-1 '.Con t inued)
Below p 6, restore the inooerable channel to OPERABLE status prior o increasing HER."AL CMER above :he ~-6 Setpoint.
- b. Above rr-5 but below ="i of ~ATED :HERBAL PCMER, res.ore the incoerable channel =o CPERAHLE status prior to increasing THERMAL POWER above 5."i of MATEO THERMAL POWER.
- c. Above S'. of RATED THERMAL POWER, POWER OPERAT'.ON may continue.
AC, IQN 4 - With :he number of channels OPERABLE one less than required by the .'4linimum Channels GPERA8LE reauirement and with the
,HERBAL POWER level:
3elow P-6, restore the nooerable channel to OPERAHLE status pr .or to increasing .HERBAL POWER above the P-6 Setpoint.
- b. Above P-6, ooeration may continue.
ACi;ON 6 - With the numoer of channels OPERABLE one less than required by he Min mum Channels ~".PERAHLE requirement, verify compliance with the SriUTi QWN ~ARCsi",l reouirements of Speci "ication 3.1.1.1 or 3.1.1.2, as aoolicable, with..n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once oer 12 hours thereafter.
AC,:"ON 6 - Mith the number of OPERABL= channels one less than the Total 'fumber of Channels, ARTUP and/or POWER OPERATICt
~ay proceed provided the following condit ons are satisfied:
- a. .ne inooerable channel is placed in ".he triooed condition within 1 hour.
he Minimum Channels CP RABLE reouiremer.t is met; however, the inoperable channel may be bypassed ror uo to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of the other channels per Specification 4.3.1.1.1.
AC-.:QN 7 - With the number of OPERABLE channels one less than :he
.otal Number of Channels, STARTUP and/or POWER OPERA ION may oroceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tr.'oped condition within hour . 1
- 0. C. COOK - UNIT 2 3/4 3-6 Amendment No.
TABLE 3.3-3 Continued)
TABLE NOTATION Trip function may be bypassed in this MODE below P-11.
Trip function may be bypassed in this MODE below P-12.
The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.
- The provision of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN. wi thin the fol lowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed unti 1 performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2. 1. 1.
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for su; veillance testing per Specification 4.3.2.1.1.
D. C. COOK - UNIT 2 3/4 3-21 Amendment No.
ATTACHMENT NO. 3 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 THE PROPOSED REVISIONS TO UNIT NO. 1 TECHNICAL SPECIFICATIONS 8504050157 850329 PDR ADOCK 05000315 P PDR
0 L J
)
3/4. 3 INSTRUMENTATION 3/4,3.1 REACTOR TRIP SYST"M INTRUMENTAT:ON LIMITING CONDITION FOR OPERATION 3.3,1.1 As a m'nimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OP RABL with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
AC i!QN:
As shown in Table 3. 3-1.
SUR'/E;Li ANCE RE"UiRcMENTS 4.3.1.1.1 -
Each reac or trip system instrumentation channel shall be demonstra.ed OP BABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNC IONAL TEST operations for the Moops at tne frequencies snown in able 4.3-1.
4.3.1.1.2 The logic for the interlocks shall be demonstrated. OPeRABLE prior to each reactor star tup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE't least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TiNE of each reactor trip function sha11 be demonstrated to be within its limit at, least once per 18 months. Each test shall include at least one logic train such tha.
both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.
- 0. C. COOK-UN I T 1 3/4 3-1 Amendmene go.
1'ABLE 3.3-2 RL'AC IOR 1 R I I'YSTLH INSTRUHL'NTATION RLSVON'SL TIHLS FUNCTIONAI. UNI I RLSPONSE TIHE
- 1. Hanual Reactor Trip NOT AI'I'LI CAIILE
- 2. I'owens Ra>>ge, Neutro>> I'lux < 0.5 seconds'.
I'ow<<r Ra>>ge, Neutron I Iux, lligli I'os itive Rate NOT AVI'LI CAIILE
- 4. Power Ra>>ge, Neutron .Flux, Iligli N<<gative Rate < 0.6 seconds"
- 5. Inteonediate Range, N<<ut.ro>> I'lux NOT API'L I CAIILE
- 6. Source Ra>>ge, Neutro>> I Iux NOT APPL ICAIII E Over tenq)era ture hI < 6.0 seconds'OT
- 0. Overpower AT Al'VLI CABLE
-
- 9. I'ressu> izer I'ressure--Low 1.0 seconds
- 10. Pressurizer Vressu~ e--ll igl> < 1.0 seco>>ds Pressurizer Water Level--lligl> NOT AVI'I.I CABLE 11.
Neutron d<<tectors are exellli)t trolll lespo>>se tlllle testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
0
TABLE 4.3-1 (Continued)
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1) If not performed in previous 7 days.
(2) Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference > 2 percent.
(3) Compare incore to excore axial imbalance above 15% of RATED THERl1AL POWER. Recalibrate if absolute difference > 3 percent.
(4) Manual ESF functional input check every 18 months.
(5) Each train tested every other month.
(6) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) - Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.
D. C. COOK-UNIT 1 3/4 3-14 Amendment No.
INSTRUMENTATION 3/4.3.2 ENGINEERE0 SAFE,Y FEATURE AC UATION SYST=M INSTR"," NTAT'.CN LIMITING CONOITION FOR OPERA; ION 3.3,2,1 The Engineered Safety Feature Actuation System (ESFAS) instrumen a-tion channels and inte. locks shown in Table 3.3-3 shall be OPERABLE with their trip setooints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICAB!LITY: As shown in Table 3.3-3.
ACTION:
- a. With an ESFAS instrumentation channel trip setpoint less corse.va-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OpERASLE status wi th the trip setpoint adjusted consistent with the Trip Setoint value.
- b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEIL'NCE REOUIRE"ENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERASLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODEs and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the interlocks shall be denonstrated OPERABLE during the automatic actuation logic test. The total interlock funct'on shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall 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 such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3~3 3 ~
- 0. C. COOK-UNIT 1 3/4 3-15 Amendment No.
TABLE 3. 3-3 ENGItlEEREO SAFETY FEATURE ACTUATIOtl SYSTBI ItfSTRUHEtlTATIOll I I I I I I I'fUt1 TOTAL NO. CIIANtlCI.S CllANtlELS APPLICABLE FUtlCTIONAL UNIT Of'llAllllELS TO 1RIP OVERAfJLE HOOES ACTIOtl SAFETY INJ ECTION; TURBINE .TR I P, FEEDWATER ISOLATION, AND HOTOR DR IVEtf I:EEOtCATER PUtlPS
. a. !Ianua I Inil.iation 1,2,3,4 18
- b. Automatic Actuation 1, 2, 3, 4 13 Logic c Containment 1,2,3 14*
Pressure-lliqh
- d. Pressurizer 1,2,3lt Pressure - Low
- e. Oifferential 1, 2, 3df Pressure Between Steam Lines - lligh Four Loops 3/s team 1 ine 2/steam line 2/steam line 14" Operating any steam line Three Loops 3/operating 1 /steam 2/operating 15 Operating steam line line, any steam line operating steam line
TABI f. 3.3-3 (Continued}
ENGINEEREI) SAFETY FEATURI'. ACTUA1ION SYSTFH IHSTRUHLNTATION n HINIHUH TOTAL HO. CIIAHNEI. S CIIANNELS APPI.ICADLE C3 C) FUNCTIONAL UNIT OF CIIANHEI.S TO TRIP Of'ENABLE HOnI:S ACTION 7C I
- f. Steam Flow in Two Steam Lines-lligh Four Loops 2/sl.earn line 1/steam line 1/steam line 14*
Operating any 2 steam lines Tliree Loops 2/operating I /any 1/opera t ing 15 Operating s team I I ne operating steam line steam line COIHC II)fNT Milli L I I IIER T --l.ow-Low avg I our Loops Operating 1 T,avg
/loop 2 T avg, any 14*
loops 3 loops lhree l.oops fNI in any 1 T in 1 T avg 15 Operating two operating operating any operating loop loop loops Q
Q 9
6 0
fhlII.L 3.3-3 (Cr)r)tlrrrred)
, ~
ltttilNLf'ILff)SAI t fY FI.Aftlltf; ACI'IIATION SYSlfH lNSTIIUHLNTATION n HlNlHIIH TOTAL NO. CIIANNLLS CIIANNf:LS AVPIICAIILE I:IINCTIONAL UNlr t)f CIIANNfl.S TO TltlP OPLItAIILE HOIIES ACTION Olt, COlNCII)KNT WITII S tear)) L ine I'res sure-I. ow
'f:our Loops 1 pr'essure/ ? pressures 1 pressure 14*
Operating 1oop arly 100ps any 3 loops INN TI)ree Loops 1 pressure/ 1 pressure 1 pressure 15 Operating oiler dtillg in ar)y oper- in any 2 loop a tir)g loop operating loops
- 2. CONIAlNHI.NI Sf ftAY L)
- a. Harrua1 1,2,3,4
- b. Autorr)at fc Actuat.io<< 1, 2, 3, 4 13 Logic
- c. Cor) ta inment f'ressure-- 1,2,3 16 lligl)-lligh R
0
inULL 3.3-3 Continued FNGINEERED SAFfTY FEATURf ACTUATION SYSTFH INSTRUMENTATION HINIHUH 10TAL NO. CHANNELS CHANNELS AAPCICAOLEX FUNCTIONAL UNIT OF CIIANNELS TO TRIP OPERABLE HOOTS ACTION
- 4. STfAH LINf ISOLATION
- a. Hanual 1/steam line l/steam line 1/operating 1, 2, 3 18 steam line
-
- b. Automatic 2 1 2 1,2,3 Actuation Logic
- c. Containm<<nt Pressure-- 1,2,3 16 lligi>-Iligl)
- d. Steam Flow in Two Steam Lines- lligh Four Loops 2/steam 1 ine 1/s team 1 ine 1/steam 1 ine 14*
Operating any 2 steam 1 ines Tliree Loops 2/operating I /any 1/opera t ing 15 OiIera t ing steam line operating steam line steam line
TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION HIHIHUlh TOTAL HO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UHIT OF CHANNELS TO TRIP OPERABLE NODES llCTI OH COINCIDENT MITH EITHER T --Low-Low avg Four Loops /loop 14*
any 1 T 2 T 1 T any Operating loops 3 loops Three Loops 1 T
/oper-1"'T 'n n 1T avg in any 15 Operating ating loop any operating two operating loop loops OR, COIHCIOEHT WITH Steam Line Pressure-Low
. Four Loops 1 pressur e/ 2 pressures 1 pressure 14*
Operating loop any loops any 3 loops Three Loops 1 pressure/ 1 pressure 1 pressure in Operating operating loop in any oper- any 2 oper-ating loop ating loops
- 5. 'TURBINE TRIP 5 FEEDWATER ISOLATION
- a. Steam Generator 3/loop 2/loop in 2/loop in 1.2,3 14*
Water Level any oper- each oper-High-High ating loop 'ating loop
TABLE 3.3-3 (Continued)
TABLE NOTATION gTrip function may be bypassed in this MODE below P-ll.
55Trip function may be bypassed in this MODE below P-12.
PHOThe channel(s) associated with the protective functions derived from the out of service Reactor Coolant L'oop shall be placed in the tripped mode.
- The provision of Specification 3 '.4 are not applicable.
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance-testing per Specification 4.3.2.1.1.
ACTION 14 With the number oz OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 15 With a channel associated with an operating loop inoperable, restore 0he inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specif'cation 4.3.2.1.1.
ACTION 16 'With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1.
D. C. COOK-UNIT 1 3/4 3-22 Amendment No.
TABLE 3.3-3 (Continued)
ACTION 17 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.
ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed prov'ded the following conditions are satisfied:
a ~ The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-ll prevents or defeats pressure channels >1915 manual block of safety pslgi injection actuation on low pressurizer pressure.
P-12 With 3 of 4 T channels P-12 prevents or defeats
> 544'F. manual block of safety injection actuation high steam line flow and low steam line pressure.
With 2 of 4 T channels Allows manual block of
<540oF, safety injection actuation on high steam line flow and low steam line pressure.
Causes steam line isolation on high steam flow. Affects steam dump blocks.
D. C. COOK-UNIT 1 3/4 3-23 Amendment No.
ATTACHMENT NO. 4 TO AEP:NRC:0659D DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 THE PROPOSED REVISIONS TO UNIT NO. 2 TECHNICAL SPECIFICATIONS
TABLE 3.3-1 (Continued TABLE NOTATION
+Mith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.
~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop. shall be placed in the tripped condition.
8The provisions of Specification 3.0.4 are not applicable.
HHigh voltage to detector may be de-energized above P-6.
ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inonerable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.
- c. Either, THERMAL POWER is restricted to ~ 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to ~ 85K of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.c.
ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
D. C. COOK - UNIT 2 3/4 3-5 Amendment No.
,ABLE 3. 3 1 !Continued)
- a. Below?-6, restore the inoaerabie c.",anne1 to OPERABLE sta us "r',or o increasing HER"AL ~OWER above he ~-6 Setaoint.
- b. Above >-6 but below 5"i of ?ATEO THERMAL ?OWER, res ore the incoerable channel :o OPERABLE status arior a incr eas ng THERMAL POWER above 5,. of MATEO THERMAL ?OWER.
- c. Above "".'l of RATED HERMAL POWER, POWER QPERAT'.ON may continue.
AC,IQN 4 - Mith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE reauirement and with the THERMAL ?OWER 1evel:
3elow ?-6, restore the inooer able channel to OPERABLE status ar.'.or to ir creasing .HER.",AL POWER above the P-6 Setpoint.
- b. Above ?-6, ooerat'.on may continue.
ACT'.ON 5 - Mith the numaer of channels OPERABLE one less t?'an required by he .colin mum Channels OPERABLE requirement, verify compliance wl h he SHUTDOWN ~ARCiIN requirements of Soeci fication 3. 1. 1, 1 or 3.1. 1.2, as aool',cable, with.'n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once aer 12 hours thereafter.
AC,'.QN 6 - Mi h the ~umber af OPERABLE channels one less than .he Total Numoer of Channels, STARTUP and/or POWER OPERATION i'ay oraceed provided the following candit';ons are satisfied:
- a. .ne inooerabie channel is olaced in he triooed condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. 'he Minimum Channels t'PERABLE reauiremer,t is met; however, the inoperable channel may be byoasseh for uo to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of the other channels per Specification 4.3.l.l.l.
AC".:QN i - With the number of OPERABLE channels one less than ".he
,otal Number of'hannels, STARTVP and/or POWER OPERATiON may oraceed until Performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is Placed in the triooed condition within hour. 1
- 0. C. COOK - UNIT 2 3/4 3-6 Amendment No.
TABLE 3.3-3 Continued)
TABLE NOTATION Trip function may be bypassed in this MODE below P-11.
Trip function may be bypassed in this MODE below P-12.
The channel(s) associated wi th the protective functions derived from the out, of service Reactor Coolant Loop shall be placed in the tripped mode.
- The provision of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 13 With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN. within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 14 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 15 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 16 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel i s placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1.
D. C. COOK - UNIT 2 3/4 3-21 Amendment No.