Text

Proposed Tech Spec Section 4.0.5,incorporating Inservice Insp & Testing Requirements of ASME Code Section XI
	ML17320A518
Person / Time
Site:	Cook
Issue date:	05/10/1983
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17320A516	List: ML17320A515; ML17320A518;
References
	NUDOCS 8305160126
	Download: ML17320A518 (32)
	v • d • e

ATTACHMENT NO. 2 TO AEP:NRC:0433 REVISED TECHNICAL SPECIFICATIONS PAGES DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 830510 8305160126 05000315 PDR ADOCK PDR P

3/4.0 APPLICABILITY SURVEILLANCE RE UIREMZZTS

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4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL

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MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified

time interval with:

a. A maximum allowable extension not to exceed 25X of the surveillance interval, and

b. A total maximum combined time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4 .0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condi-tion shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated

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surveil'nce interval or as otherwise specified.

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.'.0.5 Surveillance Requirements for inservice inspection and testing of

'SME Code Class 1, 2, and 3 components shall be applicable as follows:

Inservice inspection of AFiiE Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2 and 3 'pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i) .

D. C. COOK UNIT 1 3/4 0-2

REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTOOMN LIMITING CONDITION FOR OPERATION 3.1.2.3 One charging pump in he boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

APPLICABILITY: MOOES 5 and S.

ACTION:

a. Nth no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b. Nth more than one charging oump OP RABLE or with a safety injection pump(s) OP RABLE when tNe temperature of any RCS cold leg is less than or equal tc 188 F unless the reac.or vessel head is removed, remove the additional cha. ging pump(s) and the safety injec.ion pump(s) motor circuit breakers from'he elec.rical power circuit within one hour.

c. The provisions of Specification 3.0.3 ar not applicable.

SURVEILLANCE REOUI REAGENTS

4. L. 2.3.

verifyina, i The above reauired charging cump shall be demonstrated OPERABLE by that on recirculation flow, the sumo develoos a discharge pressure of > 2390 psig when tas~d pursuant to Spec-;fication 4.0.5.

4.1. 2. 3. 2 All charging oumps and safety injec .'cn pumps, excluding the above required OPERABLE caarqing pump, shall be demons-rated inoperable by verify ng that the motor c'.rcui br akers have been removed from their electrical power supply circui-s at Ieas~ once per 12 hcurs, except when:

a. The reac.or vessel head is removed, or 0

The temperature of all RCS caid legs is greater than 188 F D. C. COOK - UNIT 1 3/4 1-11

REACTIVE. CONTROL SYSTBIS CHARGING PUMPS - OPERAT NG LIMITING CONOITION FOR OPERATION

3. 1.2.4 At least two charging pumps shall be OPERABLE.

APPLICABIL~i: MOOES I, 2, 3 and 4.

ACTIOil:

Nth only one charging pump OPERABLE, restore at least tin charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANOBY ~ithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status ~;thin the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLO SHUTDOWN within the foIIowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of ) 2405 psig when tested pursuant to Specification 4.0.5.

0. C..COOK - UNIT 1 3/g

R~DC i IYI~i, CON i GAOL S'l'5 i c:SS BORIC ACID IIIANSF'H O'JMPS - 5'r2JTDG'AN LIMITING CONDITION FOR OPERATION 3.1.2.S At least one boric acid transfer pumo shall be OP%ABLE and capable of being power d from an OP%ABLE anergency bus if only the flow path .hrougn the boric acid transfer pump of Specification 3.',.2. la is OP ABLE. /

APPLICABILITY:'ODES B and 6.

ACTION:

'lith no boric acid transfer pump OP%ABLE as required to complet the flow path of Speci=ication 3. 1.2.la, suspend all opera ions involving CORE ALTERATIONS or posi ive reactivity changes until at least one boric acid transfer pump is restored to OPERABL= status.

SURVEILLANCE REOU IR lENTS 4.1.2.5 No additional Surveillance Requirements other than those required by Specification 4.0.5.

0. C. COOK - UN17 1 3/4 1-13

REACTIVITY CONTROL SYSTEMS BORIC ACID TRANSFER PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least one boric acid transfer pump in the boron injection flow path required by Spec",'fication 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump in Specification 3. 1.2.2a is OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With no boric acid transfer pump OPERABLE, restore at least one boric acid transfer pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to 1% ak/k at 200 F; restore at least one boric acid transfer pump to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0. 5.

D. C. COOK - UNIT 1 3/4 1-14

REACTOR COOlLANT SYSTEM STEkM GENERATORS LIM TING C"NOITION ~OR OPl'RATION 3.4.5 Each steam generator shall be OPERABLL.

APPLICABILITY: MOOES l. 2, 3 and 4.

ACTION:

Mith one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing T above 200'F.

SURYEILLANCE RE UIRBIENTS 4.4.5.0- Each steam generator shall be deranstrated OPERABLE by performance of the following augmented inservice inspection program an'd the require-ment of Specification 4.0.5.

4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shal be aetermined OPERABLE during shutdown by selecting and inspectina at leas the minimum number of s earn generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Sample Selection and 'nsoection - The steam generator tube min>mum sample si-e, inspec=ion result classification, and the corresponding action required shall be as specified in Taole 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptanc crite. ia of Specification 4.4.5;4. The-tubes selected for each inservice inspec- .

tion shall include at least 3" of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a. Where exper ierce in similar plants with similar water chemistry indicates critical areas to be inspe ed, then at least 50 of the tubes inspected shall be from "hese critical areas.

The first sample of tubes selected for each inservice inspection

{subsequent to the preservice inspection) of each steam generator snail include:

O.C. COOK - UNIT 1 3/4 4-7

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations ()20%).

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes "selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories.

~Cate or Ins ection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.

D. C. COOK UNIT 1 3/4 4-8 .

REACTOR COOLANT SYSTEM SUR'lEILLANCE REQUIREMENTS (Continued Insnection Frequencies - The above

'.4.5.3 required inservice inspections of steam generator tubes shall be performed at the following frequencies:

The first inservice inspection shall be performed after 5 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecu-tive inspections following service under AVT conditions, not including the preservice inspection, 'result in all inspection results falling into the C-I category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

If the results of the inservice inspection of a st am generator conduct d in accordance with Tab'le 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The incr ase in

,'nspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 4Q months.

Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequen Co any of the following conditions:

Pr imary-to-secondary tubes leaks {not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Speci ication 3.4.6.2.

2. A seismic occurrence great r than the Operating Basis

.Earthquake.

3. A loss-of-coolant accident requir ing actuation of the engineered safeguar"s.

4, A main ste m line or feedwater line break.

D.c. COOK UNIT 3/4 4-9

REACTOR COOLANT SYSTPII SURVEILLANCE RE UIRBIENTS Continued 4.4.5.4 Acce tance Criteria aI As used in this Specification:

~tf or t'

contour of a gtt t th df 1 tube from that required by fabrication

.f1 1 h drawings or specifications. Eddy-current testing indications below 205 of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2. ~adtf wear or general 1 -td corrosion occurring d

on kfg. 22 either inside or outside of a tube.

2.~266th the nominal tb ttfgtg f wall thickness caused by degradation.

21211'f

4. X Oe radation means the percentage of the tube wall t )c ness a fected or removed by degradation.

5. Oefect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect

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is defective.

6. ~P1 1 tf1 tb td f 1 dfb t by d which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 4OX of the nominal tube wall thickness.

7. Unserviceable describes the condition of a tube if it k 1 d f t 1 2 gh t f it structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

g. ~Tb I tf 1 b 21 f th t g t tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

D.C. COOK- UNIT 1 3/4 4-10

REACTQR CQQLANT SYS i =1 SURYE:I LNCE REQUIRE'SBlTS (Conti nued)

The s~~am generator shall be de+~wined QPBASl "- after completing the corresponding ac-..'ons (plug aII tubes ere ding the plugging lfmit and ail <be c"n- in ng through-waII c-. ccs) required by Table 4.~2.

4.4.:-.9 Reaar w Following each insarvic inspec='.cn c- s: am c n . a-"r ' oes, the nclber c7 tubes plugged in a=eh "~'5 gene. at"r shai.l be r pcr-~d w the Ccmrissicn wi:.".fn I"- days.

The amplet r suits o= ".e swan gener ar ~be fnsarric fnspec icn shall be included fn the AnnuaI Operating Repor. -,or the period fn which Rfs fnspecuon was c"mpie~&. Tnfs repcr-.

shall include:

1. Number and ex-~at cf t bes inspec ~d.

Z. Mcaticn and per ~t c-, waII-'Nic!cness penet. .'cn for ech indication of an fmpe.,a -='"n.

3. [denti-,icaticn cf wbes plugged.

c Results of steam gene~ter tube irspec.icns which -,all into Category C-3 and require prompt no-i-,ication o= the Ccaw'ssfon shall be repor d'pursuant to Spec"ffcaticn 5.9.1 prior resumption of pIant operation. The written 7cllowup o= this

, repor shall provide a description o-, fnvestiga"ion~ c"nduct d to determine cause ci the %be degradaticn ana correc:ive to pr vent recurrenca.

measures'aken O.C. COQK - UNIT 1 3/4 4-11

TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE O

O pc INSPECTLD DURING INSERVICE INSPECTION I

Q Preservice Inspection Yes No. of Steam Generators per Unit Pour First Inservice Inspection Two Second & Subsequent Inservice Inspections 2 One Table Notation:

The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators, Under such circumstances the sample sequence shall be modified to inspect the most severe conditions,

2. Each of the other two steam generators not inspected during the first inservice inspection shall be inspected during the second and third inspections, The fourth and subsequent inspections shall follow the instructions described in 1 above,

REACTOR COOLANT SYSTEM 3/4.4.10. STRUCTURAL INTEGRITY ASME COOE CLASS 1 2 and 3 COMPONENTS LIMITIHG COHOITION FOR OPERATION 3.4. 10. 1 The structural integrity of ASME Cade Class 1, 2 and 3 components shal1 be maintained in accordance with Specification 4.4. 10. 1.

APP LICABILITY: ALL MOQES ACTION:

a. Nth the structural integrity of any ASME Cade Class camponent(s) 1 not canforming to the above requirements, restore t>>e structural integrity of'he affected component(s) to within its limit or isolate the affected component(s) prior to .increasing the Reactor Caolant .

System temperature more than 50~F above the minimum temperature required by NOT considerations.

b. Mith the structural integrity of any ASME Code Clasp 2 component(s) not conforming to the above requirements, restore the s ructural integrity of the affected component(s) ta within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200~F.

c Mith the struc.ural integri .y o any ASME Cade Class 3 component(s) not canforming to the above requirements, res are the s ruc ural integrity of the affected component(s) to within its limit or isolate the affected camoonent(s) rom service.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4. 10. 1 In addition ta the requirements of Specification 4.0.5, each reactor coolant pump flywheel snail be inspected per the recommendations of Regulatory Position C. 4.b of Regulatory Guide l. 14, Revision 1, August 1975.

REACTOR COOLANT SYSTEM RELIEF VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.11 Three power operated relief valves (PORVs) and their associated block valves shall be OPERABI ~.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. Nth one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) ta OPERABLE status or close the associated block valve{s) and remove power from the block valve(s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the fallowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Nth ane or more block valve(s) inoperable, wi hin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore the black valve{s) to OPERABLE status, or (2) close the black valve(s) and remove gower from the block valve{s), or {3) close the associated PORV(s) and remove power from the associated solenoid valve(s); otherwise, be in at least HOT STANDBY within the nex-6 hours and in COLD SH~i OMN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ."

C. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.4.11.1 Each of the thr e PORVs shall be demonstrated OPERABLE:

a. At least once per 31 d ys by oerfarmance af a CHANNEL FUNCTIONAL TEST, excluding valve operation, and

b. At least ance per 18 months by performance of a CHANNEL CALIBRATION.

~hen ACTION 3.4.11.b. (3) is applied, no report pursuant ta Specification 6.9.1.9 is requir d.for the PORV.

D.C.COOK- UNIT 1 3/4 4-34

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS Continued) 4.4. 11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel. The block valve{s) do not have to be tested nor is a report required pursuant to Specification 6.9.1.9 when ACTION 3.4.11.a is applied.

4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries. This testing can be performed in conjunction with the requirements of Specifications 4.8.1.1.2.b and 4.8.2.3.2.c.

D.C.COOK-UNIT 1 3/4 4-.35

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position a 0 IMO-390 a. RWST to RHR a. Open

b. IMO-315 b. Low head SI b. Closed to Hot Leg C. INO-325 c. Low head SI c. Closed to Hot Leg

d. INO 262* d. Mini flow 1 ine d. Open

e. INO-263* e. Mini flow 1 ine e. Open f.. INO-261* f. SI Suction f. Open g ~ ICM-305* g. Sump line g. Closed

h. ICM-306* h. Sump line h. Closed

b. At least once per 31 days by verifying that each valve (manual, power operated or automat-ic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct posi tion.

C. By a visual inspection which verif ies 'that no loose debris (rags, trasn, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1. For all accessible areas of the containment prior to

2. 'festablishing of CONTAINMENT INTEGRITY, and the 'areas affected within containment at the completion each containment entry when CONTAINfiENT INTEGRITY is established.

~th: h to recirculation flow following h h iii d LOCA.

id:h:h i O.C. COOK - UNIT 1 3/4 5-4

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIRB1ENTS (Continued)

d. At least once per 18 months by:

1. Verifying automatic isolation and interlock action of the RHR systan from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2. A visual inspection of the contairment sump and verifying that the subsysten suction inlets a. e not restricted by debris and that, the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

e. At least once per 18 months, during shutdown, by:

l. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

2. Verifying that each of the following pumps start automatic lly upon receipt of a safety injection tes signaI:

a) Centrifugal charging pump b) Safety injection pump c) Residual heat removal pump

f. By verifying that each of the,ollowing pumps develops the indicated discharge pressure on recirculation flow when tes ed pursuant to Soecification 4.0.5:

l. Centrifugal charging pump > 2405 psig

2. Safety Injection pump > 1445 psig

3. Residual heat renoval pump 195 psig g~ By verifying the correct position of each mechanical stoo for the i the following Emergency Core Cooling System thr ot";Ie valves:

1. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve strok n.

operation or maintenanc on the valve when the ECCS sub-systems are required to be OPERABLE.

C. COOK - UNIT 1 3/4 5-5

~

~ ~

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE tJIREMEHTS (Continued)

2. At least once per 18 months.

Boron In j ecti on Safety Injection Throttl e Valves Throttle Valves Valve Number Valve Number

l. f -SI-141 Ll 1. i -SI-121 N

2. l ."SI-141 L2 2; I -SI-121 S

3. I -SI-141 L3

4. ) -SI-141 L4.

h. By performing a ilow balance test during shu down following completion of modifications to the ECCS subsystem that alter the subsystem flow characteristics and verifying the following flow rates:

8oron Injection System Safety Injecxion System Sinale Pumo" Sinale Pumo""

Loop 1 Boron Injection Loop 1 and 4 Col d Leg Flow 117.5 gpm Flow > 300 gpm Loop 2 Boron Injection Loop 2 and 3 Cold Leg Flow 117.5 gpm Fl ow > 300 gpm 3

LoopBoron Injection Total SIS (single pump) flow, Flow 117.5 gpm including miniflow, shall not exceed 650 gpm.

Loop 4 Boron Injection Flow 117.5 gpm "The flow rate in each Boron Injection (BI) line should be adjusted to provide 117.5 gpm (nominal) flow into each loop. Under these conditions there is zero mini-f1ow and 80 gpm simulated RCP seal injection line flow. The actual flow in each BI line may deviate iron the nominal so long as the difference between the highest and lowest flow is 10 apm or less and the total ilow to the four branch lines does not exceed 470 cpm. Minimum !ow (total flow) required is 345.8 gpm to the three most conservative (lowest flow) brarch lines.

D.C.COOK-UNIT 1 3/4 5-6

CONTAINMENT SYSTEMS 3/4.6.2 OEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDIT:ON FOR OPE'RATION 3:6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and trans, erring suction to the containment sump.

APPLICABILITY: MODES-1, 2, 3 and 4.

ACTION:

Mith one containment soray systen inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at leasi HOT STANDBY wi ihin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray system to OPERABLE status within the next, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the rlow path thai is not locked seal ed, or otherwise 'secured in po si ti on, is in i ts cori eci positon.

b. By verifying, that on recirculation flow, each pumo develops a discharge pressure of > 255 psig at a flow of ) 700 gpm, when tested pursuant to Specification 4.0.5.

C. At leas . once per 18 months during shutdown, by:

1. Verifying:hat each au.omatic valve in the "flow path actuates to its correc position on a Containment Pressure--H gh-High test signal.

2. Verifying that each spray pump starts automatically on a Containment Pressure High-High tes t si gnal .

d. Ai leasi once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobsiructed.

D. C. COOK -. UNIT 1 3/4 6 10.,i " ~- ~v'

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D. C. COOK UNIT 1 3/4 6-11

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separate emergency busses, and

b. One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered from separate emergency busses and one capable of being powered by an OPERABLE steam supply steam) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLIANCE RE UIREMENTS 4.7.1.2 The auxiliary feedwater system shall be demonstrated OPERABLE:

a~ By verifying that each motor driven pump develops a discharge pressure) 1375 psig on recirculation flow when tested pursuant to specification 4.0.5.

b.

)

By verifying that the steam turbine driven pump develops a discharge pressure of > 1285 psig at a flow of 700 gpm when the secondary steam supply pressure is greater than 310 psig.

when tested pursuant to specification 4.0.5. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3~

C ~ At least once per 31 days by verifying that each nonautomatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.

D. C. COOK UNIT 1 3/4 7-5

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS

d. At least once per 31 days by verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10K RATED THERMAL POWER.

e. At least once per 18 months during shutdown by:

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

2~ Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

D. C. COOK - UNIT 1 3/4 7-6

PLANT SYSTEMS A

3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the follow-ing 30 hours.

SURVEILLANCE RE UIREMENTS

~ H 4.7.3.1 At least two comoonent cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety r elated equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

D. C. COOK - UNIT 1 3/4 7-15

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D. C. COOK UialXT 1 3/4 7-16

PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION

, ~

3.7.4.1 At least two independent essential service water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2.'3 and 4. A~

~ ~

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

r A

SURVEILLANCE RE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

ar At least once per 31 days by verifying tha, each valve (manual, power operated or automatic) servicing safety r lated equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

D. C. COOK - UNIT 1 3/4 7-17

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APPLICABILITY BASES 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these technical specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section ZI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to

. ensure consistency in surveillance intervals throughout these technical specifications and to remove any ambiguities relative to the frequencies for performing and the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation. And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable, D. C. COOK - UNIT 1 B 3/4 0-5

REACTOR COOLANT SYSTEM BASES 3/4.4.10 STRUCTURAL INTEGRITY The. inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

3/4.4.11 RELIEF VALVES The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves.

These relief valves have remotely operated block valves to provide a positive shutoff capability should the relief valve become inoperable.

The electrical power for both the relief valves and the block valves is supplied from an emergency power source to ensure the ability to seal this possible RCS leakage path.

D. C. COOK - UNIT 1 B 3/4 4-12

ATTACHMENT NO. 3 TO AEP:NRC:0433 REVISED TECHNICAL SPECIFICATIONS PAGES DONALD C. COOK NUCLEAR PLANT UNIT NO. 2

REACTIVITY CONTROL SYSTBlS CHARGING PUMP - SHUTQGMN LIMITING CONOITION FOR OPERATION 3.1.2.3 One charging pump in the boron injec ion flow path required by Specification 3. 1.2. 1 shall be OPERABLE and capable of being powered frcm an OPERABLE emergency bus.

APPLICABILITY: MOOES 5 and 6.

ACTION:

a., Nth no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b. Mith more than one charging pump OPERABLE or with a safety injection pump(s) OPERABLE when the temoerature of any RCS cold leg is less than or equal to 152 F, unless the reac or vessel head is removed, r move the additional charging pump(s) and the safety iniecticn pumo(s) motor circuit breakers from the elec-ricaI power circuit within one hour.

c The provisions of Specification 3.0.3are not applicable.

SL'RYEI LLANCE REQUIRE! E".ITS 4.1.2.3. 1 The above required charging pump shall be demonstrated OPERABL= by verifying, that on recirculation flow, the pumo develcos a discharge pr ssure of )2390 psig when tested pursuant to Specification 4.0.5.

4.1.2.3.2 All charging pumps and safety injec ion pumps, excluding the above required OPERABL charging pump, shall be demons-rated incoerabie by verify ng that the motor circuit breakers have been removed from their elec rical pcwer supply circuits at lees" once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , except wnen:

a. The reac cr vesseI head is removed, cr

b. The temperature of all RCS cold legs is greater than 152 F.

0. C. COOK - UNIT 2 3/4 1-11

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separate emergency busses, and

b. One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered from separate emergency busses and one capable of being powered by an OPERABLE steam supply steam) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWi within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLIANCE REQUIP~NTS 4.7.1.2 The auxil'ary feedwater system shall be demonstrated OPERABLE:

a~ By verifying that each motor driven pump develops a discharge pressure) 1375 psig on recirculation flow when tested pursuant to specification 4.0.5.

b. verifying that the steam turbine driven pump develops a By discharge pressure of ) 1285 psig at a flow of ) 700 gpm when the secondazy steam supply pressure is greater than 310 psig.

when tested pursuant to specification 4.0.5. The pzovisions of Specification 4.0.4 are not applicable for entry into MODE 3~

c. At least once per 31 days by verifying that each nonautomatic valve in the flow path that is not locked, sealed, or othezwise secured in posit'on is in its correct position.

D. C. COOK - UNIT 2 3/4 7-5

PLANT SYSTEMS SURVEILLANCE REQUIREiaKNTS

d. At least once per 31 days by verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10K RATED THK21AL POWER.

e. At least once per 18 months during shutdown by:

I

1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

2~ Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate eng"neered safety features actuation test signal required by Specification 3/4,3.2.

D. C. COOK UNIT 2 3/4 7-6

ML17320A518

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