Text

Proposed Tech Spec Revs Re Inservice Insp & Testing Requirements,Boric Acid Transfer Pumps,Auxiliary Feedwater Pumps & Centrifugal Charging Pumps
	ML17324A959
Person / Time
Site:	Cook
Issue date:	06/20/1986
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17324A958	List: ML17324A957; ML17324A959;
References
	AEP:NRC:0433K, AEP:NRC:433K, NUDOCS 8606260357
	Download: ML17324A959 (31)
	v • d • e

n Mr. Harold R. Dento AEP:NRC:0433K ATTACHMENT 2 TO AEP:NRC:0433K Revised Technical Specifications Pages Eor D.

C.

Cook Units 1 and 2

BbOb2b0357 BbOb20 PDR

DOCK 05000315 PDR

SGRVE 4.0.1 Surveillance r equirements shall be applicable during the OPERATIONAL 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 25j 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 condition shall not be made unless the Surveillance Requirement(s) associated w'

he Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for irservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a ~

Inservice inspection of ASME Code Class 1, 2, and 3 components ard irservice 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 Pr essure 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 C/R 50'ection 50 55a(g) (6) (i) ~

D. C.

COOK UNIT l 3/4 0-2 amendment No.

I REACTjVITY CONTROL SYSTEMS CHARGING PUMP " SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 One charging pump in he boron injection f1cw path required by Specification

3. 1.2. 1 shall be OPERABLE and capable cf being powered fram an

, OPERABLE emergency bus.

APPLICABILITY:

DOGES 5 and 6.

ACTION:

a.

Vith no charging pumo OPE!MLE, suspend all oper a fcns fnvo$ vfag CORE ALTERATIONS or pasitive reactivity changes.

b.

Wth mare than one char fng oump OPERABLE or with a safety fnjection pump(s} OPERABLE when the temoerature of any RCS eoId Ieg is less than cr equal to l70 F, unless the r ac-.oi vessel head is removed, r

move the additional cha.ging pump(s) and -he safety injec=ion pump(s) motor circuit breakers fram the elec=rical power cir uit wfzhin cne hour.

c.

The provisions cf Speci icaticn 3.0.3 ar not applicaole.

I I

I I II

, i SURVE LLAHC"- REOUIR.'. NTS 4-1.2.3.1 The above mqufr d charging oump sha11 be demonstrated OPERABL by verffyfna, that on recirculation flow, the sumo develcos a, discharl;e pressure Cf >2390 pSig When taSWd purSuant W SpeCifiCatiOn 4.0.5 at least once per ~l <<Ys-.

4.1.2.3.2 All charging oumos and safety injec on pumps, excludfng the above required OPERABLE cnarqing pump, shall be demons-rated

'.ncoeraole by veri,y',ng that the motor c'.rcuft breakers have been removed f.m their elec rical power supply circuits at least ance per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , except wnen:

a.

The reac-.or vessel head is removed, or b.

The temperature of all RCS cold legs fs greater than 1.70 F

0 C.

COOK - UNIT 1

3/4 1-11 Amendment No.

REACTIVE CONTROL SYSTB<S CHARGIHG PUMPS - OPERATiHG LIMITIHG CONOITION FOR OPERATION

3. 1.2.4 At least two charging pumps sha11 be OPHABLE.

APPLICABTL~i:

NOES I, 2, 3 and 4.

ACTION:

fifth only one charging oump OPERABLE, restore at 1east two charging pumps to OPERABLE situs wfthin 7Z hours or be in HOT STANOBY <<fthin the nex 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least t<<o charging pumps to OPERABLE status <<it rfn 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 i'ol)oi<<ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIR&ENT S 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 at least once per 31 days on a STAGGERED TEST BASIS.

D. C.

COOK UNIT 1 3/4 1-12 Amendment No.

~

j ~

~

j ~

~

~ j

~

e

~ j'g 'I

~

~ '

~ s

~

~ ~

~ j

~

II

~

j

~

~ ~

~

~ j '

~

~ ~

~

I

~

~ ~

~

0

~

~ ~

I

~

0

~

REA,CTOR COOLANT. SYSTEM SURVEILLANCE RE UIREMENTS (Continued) 1.

All nonplugged tubes that previously had detectable wall penetrations

+20X).

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 part'al 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 poreions of the tubes where imperfections were previously found.

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

Cateeorv Ins ecti.on Results C-1 Less than 5Z of the total cubes inspected are degraded tubes and none of the inspected tubes are defective.

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

C-3:

More than lOX of the total tubes inspected are degraded tubes or more than 1X of the inspected tubes are defective.

Note:

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

D. C.

COOK UNIT 1 3/4 4-8 Amendment No.

REACTOR COOLANT SYSTEM(

SURVEILLANCE REOUiR&EHTS (Continued )

4.4.5.3 Insvection Freau ncies

- The above r equired inservice inspections of steam generator tuoes shall be performed at the following frequencies:

The first inservic inspection shall be performed after 5

Effective Full Power Hoaths but within 24 calendar months of initial criticality.

Subsequent inservic 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 inspe tfons demonstrat that previously observed degradation has not continued and no additional degradation has occur red, the inspection interval may be extended to a maximum of once per 40 months.

b.

C ~

the r esults of the inservic inspection of a s

earn generator conduct 0 in accordance with Table 4.4-2 at 40 month intervals,all in Category C-3, the inspection freouency shall be increased to at least cree per 20 months.

The increase in inspection requency shall aooly until the subseauent inspections satis, y :he criteria of Soecification 4.4.5.3.a;

he inte. val may then be extended to a maximum o-onc per 4" months.

Addi iona I

~ unschedul ed inservic inspections shal I be per formed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown su"sequer,t to any of the foliolNing conditions:

.. I.

Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sneet welds) in excess of the limits of Speci ication 3.4.6.Z.

2.

A seismic occurrence gree" r than the Operating Basis

.Earthquake.

3.

A loss-of-coolant ac ident requiring ac.uation of the engine red safeguards.

4.

A main steam line or feedwater line break.

0 AC COOK UNIT 3/4 4-9 Amendment No.

REACTOR COOLANT. SYSTEM SURVEILLANCE RE UIREMENTS Continued 4.4.5.4 Acce tance Criteria As used in this Specification:

gtl It dl i, flit or contour of a tube from that required by fabrication drawings or specifications.

Eddy-current testing indications below 20% of'he nominal tube wall thickness, if detectable, may be considered as imperfections.

2.~0d I

I -ldd llg.

tg wear or general corrosion occurring on either inside or outside of a tube.

3.

Degraded Tube means a tube containing imper ections

>20" tll k d by d

g I tl 4.

5 Oe radation means the percentage of the tube wall tnlc ness arfected or removed by degradation.

5.

Defect means an imperfection of such severity that it exceeds the plugging limit.

A tube containing a defect is defective.

6.

Pluaoina L:mit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and

's equal to 40" of the nominal tube wall thickness.

7.

Vnserviceable describes the condition of a tube if it k <<I df tl ll gtt ff*

structural integrity in the event of an Operating Basis

'arthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

2.

~Tb I

I I

g I

f I

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 Amendment No.

REACTOR COOLANT SY~i SURYETLLNC"- REOUTRB<~i (Continued) 4.4.5.5 b.

c The s~<m generatar shz11 be determined OFGNSLE after campletfnq the corresponding actfans (plug all tubes exceedfnq CM pluggfnq liarit and all tubes containing thrcuah-wall a"cks) requfred by Table 4.4-2.

Fcllcwfnq each inservice inspection cf steam generator

'abes, the number af Cubes plugged in each a~am generator shai.l be reported w De Ceamssfcn wi Din 15 days.

<ae ampler resu1ts',

the stem~

generator wbe inservfce fnspectfcrt shall be included in Ne Annual Operating Report far the periad in wnich this inspecticn was aunpleted, Thfs report sha11

<nclude:

Number,and extant af ~es inspected.

Z.

Mtfcn and peart a-, wzlI-Sickness penetration fcr each indi t cn.

w imperractian.

3.

identification af Sbes plugged.

Results af s-earn generawr ube inspecticns which all inta Category C-3 and >quire prost nctific tier cf the Caaaissfon shall be reported'pursuant z Spec-.'-,icatfcn 6.9.1 prior ta resumption of pl'nt operation.

The wr ittan fcilcwup af this report shall provide a description cf investigations conducted ta determine cause c= the gabe mgr

'atiar. zna carrective measures wken w prevent r currenc O.C.

COOK - UNET 1

Amendment No.

a n

C)OO pc I

TABLE 4.4-1 MINIMUM NUHBL'R OF STEAM GENERATORS TO BF.

INSPECTL'D DURING INSERVICE INSPECTION Preservice Inspection No. of Steam Generators per Unit Yes Four First Inservice Inspection Second

& Subsequent Inservice Inspections Two One 2 Table Notation; The inservice inspection may be limited tr one steam generator on a rotating schedule encompassing 3 N X 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.

~ ~

~

t g

~

e

~ l

~ ~

I

~ ~

~

~ ~

~

~ ~

~

II

~

~ ~

~

11

~

s I

~

~ ~

~

~ ~

0 s

~

~ ~

~

~,

~ ~

~

1

~

1 ~

~

REACTOR COOLANT SYSTEM This page intentionally left blank.

D.

C.

COOK - UNIT 1 3/4 4-34 Amendment No.

REACTOR CCOLAHT SYST"-9 RELIEF VALVES - OPERATIHG

'IHITEM COHOIT.OH FOR OPERATAOH 3.4.U.

Three power operated relief valves (PORVs) and their assaciated black valves shall be OPERABLE.

APPLICABILITY:

MOQES 1, 2, and 3.

ACTION:

C.

fifth one or more PORV(s) inooerable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORY(s) to OPERABLE status or close the associated block valve(s) and remove power from the black valve(s); otherwise, be in at, least HOT STAHOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in CQLQ SHUTOGW within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

IAtl ~1 one or more block valve(s) inaperable, wi hin 'our either

(~) restore the block valve(s) to OPERABL= status, or (2) close the black valve(s) and remove oower rram the black valve(s),

or (3) close the associated PCRV(s) and remove power fram the associated solenoid valve(s);

other <<isa be in at least HCT >TAHOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUtOOMH within the o11cwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . "

one provisians o, Specification 3.0.>> are not aopliczble.

SURVEILi&HCE RE"UIREHBl S

4.4.U..1 Each of the thr e FORVs shall be demonstrated OPERABLE:

At least once per 31 days by performance af a CHAHHEL FUHCTTOHAL TcST, excluding valve aoeration, and b.

At feast ance per

~8 months by performance of a CHAHHEL CALIBRATTOH.

~hen ACT.OH 3.$.>>.b. (3) is aoolied, no reoor pursuant ta Speciffcation 6.9.1.9 is r equired or the PORV.

D-C.

COOK UNIT 3/4 4-35 Amendment No.

~

g

~

~ ~

~

~ ~

~

~ ~

~

~ ~

~ ~ ~

~

I ~

~

~ *

~

s I ~

~

~ ~

~

~II~

I '

~

II

~

XVX'NC COIDITIOKS 76R OPERATIO1 3.4.12.1 kt least one of Che Reactor Vessel head vent paths, consisting of Cue raetely operated valves in series, powered fxoa Class 1E DC

busses, shall be OPEXLSLE and closed.

1. 2. 3.

~

k9GRK:

Vith both of Che Reactor Vessel head vent paths iaoperlble, aad at leas C 0'ne of Che Pres suriser sCsa%

space vsat paths OPER@LE (see Specification 3.4.12.2),

operation in NSES l, 2, 3 or 4 aay conC blaue

~ provided the iaopersb le vent paths are Na inta ined c lo s ed eith pever reaoved froa the valve actuators of all the r~tely operated valves ia all of the iaoperab!e mat paths; restore at least one of the Reactor Vessel head vent paths within 30 days or be in HOT STLRbT within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHTDOM5 within the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

~

bo Vith both of the Reactor Vessel head vent paths and both of the Pressurizer steaa space venC paths iaoperable; aamtain the inoperable vent paths closed vith poser zssoved froa the valve actuators of all of the remotely operated valves ia all of the inoperable vent paths; restore one of the inoperible rent paths froa either the Reactor Vessel head vent or the Pressurizer steaa space <<ithia 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be ia ROT SThSDET vithm 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aad ia COLD SHUTDSiW within the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C ~

The provision of Specification 3.0.4 are not applicable

~

D. C.

COOK UNXT 1 3/4 4-37 Amendment No.

i.4.12.1 Both Reactor Vessel head vent paths shall be demonstrated OPERABLE at least once yer 18 months by:

1. Veri+in'he common manual isolation valve in the Reactor vessel head vent is sealed in the open position.

R.

Cycling each ot the remotely oyerated valves in each path through at least one complete cycle ot ~1 travel tram the Control Hoee while in Modes 5 or 6.

3.

Verifying Acw through both of the Reactor Vessel head vent paths dur~ venting oyeratioa, while in Modes 5 or 6.

Surveillance roquiraaeats to demonstrate the operability ot each Reactor Vessel head vent path wQ,l be performed the next time the unit enters MODES 5 or 6 following the issuance of this Technical Specification, and after the appropriate Plant procedures have been written.

D C

COOK UCT l 3/4 4-38 Raenchaent Ho.

OR COO IDII 0 R

RL TON 3.4.12.2 kt 1east one of the Pressurizer steaa space vent paths, each consisting of tvo remotely operate valves in series,

povered, frets Class IE DC busses, shall be OPERAbLI and c1osed.

1..3.

13 ao Vith both of the Pressurizer steam space vent paths inoperable, and at least one of the Reactor Vessel head vent paths OPEMLZ (see Specification 3.4.12.1),

operation in SEES 1, 2, 3 or 4 may

continue, provided the inoperable vent paths are aaintained closed vith the pover removed froa the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Pressurizer steaa apace vent paths vithin 30 days or be in EOI SXLHDBT vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDORf in the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Pith. both of the Pressurizer steaa apace vent paths and both of the Reactor Vessel head vent paths inoperable',

maintain the inoperable vent paths closed vith pomr removed froa the valve actuators of all of the reaetely operate valves in all of the inoperabla vent paths; restore one of the inoperable vent paths free either the Reactor Vessel head vent or the Pressurizer stsaa space vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in SOT SThHDBT vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SEUIDOQE vithin the folloving 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.

D. C.

COOK - UNIT 1 3/4 4-39 Amendment No.

4.4.12.2 Both ~surfer steaa space vent paths shall be decenstrated OPEQBLB at least once per

$ 8 months by:

Veritying the common manual isolation valve in the Pressurixer steais space vent is sealed in the open yosition.

2.

Cycling eaoh ot the renotely operated valves in each path through at least one complete cycle ot full travel froa the Control Roen vhLle in Modes 5 or 6.

3 ~

Verifying floe through both ot the Pressurixer steaa space vent yaths during venting operation, ~le in Modes 5 or 6.

Surveillanoe requirments to deaenstrate the operability ot each Pressurizer steam spaoe vent yath will be performed the next t~ the unit enters NODES 5 or 6 following the issuance ot this Technical Specification, and atter the appropriate Plant procedures have been written.

O. C.

CO@X - OSZT l 3/4 4-40 Amendment No.

~

I

~

0

~

4 ~

~

I 'I I

~

I ~-

~

I

~

~ ~

~

~ ~

~

4

~

~ ~

C

~

~ ~

~

0

~

0 ~

~

I

EMERGENCY CORE COOLING SYST"-RS SURVEILLANCE REOUIRBIE'HTS (Continued )

d.

At least once per 18 months by:

e.

l.

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

2.

A visual inspection or the cantairment sump and ver ifying that the subsysten suction inlets are not r estricted by debris and that the sump components (trash racks, sere ns, etc.)

show no evidence of structural distress or corrosion.

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

1.

Verifying that each automatic valve in the low path actuates to its corre t position on a Safety Injection test signal.

g.

a)

Centr ifugal charging pump b)

Safety injection pump c)

Residual hea.

removal pump By verifying that each of the ollowing pumps develoos the indicated discharge pressure on re irculation flow when tested pursuant to Soecification 4.0.5 at leas~

once per 3l daYs on a STAGGERED TEST BASIS.

1.

Centrifugal charging pump

> 2405 psig 2.

Safety Injection pump 1445 psig 195 psig 3.

Residual heat removal pump Sy verirying the correct position of each mechanical stop for the the following Emergency Core Cooling System throttle valves:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking opera tion or ma intenanco on the va 1 ve when the ECCS sub-systans are required to be OPERABLE.

Amendment No.

2.

Verifying that each o.

the following pumps start automatically upon receipt of a safety inje"tion test signal:

0.

C.

COOK

-. UNIT 1 3/4 5-5

EMERGENCY CORE COOLING S

EMS

'tjRVEIL!DHCE REOttIREMEHTS (Continued) 2.

At least once per 18 months.

Boron Injection Throttle Yalves Safety Injection Throttle Yalves Valve Number 1.

) -Sr-141 L1 2.

(.-SI-141 L2 3.

t

-SI-141

4. l

-SI-141 L4.

Valve Number

-SI-121 H

2. l

-SI-121 S

h.

By performing a flow balance test during shutdown following completion of modifications to the ECCS subsystem that after th subsys em flow charac eristics and verifying the following flow rates:

~

'. I Boron Injection System Sinale Pumo~

Loop 1 Boron Injection Slow 117.5 opm Coop 2 Boron Injection Flow 117.5 gpm Loop 3 Boron Inject. ion Flo 117.5 gp Loop 4 Boron Injection Flow 117.5 apm Safety Injection Svs em Sinole Pumo""

.Loop 1 and 4 Cold Leg Flow > 300 gpm Loop 2 and 3 Cold Leg Flow > 300 opm "The flow rate in each Boron Injection (SI) line should be adjusted to provide 117.5 gpm (nominal} flow into each loop.

Under these conditions there is zero mini-flow and 80 cpm simulated RCp seal injection line flow.

The ac-ual flow in each Bi line may deviate from the nominal so long as the differ nce between the highest and lowest low is 10 gpm or less and tne total flow to the four branch lines does not exceed 470 gpm.

Minimum f!ow (total flow}

required is 345.8 gpm to the thr e most conservative (lowest flow) brarch 1 ines.

- Combined Loop 1, 2, 3, and 4 Cold Leg Flow (single pump) less than or not exceed 700 equal to 640 gpm.

Total SIS (single pump) flow includin 'fl h

11 gpm.

m>n>

ow, s

a 0.

C.

COOK - UNIT 1

3/4 5-6 Amendment No.

I

~

e l

~

I I

~ ~

I ~

~

~ -

I

'o

~

~ I

~

0 If

~

e

~

0

~

I

~

I '

~

~ ~

~

~ ~

~

~ ~

~

This page intentionally left blank.

~j D.

C.

COOK - UNIT 1 3/4 6-11 Amendment No.

Pl

~

g e

~

~ ~

~

~ ~

~

~ ~

~

I

~

I

~

~ ~

~

I

~

~ ~

~

~ ~ ~

I 4

~

I

~

I t

~

g

~

~ ~

~

~ ~

~

~ ~

~

I

~

~ ~

~

~ ~

~

~ ~

0

~

This page intentionally left blank.

D. C.

COOK UNIT 1 3/4 7-16 Amendment No.

~

~ 0 l

~

I ~

~

~ ~ I I

~

~ ~ ~

I l ~

~

4

~ I

~

I ~

~

~ I ~

~

~ ~

I ~

~

t

~ ~

~

0

~

I

~

~ 0 o

~

I

~ ~

~

APPL ZCABILITY BASES 4.0.5 This specif'cation 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.

Rel'ef from any of the above requirements has been provided in writing by the Commission and is not a part of these technical specifications.

This spec'ication includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI 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 pr'or to entry into an OPERATIONAL MODE or other specif'ed applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code pzovision 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 Amendment No.

REACTOR COOLANT SYSTEM BASES 3/4.4. 10 STRUCTURAL ZNTEGRITY The inspection and testing programs for ASME Code Class 1,

2 and 3 components ensure that the structural integrity of these components vill 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 Xl of the ASME Boiler and Pressure Vessel Code.

D. C.

COOK - UNIT 1

B 3/4 4-12 Amendment No.

~ Q)

~

~I

~

~ ~

~

~ I

~I

~

~\\ ~

II ~

~

I~ ~

~

~ I ~

~ ~

~

~ I ~

~

~ I ~

~

~ II

~

~ I ~

~

~ r

~

I

~

0 '

~

~ I

~

~I

~

~ I ~

~

II ~

~

~ '

I ~

~

~I 0

~ ~

~

~ ~ ~

~

~I ~

~

0 ~

0

~I

~

t ~

~ ~

~

~'

~ I

~

~ ~

I

~ IA

ML17324A959

Text

Navigation menu

Search