Text

Proposed Tech Specs Change Re Reactor Coolant System Pressure Isolation Valves
	ML17332A345
Person / Time
Site:	Cook
Issue date:	10/07/1994
From:	Fitzpatrick E; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17332A344	List: ML17332A343; ML17332A345;
References
	NUDOCS 9410170208
	Download: ML17332A345 (20)
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INC CONDI ION FOR OPERATION 3

4 6.2 Reactor Coolant. System leakage shall be limi.ted to>

a. 'o PRESSURE BOUNDARY LEAKAGE, 1

GPM UNZDENTZFZED LEAKAGES Co e.

600 gallons per day total primary-to-secondary leakage through all steam generators and 150 gallons per day through any one steam generator -for Fuel Cycle 14, 10 GPM ZDENTZFZED LEMCKGE from the Reactor Coolant Syatemt Seal line resistance greater than or ecpxal to 2.27E-1 ft/gpm~ and,

~CTION:

a.

b.

C ~

. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDONN wi.hh..n the followi.ng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

M'ith any'Reactor Coolant System leakage greater than any one of the above

limits, excluding

. PRESSURE BOUNDARY 'EAKAGE, reduce the leakage rite to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or 'be in.at least HOT.

~..STANDBY within 'the "qext' hours an'd in COLD, SHUTDOWN within the foliowing'Q"houri.

Wi.th any reactor coolant system pressure'i.aolation valve(s) leakage Speci.fication 3.4.6.2.e ia applicable with average pressure within 20 pai.

of the nominal full pressure

'value.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-16 AMENDMENT.NO. +62 g zan&,

$ 7@.~P)".g Order dated April 20, 1981 9410170208 941007 l

PDR ADOCK 05000515 P

PDR

~

REACTOR COOLANT SYSTEM LIHITIHG CONDITION TOR OPERATION Continued declax'e the leaking valve inoperable and isolate the high

'xessuze'oxtion of the affected system from the lov pressure portion by the use of a combination of at, least tvo closed'valves, one of vhich may be the OPERASLK check valve and the other. a closed de-energixed motox operated valve.

Verify the isolated'ondition of the closed de-enezgi.sed iotor operated valve at least once pex'4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be in't least HOT STANDBY vithin the next 6

hours and in COLD SHUTDMH vithin the follovtng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREHENTS 4.4.6.2.1 Reactor Coolant System leakages shall be dcmonstzatcd to be vithin each of the above limits by:

a

~

Honitoxing the containmcnt atmosphexe particulate radioactivity monitor at least once pcr 12 houxs.

b.

Monitoring thc containmcnt sump inventory 'and discharge at least once pcr 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

. c, 'Determining thc. seal.linc rcsi.stanba at least once:per 31 days

~

. vhcn thc ivezagc prcssurixcr 'prcssure's vithin 20 psi of its..

.nominal full pr'assure'alue.

The seal line resistance'easured duzing2the surveillance must be greater than or equal to 2.27 E-1 ft/gpm The seal line resistance, RSL, is determined from the folloving expression:

SL '( CHP SI

&&%%'0)%

'0'0 Q

vhere:

P~ ~ charging pump header prcssure, psig PS

~ 2112 paig (lov pxesaure operation)

SI 2262 psig (high preaauxe operation) 2.31 conversion factor (12 in/ft) /(62.3 lb/ft )

~ the total seal infection flov, gpm The pxovisions of Specification 4.0.4 are not applicablc for entry into MODES 3 and 4.

d.

Performance of a Reactox'oolant System vater inventory balance at least once per 72 houzs during steady state opezation, and COOX NUCLEAR PLANT -

UNIT.1 3/4 4-17 AMENDMENT HO. f+,

~ ~t~ ~il Al 1W1

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIRENENTS Continued l

e.

Monitoring. the. reactor head flange leakoff system at least once per'4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ..

pu~s c a~+ W'pa~lA cU~ $,0, 5.

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4.4.6.2.2 Each reactor coolant system ressure isolation valve specified in Table 3.4-0 shall-be demonstrated OPERABLE a.

After each refueling outage; b.

%bene r the pl t has bee n COLD SHUTD for 72 s or aore an f leaks testing s not been pe ormed in e previous 9

nths; Prior o returni the valve service f

loving, tenanc rep r or repla e=ent vork the valv ac%'K 4g

/

1L

,I'OOK NUCLEAR PLANT UNIT 1 3/4 4-17a

. ~NDHENT NO. 162' dated Ppri1 20, 1981

~

TABLE 3.4"0 REA TQR CflQlT Sv~

PRESSURE ISQLATQQN VALVE VALVE BER SI-170L2 RH133 S I-170L3 RH134 RJNCTIQN<'~

Low Head Safety Injection Loop 2, col leg Loop 3, old 1 eg

~ LA:;ps

,~ \\

I

. I",inimum test differe ia1 pressure shall not.be below 50 psid.

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COOK - UNIT 1

Ol der dated April 2Q 19B1

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REACTOR COO COOLANT.SYSTEM P'" 'o~~

.-'*~( 5 t( y~ Ss~r a<4~.

OPERATIONAL LEliXACE LIMITIHC COHDITION FOR OPERATION 3.4. 6.2 b.

Reactor Coolant System leakage shall be limited to:

1 Ho PRESSURE BOUNDARY UP~GE, 1 CM UNIDENTIFIED LEAXAGE, C ~

1 CPM total. primary-to-secondary Leakage through all steam generators and 500 gallons per day through any one steam generator, d.

10 CPM IDENTIFIED LEhXAGE from the Reactor Coolant System, 2

Seal line resistance greater than or equal to 2.27 E-1 ft/gpm, and APPLICABILITY:

MODES 1. 2.

3 aad ACTION::. :: '"':::.

~

r

~

a

. a.

Vith any PRESStJRE BOUNDARY LEhXACE', be in at Least HOT STANDBY.

vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOVN vithin the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Vith any Reactor Coolant System leakage'greater than any one of the above limits, excluding PRESSURE BOUNDARY'LFMACE, reduce the leakage rate to vithin limits vithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at, least HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOVH vithin the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

Vith any reactor coolant system pressure isolation valve(s)

AHEHDmmT HO.

146 Order dated Ppi l 20, 1981 pacify.cati.on 3.4.'6.2.e is appLicable vith average pressuriser pressure vithin 20 psi of the nominal full pressure value.

COOK NUCLEhR PLANT - UNIT 2 3/4 4-LS

~,

. ACTOR COOILHT SYSTEM LZMZTZHC COHDZTZOH POR OPZRATZOH Continued declare the leaking valve inoperable and isolate the high pressure portion of the affected system from the Lov pxessure portion by the use of at least two closed valves.

one of vhich may be the OPERQLE check vaLve and the other a closed de energised motor opexated valve.

Verify the isolated condition of the closed de-energized motor operated valve at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or be in at least HOT SThHDBY vt.thin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHQTDOVN vithin the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SQRVEZL1hHCE RE QZREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstxated to be vithin each of the above limits by:

a.

Monitoring the containment atmosphere particulate radioactivity

. monitor at least once per 12 houxs.

b.

Monitoring the containment sump inventory and discharge at'east once per 12 houzs.

c.

Determining the seaL line resistance at least once per 31 days vhen the 'average.pressurisar prcssuze is vf.tHin 20 psi of its noadnaL fu11,:pre'ssuri vaL'ue.

The. seal.Line resistance measured

,: during2the surveillance must be'eater than. or egal to 2.27 E-L ft/gpm. ~

The seal Line x'esistance, RS<, is deteriined from the foLLoving expression:

RSL 2.31 (PMP - PSI)

Q2 vhere:

P~ ~ charging pump header pressure, psig PSI 2262 psig (high pressure operation) 2.31 conversion factor (12 in/ft) /(62.3 lb'/ft )

~ the total seal injection flov, gpm The pxovisions of Specification 4.0.4 are not appLicable for entry into MODES 3 and 4.

d.

Performance of a Reactor Coolant System.vater inventory balance at

'east once pex 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months duxing steady state operation, and COOK NUCLEAR PIJLHT - QHIT 2 3/4 4-16 AHKHDMEHT HO ~

146 Order dated Peril 20, f981

REACTOR COOIhHT SYSTEH SURVEILLANCE RE U~NTS Continued e.

Monitoring the reactor head flange leakoff system at least once per 24 houxs.

4.4.6.2.2 Each reactor in Table 3.4-0 shall be 4

~

cool.ant system pressuxe isolation valve specified demonstrated OPERABLE pursuant to Specification a.

After h refueling outage; b.

nevex the lant has be in COLD SHUTDQ ox'2 ho ox more and if le age testin as not been pe ed in the evious 9

months I

c.

P or to xetu ing 'the valve o service fo oving maintena

~,

repair or placement vonk on the valv*.

COOK NUCLEAR PLANT - UNZT 2 3/4 4-16a hHENDMENT HO ~

GM dGtEf april +, le

TABLE, 3.4;0 REACTOR COOLANT SYSTBi PRESSURE ISOLATION VALYES VALYE NUMBER S

170L2 RHl 3 SI-17 $3 RH134 FUNCYNN Los-Head S

ety Injection Loop Z.

old leg Lo 3, cold 1 ea i

I 1

t

\\

I

.f Hi mum test differential pressure shall not be.below 150 psid.

O.C.

COOK - UNIT 2 3/4 4-16b Order dated April 20, 1981

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ATTACHMENT 3 TO AEP:NRC:1180A PROPOSED REVISED TECHNICAL SPECIFICATIONS PAGES

0 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

600 gallons per day total primary-to-secondary leakage through all steam generators and 150 gallons per day through any one steam generator for Fuel Cycle 14,-,

d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.

Seal line resistance greater than or equal to 2.27E-1 ft/gpmz and, f.

The leakage from each Reactor Coolant System Pressure Isolation Valves specified in Table 3.4-0 shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a Reactor Coolant System average pressure within 20 psi of the nominal full pressure value.

APPLICABILITY:

MODES 1, 2, 3 and 4.*

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 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 .

b:.'ith any.Reactor. Coolant.Syptem leakage: great'er than any one'f the above 'imits',

excluding PRESSER/

BOUNDARY L'EAKAGE, reduce the'eakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 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 .

c ~

With any reactor coolant system pressure isolation valve(s) leakage greater than the above limit, declare the leaking valve inoperable and isolate the high pressure portion of the affected system from the low pressure portion by the use of.a combination of at least two closed valves, one of which may be the OPERABLE check valve and the other a closed de-energized motor operated valve.

Verify the isolated condition of the closed de-energized motor operated valve at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 .

Specification 3.4.6.2.e is applicable with average pressure w'ithin 20 psi of the nominal full pressure value.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-16 AMENDMENT NO. 442-,

464-, 474

EACTOR COOLANT SYSTEM LIMITING CONDITIONS FOR OPERATION Continued SURVEILLANCE RE UIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ce Determining the seal line resistance at least once per 31 days when the average pressurizer pressure is within 20 psi of its nominal full pressure value.

The seal line resistance measured during the surveillance must be greater than or equal to 2.27 E-1 ft/gpmz.

The seal line resistance,

RSL, is determined from the following expression:

RSL 2'1 (PCHp PSI) where:

PCHP - charging pump header pressure, psig PSI - 2112 psig (low pressure operation) 2262 psig (high pressure operation) 2,31 - conveision:factor (12 in/ft) /(62.3 lb/ft.,)

I the total seal injectibn flow, gp'm The provisions of Specification 4.0.4 are not applicable for entry into MODES 3 and 4.

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during ',steady state operation, and e.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.6.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4-0 shall be demonstrated OPERABLE pursuant to Specification 4.0.5.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-17 AMENDMENT NO.

h TABLE 3 4-0 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE Valve Number Valve Size (in.)

Function (

Maximum Allowable Leakage (gpm)

SI-170L2 10 RH 133 8

SI-170L3 10 RH 134 8

ECCS to Reactor Coolant Loop ¹2 Cold Leg RHR to Reactor Coolant Loop ¹2 Cold Leg ECCS to Reactor Coolant Loop ¹3 Cold Leg RHR to Reactor Coolant Loop ¹3 Cold Leg I

) Minimum test differential pressure shall not be below 150 psid'.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-17a AMENDMENT NO.

This page intentionally left blank COOK NUCLEAR PLANT - UNIT 1 3/4 4-17b AMENDMENT NO.

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.

Seal line resistance greater than or equal to 2.27E-1 ft/gpmz and, f.

The leakage from each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-0 shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a Reactor Coolant System average pressure within 20 psi of the nominal full pressure value.

APPLICABILITY:

MODES 1',-2, 3 and 4.*

ACTION'.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 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 .

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 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 CQLD <SHUTDOWN within the follow'ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With any reactor coolant'ystem pressure isolation valve(s) leakage greater than the above limit, declare the leaking valve inoperable and isolate the high pressure portion of the affected system from the low pressure portion by the use of at least two closed valves, one of which may be the OPERABLE check valve and the other a closed de-energized motor operated

valve, Verify the isolated condition of the closed de-energized motor operated valve at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 .

Specification 3.4.6.2.e is applicable with average pressurizer pressure within 20 psi of the nominal full pressure value.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-15 AMENDMENT NO. 444

REACTOR COOLANT SYSTEM LIMITING CONDITIONS FOR OPERATION Continued SURVEILLANCE RE UIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by; a.

Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Monitoring the containment sump inventory and discharge at least once per,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C.

Determining the seal line resistance at least once per 31 days when the average pressurizer pressure, is within 20 psi of its nominal full pressure value.

The seal line resistance measured during the surveillance must. be greater than or equal to 2.27 E-1 ft/gpmz.

The seal line resistance,

RSL, is determined from the following expression:

R 2.31 (P

P

)

CHP SI A

Q where:

PCHP charging pump header pressure, psig PSI - 2262 psig (high pressure operation) 2.31 - conversion factor (12 in/ft)2/(62.3 lb/ft3)

Q

- the total seal injection flow, gpm The provisions of Specification 4.<0:4 are not appli'cable for entry into MODES 3 and 4.

d.

Performance of a Reactor Coolant System water inventory balance at lea'st once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during steady state operation, and e.

Monitoring the reactor head, flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.6.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4-0 shall be demonstrated OPERABLE pursuant to Specification 4.0.5.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-16 AMENDMENT NO. 446

TABLE 3 4-0 EACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE Valve Number Valve Size (in.)

Function (

Maximum Allowable Leakage (gpm)

SI-170L2 10 RH 133 8

SI-170L3 10 RH 134 8

.ECCS to Reactor Coolant Loop ¹2 Cold Leg RHR to Reactor Coolant Loop ¹2 Cold Leg ECCS to Reactor Coolant Loop ¹3 Cold Leg RHR to Reactor Coolant Loop ¹3 Cold Leg 5

) Minimum test differential pressure shall not be below 150 psid.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-16a AMENDMENT NO. 444

This page intentionally left blank COOK NUCLEAR PLANT - UNIT 2 3/4 4-16b AMENDMENT NO.

This page intentionally left blank COOK NUCLEAR PLANT - UNIT 2 3/4 4-16b AMENDMENT NO. 444

ML17332A345

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