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Proposed TS 3/4.6.2, RCS Operational Leakage, Reflecting Deletion of Table 3.4-0, RCS Pressure Isolation Valves, LCO 3.4.6.2f & Action C & SRs 4.4.6.2.2 for Both Units
	ML17331B060
Person / Time
Site:	Cook
Issue date:	11/15/1993
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17331B059	List: ML17331B058; ML17331B060;
References
	NUDOCS 9311190232
	Download: ML17331B060 (27)
	v • d • e

ATTACHMENT 2 TO AEP:NRC:1180 MARKED-UP TECHNICAL SPECIFICATION PAGES 9311190232 931115" PDR ADOCK,,05000315

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CTOR C 0 N E G GCND ON R P 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY IKlKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE,

c. '00 gallons

'I per day total primary-to-secondary leakage through all steam generators and 150 gallons per day through any one steam generator for Fuel Cycle 13, de I.Q GEE ZDEETZEZED LF~GE f om ehe eEssedo. GolososSystemGI,ZCl

e. Seal line resistance greater than or equal to 2.27E-1 ft/gpm~ end, APPLICABILITY: MODES 1, 2, 3 and 4.~+

ACTION:

Pith 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. Vi.th any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits vithin 4 houzs 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 SHUTDOWN within the follovtng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Specification 3.4.6.2.e is applicable vith average pressure vithin 20 psi of the nominal full pressure value.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-16 AMEHDMENT NO.

REACTOR COOLLHT SYSTEM LZMZTZHG COHDZTZOH TOR OPERATXOH Continued SURVEZLIANCE RE UXREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be vithin each oi the abave limits by:

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

b. Monitoring the containment sump inventory and di.scharge 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 vhen the average pressurizer pressure is vithin 20 psi of its nominal full pressure value. The seal line resistance'easured duxing2the surveillance must be gzeatez than or equal to 2.27 E-1 ft/gpm . The seal line zesistance, RSL, is determined from the folloving ezpzession:

SL 2'31 ( CHp SZ 2

Q vhere: P ~ charging pump header pressure, psig P

SZ Z

- 2112 psig (lav pressure operation) 2262 psig (high pressure opezati.on) 2.31 ~ conversion factor (12 in/ft)2 /(62.3 lb/ft3 )

the total seal injection flav, gpm The provisions of Specification 4.0.4 are not applicable for entry into MODES 3 and 4.

d. Performance of a Reactoz Coolant System vatez inventory balance at least once per 72 houzs during steady state operation, and COOK NUCLEAR PLANT - UNXT 1

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3/4 4-17 AMENDMENT HO.~

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VALYE NUMBE Lmr Head Safety Injection 5 I-170L2 Loop 2, cold leg RH133 SI-1 Loop 3, ld 1 eg 4

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O Co Zaintaining an operating leakage 1&d.t of 150 gpd per steam gene ator (600 gpd total). fox Fuel Cycle 13 vill mindi=e the potential for a large 3.eakage event during steam line break under LOCh. conditions. Eased on the HDE uncertainties, bobbin coil voltage distribution and c ack grovth rate the previous inspection, the expected leak rate folloving a steam l&e 'rom xuptu=e i.s limited to belier 120 gpm in the faulted loop and 150 gpd pe steam gene ator in the intact loops, vhich vill limit offsite doses to vithin 3.0 pezcent of the 10 CFR 100 guidelines. Zf the projected end of cycle dist ibution of c ack indications x'esults in pr9nazy-to-secondary leakage greater than 120 gpm in the faulted loop during a postulated steam f

line break event, additional tubes must be removed om service in orde to educe the postulated pxixzzy-to-secondary steam line break leakage to belov 120 gpm.

PRESSURE BOUNDARY ~v!XAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Should PRESSURE BOUNDARY ~<%AGE occur thxough. a component vhich can be isolated from the balance of the Reactor Coolant'ystem, plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since isolation removes the source of potential faQu e.

3 4.4.7 CHEMTSTRY The 1Mtations on Reactor Coo3.ant System chemist~ ensu=e that corrosion of the Reactor Coolant System is minimized and xeduces the potential fox'eactor Coolant System leakage or failure due to st=ess cox osion. Eaintaining the chemistry vithin the Steady State Limits provides ade~te coxrosion protection to ensuxe the stxucmal integrity of the Reactor Coolant System over the 3.ife of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits axe time and temperat~e dependent. Corrosion studies shov that operation may be continued Wth contaminant concent ati.on levels in es:cess of the Steady State Limits, up to the Transient Limits, for the specified limited time internals vithout having a significant ~ffect on the sutural integrity of the Reactor Coolant System. The time interval permitting continued operation vithin the restrictions of the Transient LLmits provides time for taking corrective actions to restoxe the contaminint concentrations to vithin the Steady State Limits.

COO@ NUCLEAR PLANT - UNZIP 1 B 3/4 4-4 AK?NDK2iT NO. ~

REACTOR COOIAFT SYSTEM OPERATIONAL LEAXACE LZMZTINC CONDITION FOR OPERATION

, 3.4,6.2 Reactor Coolant System leakage shall be Limited co:

'I a . No PRESSURE BOUNDARY LEAXAGK,

b. 1 CHf UNIDENTIFIED LEhKACK, c.. 1 CPM; totaL primacy-co-secondary'eakage through all steam generacors and 500 gallons per day through any one steam generator,

d. 10 CPM IDENTIFIED LEAKAGE from the Reactor CooLant System)

e. Seal Line resistance greater chan ar equal to 2.27 E-1 ft/gpm2 e APPLZCABXLZTY: MODES 1, 2, 3 and 4'5 ACTXON:

aa Vith any PRESS%X BOUNDARY ~AGE', be in ac least HOT STA.'iDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN vithin the follaving 30 hours.

Vi.th any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY ~~ CE, reduce the leakage rate co vichin 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 vichin che next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN vithin the follovtng

-measly 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f @Specification 3.4.6.2.e is applicable vith "vithin 20 psi of the nominal

- UNIT full pressure average pressuriser value.

pressure hHRGNEC NO. ~

COOT NUCLEAR PLANT 2 3/4 4-15

~ ~

~CTOg, COOZhHT SYSTEM SURVZILLhBCE RE UERRKHTS Continued

e. Monitoring the teactoz.head fLange leakoff agate't Laaat once per 24 hem's.

I

~ ~ ~

COOK NUCLKhR PlhBT - UNXT 2 3/4 4-164 hHENlENT HO.~

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REhCTOk COOLLHT STS~

lASES The limitation on seal line resistance ensures that the seal line resistance is gzeataz than oz equal to the zasistance assumed in che minimum safeguazds LOCh analysis. This analysis assumes that all of the flov that is divezted fzom the bozon injection line to the seal injection line is unavailable for core coolLng.

The total steam generator tube leakage limit of 1 GPK for all steaa genezators not isolated from the RCS ensures thar. the dosage contribute.on from the tube leakage vill be limited to a small fraction of Part 100 limits in the'vent of either a stcam generator tube rupture or steam line break. The 1 GPM limit is consistent. vith the assumptions used Ln the analysis of these accidents. The 500 gpd leakage limit pez steam generator ensuzes that stcam generator tube integrity is maintained in the event of a main stcam lLne rupture oz undez LOCh cond'tions.

PR SSURE BOUNDhRY ~~GE of any magnitude L,s unacceptable since it may. be indicatL.vc of an impending gross failuzc of the pressure boundary.

Should PRESSURE BOUNDARY ~~GE occur through a component vhich can be isolated from the balance of the Reactor Coolant System, plant operation may continue provt.dcd the leaking component is promptly isolated from the Reactor Coolant System since isolation removes thc source of potential failuze .

The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential foz Reactor Coolant System leakage or failure due to stress corrosion. maintaining the chcmistzy vithin the Steady State Limits provides adequate corrosion pzotection to ansuze the stzuctural integrity of the Reactoz Coolant System over the 1Lfa of the plant. The associated effects of exceeding the oxygen, chlorLde, and fluoride limits aze time and tempezatuze dependent. Corzosion studies shov that operation may be continued vith concaminant concentzatLon levels in excess of the Steady State LLmits, up to the Tzansicnt Limits, for the specified limited time intezvals vithout having a significant effect on the structu=al integrity of the Reactor Coolant System. The time interval permitting continued operation vithin the rcstrLctions of thc Transient Limits provides time foz taking cozrective actions to restore thc contiminant concentrations to vithin the Steady State Limits.

COOK NUCLEhR- PLhNT - UNZT 2 B 3/4 4"4 hMENDNRiT NO ~ ) >gal

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

) ~

REACTOR COOLANT SYSTEM OP RATIONA 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 13,

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and

e. Seal line resistance greater than or equal to 2.27E-1 ft/gpm~.

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 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 within 20 psi of the nominal full pressure value.

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

REACTOR COOLANT SYST 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 4 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/gpm2. The seal line resistance, Rs<, is determined from the following expression:

Rsz. - 2.31 (PcHp - Psz)

Q2 where: PcHP - charging pump header pressure, psig Psz - 2112 psig'low pressure operation) 2262 psig (high pressure operation) 2.31 conversion factor (12 in/ft) /(62.3 lb/ft )

Q - the total seal injection flow, gpm 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 .

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

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

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

REACTOR COOLANT SYSTEM BASES Maintaining an operating leakage limit of 150 gpd per steam generator (600 gpd total) for Fuel Cycle 13 will minimize the potential for a large leakage event during steam line break under LOCA conditions. Based on the NDE uncertainties, bobbin coil voltage distribution and crack growth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below 120 pgm in the faulted loop and 150 gpd per steam generator in the 'intact loops, which will limit offsite doses to within 10 percent of the 10 CFR 100 guidelines. If the projected end of cycle distribution of crack indications results in primary-to-secondary leakage greater than 120 gpm in the faulted loop during, a postulated steam line break event, additional tubes must be removed from service in order to reduce the postulated primary-to-secondary steam line break leakage to below 120 gpm.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Should PRESSURE BOUNDARY LEAKAGE occur through a component which can be isolated from the balance of the Reactor Coolant System, plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since isolation removes the source of potential failure.

3 4 4 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 4-4 AMENDMENT NO. R~

I REACTO COOLANT SYSTEM OPERAT ONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6,2 Reactor Coolant System leakage shall be limited to:

a ~ No PRESSURE BOUNDARY LEAKAGE, 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, and

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

ACTION' 0 With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours 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 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.

~ 6 I

I Q

REACTOR COOLANT SYS EM SURVEILLANCE RE U REMENTS 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, Rs<, is determined from the following expression:

2.31 (P~ - Psr)

Q2 where: P~ charging pump header pressure, psig Psz 2262 psig (high pressure operation) 2.31 - conversion factor (12 in/ft) /(62.3 lb/ft )

the total seal injection flow, gpm 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 .

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

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

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

C f

8 CTOR COOLAN SYS BASES The limitation on seal line resistance ensures that the seal line resistance is greater than or equal to the resistance assumed in the minimum safeguards LOCA analysis. This analysis assumes that all of the flow that is diverted from the boron injection line to the seal injection line is unavailable for core cooling.

The total steam generator tube leakage limit of 1 GPM for all steam generators not isolated from the RCS ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. The 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Should PRESSURE BOUNDARY LEAKAGE occur through a component which can be isolated from the balance of the Reactor Coolant System, plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since isolation removes the source of potential failure.

3 4 4 7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

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

4 1 0

~ V A

8

ML17331B060

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