Text

Amend 66 to License NPF-30,revising Tech Specs to Change Max Allowable Leakage Rate of RCS Pressure Isolation Valves
	ML20091Q399
Person / Time
Site:	Callaway
Issue date:	01/24/1992
From:	Hannon J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20091Q406	List: ML20091Q399; ML20091Q407;
References
	NUDOCS 9202040377
	Download: ML20091Q399 (9)
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UNION ELECTRIC COMPANY CAllAWAY PLANT, UNIT 1 DOCKET NO. STN 50 483 AMENUMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-30 1.

The Nuclear Regulatory Consnission (the Connission) has found that:

A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated March 15, 1991, as clarified by letters dated August 15, 1991, and January 23, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter 1; B.

The facility will operate in conformity with the appilcation, the provisions of the Act, and the rules and regulations of the Conunissiont C.

Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted

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in compliance with the Connission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

According1,thelic.enseisamendedbychan!estotheTechnicalSpecifica-2.

tionsasifdicatedintheattachmenttothi license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 66, and the Environmental Protection Plan contained in Appendix 0, both of which are attached hereto, are hereby incorporated into the license.

UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR Tite NUCLEAR REGULATORY COMMISSION

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,/ John N. Hannon

, Lirector Project Directorate 111-3

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Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes t se Technical Specifications Date of issuance: Janua ry 24. 1992 t

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ATTACHMENT TO LICENSE AhtHDMENT NO. 66 OPERATING LICENSE NO. NPF 30 DOCKET NO STN $0-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by tne captioned amendment number and contain marginal lines indicating the area of change. Corresponding overicaf pages are provided to maintain document completeness.

REMOVE INSERT S/4 4-19 3/4 4-19 l

i 3/4 4 21 3/4 4-21 B 3/4 4-5 B 3/4 4-5 i

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REACTOR COOLANT SYSTEM CPE M TIONAL LEAKAGE LIMll!NG CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

1 gpm UN! DENT!r!ED LEAKAGE.

c.

I gpm total reactor-to-secondary leakage through all steam generators not isolated from the Reactor Coolant System and 500 gallons per day through any one steam generator, d.

10 gpm IDENT!FIED LEAKAGE from the Reactor Coolant System, e.

8 gpm per RC pump CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 1 20 psig, and f.

The leakage from each Reactor Coulant System Pressure Isolation Valve specified in Table 3.4-1 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 pressure of 2235 1 20 psig.*

APPLICABILITY: MGDES 1, 2, 3, and 4.

ACT!0N:

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.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE B0UNDARY LEAKAGE and leakage from l

Reactor Coolant System Pressure Isolation Valves, 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 , c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, 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-HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with an RCS pressure of less than 600 psig.

Test pressures less than 2235 psig but greater than 150 psig are allowed.

Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure differential to the one-half power.

CALLAWAY, UNIT 1 3/4 4-19 Amendment No. 66 1

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.9 REAC, TOR COOLANT SYSTE'4 A

SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

fionitoring the containment atmosphere gaseous or particulate i

a, radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

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b.

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

.4easurement of the CONTROLLED LEAKAGE from the reactor coolant' pump c.

seals when the Reactor Coolant System pressure is 2235 t 20 psig at least once per 31 days.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d,

forformance-of a Reactor Coolant System water inventory balance at least once per-72 hours; and Monitoring the Reactor Head Flange Leakoff System at least once per e.

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 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:-

-a.

At least once per 18 months; b.

Prior to entering 110DE 2 whenever the unit has been in COLD SHUTDOWN for 7J nours or more and if leakage testing has not been performed in the previous 9 months; Prior to returning the valve to service following maintenance, c.

repair or replacement work on the-valve; and d.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve except-for valves BBPV8702 A/B and EJHV8701 A/B.

The-provisions of Specification 4.0.4 are not appitcable for entry into MODE 3 or 4.

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- CALLAWAY - UNIT 1 3/4 4-20

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TABLE 3.4-1 REACTOR COOLANT SYSTEH PRESSURE ISOLATION VALVES MAXIMUM VALVE VALVE ALLOWABLE NUMBER SIZE (in.)

FUNCTION LEAKAGE (qpm)

BB8948A 10 RCS Loop 1 Cold Leg SI Accu Chek 5.0 BB894BB 10 RCS Loop 2 Cold Leg SI Accu Chek 5.0 BBB948C 10 kcS Loop 3 Cold Leg SI Accu chek 5.0 BBB94BD 10 RCS Loop 4 Cold Leg SI Accu Chek 5.0 BBB949A 6

RCS Loop i

$t Leg SI/RHR Pump Chek 3.0 BB8949B 6

RCS Loop 2 t'.ut Leg SI/RHR Pump Chck 3.0 BBB949C 6

RCS Loop 3 Hot Leg SI/RHR Pump Chck 3.0 BB8949D 6

RCS Loop 4 Hot Leg SI/RHR Pump Chek 3.0 BBV0001 1.5_

RCS Loop 1 Cold Leg SI/ BIT Chek 0.75 BBV0022 1.5 RCS Loop 2 Cold Leg SI/ BIT Chck 0.75 BaV0040 1.5 RCS Loop 3 Cold Leg SI/ BIT Chek 0.75 BBV0059 1.5 RCS Loop 4 Cold Leg SI/ BIT Chck 0.75 BBPV8702A 12 RCS Loop 1 Hot Log to RHR Pumps ISO 5.0 BBPV8702B 12 RCS Loop 4 Hot Leg to RHR Pumps ISO 5.0 EJ8841A 6

RHR TRNS SIS Hot Leg Loop 2 Recire 3.0 EJ8841B 6

RHR TRNS SIS Hot Leg Loop 3 Recirc 3.0 EJHV8701A 12 RHR Pump A Suction ISO 5.0 EJHV8701B 12 RHR Pump B Suction

'"O 5.0 EMV0001 2

SI Pump A Disch to 7t Leg Loop 2 Chek 1.0 EMV0002 2

SI Pump A Disch to Hot Leg Loop 3 Chek 1.0 EMV0003 2

SI Pump B Disch to Hot Leg Loop 1 Chck 1.0 EMV0004 2

SI Pump B Disch to Hot Leg Loop 4 Chek 1.0 EM8815 3

BIT C'!CS Out Check 1.5 EPV0010 2

SI Pumps to RCS Cold Leg Loop 1 Chek 1.0 EPV0020 2

SI Pumps to RCS Cold Leg Loop 2 Chek 1.0 EPV0030 2

SI Pumps to RCS Cold Leg Loop 3 Chek 1.0 EPV0040 2

SI Pumps to RCS Cold Leg Loop 4 Chck 1.0 EP8818A 6

RHR Pumps to RCS Cold Leg Loop 1 Chck 3.0 EP8818B 6

RHR-Pumps to RCS Cold Leg Loop 2 Chek 3.0" EP8818C 6

RHR Pumps to RCS Cold Leg Loop 3 Chek 3.0 EP8818D 6

RHR Pumps to RCS Cold Leg Loop 4 Chck 3.0 EP8956A 10 SI Accu TK A out Upstream Chek 5.0 EP8956B 10 SI Accu Tk B out Upstream Chek 5.0 EP8956C 10 SI Accu TK C Out Upstream Chek 5.0 EP8956D 10 SI Accu TK D Out Upstream Chek 5.0 CALLAWAY - UtilT 1 3/4 4-21 Amendment No. 66

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REACTOR COOLANT SYSTpf 3L_4.4.7 CHEMISTRY LIMITING CONDITION FOR_0PERATION 3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-2.

APPLIGABILITY:

At all times.

ACT!0'(:

MODES 1, 2, 3. and 4.

a.

With any one or more chemistry parameter in excess of its Steady-State Limit but within its Transient Limit, restore the parameter to within its Steady-State Limit within 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 , b.

With any one or more chemistry parameter in excess of its Transient Limit, 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 .

At All Uther Times:

With the concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady-State Limit for nore than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or in excess of its Transient Limit, reduce the pressurizer oressure to less than or equal to 500 psia, if applicable, and perform an enoineerinq evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation prior to increasing the pressurizer pressure above 500 psig or prior to proceeding to MODE 4.

i SURVILLANCE REQUIREMENTS l

4.4.7-The Reactor Coolant System chemistry shall be determined to be within the limits by analysis of those parameters at the frequencies specified in Table 4.4-3.

l CALLAWAY - UNIT 1 3/4 4-22

REACTOR COOLANT SYST O BASES OPERATIONAL LEAKAGE (Continued)

The leakage fron any RCS pressure isolation valve is sufficiently l

low to ensure early detection of possible in-series check valve failure.

It is apparent that when pressure isolation is provided by two in eries check valves and when failure of one valve in the pair Can go undetected for a sub-stantial length of time, verification of valve integrity is required.

Since these valves are important in preventing overpressurization and rupture of the ECCS low pressure piping which would result in a LOCA that bypasses con-tainment, these valves should be tested periodically to ensure low probability of gross failure.

The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probabilit/ of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

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 eftect on the structural integrity of the Reactor Coolant System.

The time interval parmitting 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.

The Surveillance Requirements provide adequate assurance that concentra-tions in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolar.t ensure that the resJiting 2-hour doses o the SITE BOUNDARY will not exceed an appropriately s N il traction of 10 CFR part 100 dose guideline values following a steam generator tube rupture ac.ident in conjunction with an assumed steady state reactor-to-secondary steam generator leakage rate of 1 gpm.

The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations.

These values are conservative in that specific site parameters of the Callaway site, such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.

CALLAWAY - UNIT I B 3/4 4-S Amendment No. 66

REACTOR COOLANT SYSTEM BASE 5 SPECIFIC ACTIVITY (Continued)

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 1 microcurie / gram DOSE EQUIVALENT l-131, but within the allowable limit shown on Figure 3.4-1, acconmodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.

Reducing T,yg to less than 500*F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the reactor coolant 15 below the lif t pressure of the atmospheric steam relief valves.

The Surveillance Requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomen.

A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.

3/4.4.9 PRESSURE / TEMPERATURE LIMITS The temoerature and pressure changes during heatup and cooldown are limited to be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code Section III, Appendix G:

1.

The rear. tor coolant temperature and pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with figures 3.4-2 and 3.4-3 for the service period specified thereor :

a.

Allowable combinations of pressure and temperature for specific temperature change rates are below and to the right of the limit lines shown. _ Limit lines for cooldown rates between those presented may be obtained by interpolation, and b.

Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only.

For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be-achieved over certain pressure-temperature ranges.

CALLAWAY - UNIT 1 B 3/4 4-6 Amendment No. 27

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ML20091Q399

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