Text

Amend 57 to License NPF-47,revising TSs 4.0.5,3.4.3.1 & 3.4.3.2 Re Inservice Insp,Leak Detection & Actions Taken When Leakage Limits Exceeded & Revised Bases of TS 3/4.4.3.1
	ML20073R493
Person / Time
Site:	River Bend
Issue date:	05/31/1991
From:	Dick G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20073R494	List: ML20073R493; ML20073R497;
References
	NUDOCS 9106100097
	Download: ML20073R493 (11)
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UNITED STATES 5 ' !:

i NUCLEAR REGULATC1RY COMMISSION 1( I!5/ f WASHINoTON, O C. 20566 g

%,...../

GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENI TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-47 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Gulf f tates Utilities Compaif (the licensee) dated June 4,1990 a.1d supplemented by letters dated Feb ruary 13, 1991, April 11, 1991, and May 2,1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and tne Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions' of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:

D.

The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.

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9106100097 910531 ADOCK 050 g 8 DR

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicat.ed in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating l.icense No. NPF-47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications cont 3ined in Appendix A, as revised through Amendment No. 57 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

'50 shall operate the f acility in accordance with the Technical

.ecifications and the Environmental Protection Plan.

3.

lhe license amendment is effective as of date of issuance to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION t (' 'V- -

Georgd/ F. Dick, Act4 ng Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 31, 1991 i

ATTACNMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. NPF-47 00CKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change, The overleaf pages i

are provided to maintain document completeness.

REMOVE INSERT 3/4 0-3 3/4 0-3 3/4 4-10 3/4 4-10 3/4 4-11 3/4 4~11 3/4 4-12 3/4 4-12 8 3/4 4-3 B 3/4 4-3 B 3/4 4-3a B 3/4 4-4 8 3/4 4-4 l

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APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology '.r inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 day-Every 9 months At least once per 276 day.

Yearly or annually At least once per 366 days

c..

The provisions of Specification 4.0.2 are applicable to the above required frequer.cies for performing inservice inspection and testing activities, d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements, e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

f.

The Inservice Inspection Program (ISI) for piping susceptible to Inter-I granular Stress Corrosion Cracking (IGSCC) shall be performed in accord-ance with the NRC positions included in Generic Letter 88-01.

RIVER BEND - UNIT 1 3/4 0-3 Amendment No. 57

REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET F'JNCTION LIMITING CONDITION FOR OPERATION 3.4.2.2 safety / relief valves shall be OPERABLE with the foll o ant system settings:

Low-Low Set Function Valve No.

Setpoint* (psig) i 15 psi Open Close _

1821*RVF051D 1033 1821*RVF051C 926 1073 1B21*RVF051B 936 1113 IB21*RVF051G 946 1113 IB21*RVF047F 946 1113 946 MPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the low-low set function of one of the above a.

coolant system safety /reliet required reactor relief valve function and the low-low set function tr OPERABLE within 14 days or be in at least HOT SHUTDOWN within th and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months status e next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months b.

With the low-low set function of more than one of e above required HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOW

, be in at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

within the next With either low-low set function pressure actuati c.

or "B" inoperable, restore the inoperable trip system to OPERABLE on trip system "A" status within 7 days; otherwise, be in at-least HOT SHUTDOWN 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 h within ours.

SURVEILLANCE REQUIREMENT 4 4.4.2.2.1 be demonstrated OPERABLE by performance of a:The low-low set f a on shall CHANNEL FUNCTIONAL TEST a.

setpoint, at least once,per M u,sys.incheinn calibration of the trip unit b.

matic operation of tha cr. tire system at least onc simulated auto-n

The lift ietting pressure shall correspond to er 18 months.

at nominal operating temperatures and pressures.bient conditions of the valves am RIVER BEND - UNIT 1 3/4 4-9

REACTOR COOLANT SYSTEM OPERATIONS LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAJE.

c.

25 gpm total leakage (averaged over any 24-hour period).

d.

0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm leakage at a reactor coolant system pressure of 1025 1 15 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.2.2-1.

e.

2 gpm UNIDENTIFIED LEAKAGE increase within any period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less (Applicable in OPERATIONAL CONDITION 1 only).

APPLICABILITY:

OPERATIONAL CONDITIONJ 1, 2 and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWh within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 20WN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With any reactor coolant system pressure isolation valve leakage greater than tha above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two other closed manual, deactivated automatic or check

valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-2 inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm point at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The provisions of Specifi-cation 3.0.4 are not applicable.

e.

With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than the liniits in e., above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months identify the source of leakage es not IGSCC susceptible material or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Which have been verified not to exceed tne allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.

RIVER BEND - UNIT 1 3/4 4-11 Amendment No. 57

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REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION LIMITING CONDITION FOR OPERATION 3.4.2.2 The low-low set function of the following reactor coolant system safety / relief valves shall be OPERABLE with the following settings:

Los-Low Set Function Setpoint* (psig) 1 15 psi Valve No.

Open Close 1B21*RVF0510 1033 926 1821*RVF051C 1073 936 1821*RVF051B 1113 946 1821*RVF051G 1113 946 1821*RVF047F 1113 946 APPLICABILITY:

0FERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the low-low set function of one of the above required reactor a.

coolant system safety / relief valves inoperable, restore the inoperable relief valve function and the low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the low-low set function of more than one of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With either low-low set function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2.2.1 The low-low set function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL FUNCTIONAL TEST, including calibration of the trip unit setpoint, at least once per 31 days, b.

CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated auto-matic operation of the entire system at least once per 18 months.

The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

I RIVER BEND - UNIT 1 3/4 4-9

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The drywell atmosphere particulate radioactivity monitoring syster, a.

b.

The drywell and pedestal floor sump drain flow monitoring

systems, Either the drywell air coolers condensate flow rate monitoring c.

system or the drywell atmosphere gaseous radioactivity monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With leak detection systems 'a' and/or 'c' inoperable operation may a.

continue for up to 30 days provided grab samples are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the inoperable radiation monitors; otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With the drywell floor and/or pedestal sump drain flow monitoring subsystem inoperable, operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demon-strated OPERABLE by:

a.

Drywell atmosphere particulate and gaseous monitoring systems-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION l-at least once per 18 months.

b.

The sump drain flow monitoring systems performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.

c.

Drywell air coolers condensate flow rate monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

d.

Flow testing the drywell floor drain sump inlet piping for blockage at least once per 18 months.

RIVER BEND - UNIT 1 3/4 4-10 Amendment No. 57

REACTOR-COOLANT SYSTEH OPERATIONAL' LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 -Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE.

c.

25 gpm total leakage (averaged over any 24-hour period).

d.

0.5 gpm per nomincl inch of valve size up to a maximum of 5 gpm leakage at a reactor coolant system pressure of 1025 1 15 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

e.

2 gpm UNIDENTIFIED LEAKAGE increase within any period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less (Applicable in'0PERATIONAL CONDITION 1 only).

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With-any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , With any reactor coolant system pressure isolation valve leakage greater c.

than the above limit, isolate-the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least y

two other closed manual, deactivated automatic or check

valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , d.

With_one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.-2-2 inoperable, restore the inoperable monitor (s) to OPERABLE status within ? days or verify the pressure-to be less than the alarm point-at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The-provisions of Specifi-E cation 3.0.4 are_not applicable.

1 e.

With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than the limits in e., above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months identify the source of leakage os not IGSCC susceptible material or be in at least H0T SHUTDOWN within.the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time'the valve was disturbed, whichever is more recent.

RIVER BEND - UNIT 1-3/4 4-11 Amendment No. 57

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

Monitoring the drywell atmospheric particulate radioactivity at least a.

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Monitoring the sump flow rates at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

Monitoring the drywell air coolers condensate flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and d.

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

4,4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 including paragraph IWV-3427(B) of the ASME Code and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance, repair or replacement work oa the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.

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RIVER BEND - UNIT 1 3/4 4-12 Amendment No. 7, 57 w

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REACTOR COOLANT SYSTEM 3/4.4 REACTOR COOLANT SYSTEM BASES SAFETY / RELIEF VALVES (Continued)

Demonstration of the safety relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.

The low-low set system ensures that safety / relief valve discharges are minii : zed for a second opening of these valves, following any overpressure transient.

This is achieved by automatically lowering the closing setpoint of 5 valves and lowering the opening setpoint of 2 valves following the initial opening.

In this way, the frequency and magnitude of the containment blowdown duty cycle is substantially reduced.

Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis.

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECT:0N SYSTEMS The RCS leakage detect on systems required by this spec'fication are provided to monitor and detect leakage from the reactor coolant pressure boundary.

These detection systemc are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems", May 1973.

In conformance with Regulatory Guide 1.45, the atmospheric gaseous radioactivity system will have a sensitivity of 10 6 pCi/cc.

The drywell and pedestal floor sump drain flow monitoring systems consist of 2 sumps with one level transmitter and two 100% pumps each.

The level trans-mitters feed Main Control Room level indicators as well as various automatic control systems.

Each of the automatic systems calculate leakage, control pumps and provide annunciation.

The leak rate may be determined by the automatic sys-tem or a manual procedure through the use of the level indication and pump con-trol _ switched located in the main control room.

The substitution of grab samples for tne drywell particulate and gaseous monitors is to allow for continued moni-toring of the function while normal components are inoperable.

3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based

-on the predicted and experimentally observed behavior of cracks in pipes.

The normally expected background leakage, due to equipment design and the detection capability of the instrumentation for determining systam leakage, was also considered.

The evidence obtained from experiments suggests that, for leakage screwhat greater than that specified for UNIDENTIFIED LEAKAGE, the probability is small that the imperfection or crack associated with such leakage would grow rapidly.

However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shut down to allow further investigation and corrective action.

RIVER BEND - UNIT 1 B 3/4 4-3 Amendment No. 57

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REACTOR COOLANT SYSTEM 3/4.4 REACTOR-COOLANT SYSTEM BASES 3/4.4.3.2 OPERATIONAL LEAKAGE (Continued)

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

Leakage from the RCS pressure isolation valves is IDENTIF'k) trAKAGE and will be considered as a portion of the allowed limit.

RIVER BEND - UNIT 1 B 3/4 4-3a Amendment No. 57

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REACTOR COOLANT SYSTEM BASES 3/4.4.4 ~ CHEMISTRY The water chemistry lit.its of-the reactor coolant are established to prevent damage to the reactor materials in contact with the coolant.

Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.

The effect of chloride is not as great when the oxygen. concentration in the coolant is low; thus the 0.2 ppm limit on chlorides is permitted during POWER

' OPERATION.

During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.

Conductivity measurements are required on a continuous basis since-changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides and-other impurities affecting conductivity must also be within their acceptable limits. With the conductivity _

meter inoperable, additional samples must be analyzad to ensure that the chlorides are not exceeding the 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.

3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid and whole body doses resulting.from-a main steam line failure 'outside the containment during steady state operation will not exceed small fractions of the. dose guidelines of 10 CFR 100.

The values for the limits on specific activity represent interim limits-based upon a parametric evaluation

by the: NRC. of typical site locations.

These values are conservative-in that specific site parameters such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statement permitting POWER OPERATION to continue for limited time periods, with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 but less than or equal to 4.0 micro-curies'per gram DO5E EQUIVALENT I-131, accommodates possible iodine spiking phenomena'which may occur following changes in THERMAL-POWER.

. _ Closing the main steam line isolation valves prevents the release of L

activity to the environs should a steam line rupture occur outside containrr.ent.

The surveillance requirements provide adequate assurance that excessive-specific activity _ levels-in the reactor. coolant will be detected in sufficient time to take corrective a'. tion.

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RIVER BEND - UNIT 1

_B 3/4 4-4

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ML20073R493

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