ML17228B336

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Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15
ML17228B336
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 11/22/1995
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228B335 List:
References
RTR-NUREG-1432 NUDOCS 9511290223
Download: ML17228B336 (16)
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Text

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments RCS LEAKAGE DETECTION SYSTEMS ATTACHMENT 3 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 3/4 4-12 INSERT A Page 3/4 4-13 Page B 3/4 4-4 9511290223 95ii22 PDR ADOCK 05000335 P ~ 'AAht Vl -~ W'm r 3 4ll I

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION

.4.6.1 The following Reactor Coolant System leakage detection systems s all be OPERABLE:

A containment atmosphere particulate radioac6vity monitor ng system,

b. e reactor cavity sump level and flow monitoring sy em, and
c. A co ainment atmosphere gaseous radioactivity m itoring system.

APPLICABILITY: NOD 1, 2, 3 and 4.

ACTION:

a ~ Wi th one of the a ve required radi cti vi ty moni toring leakage detection systems i erable, ope tions may continue for up to 30 days provided:

1. The other two above e ared leakage detection systems are PE
2. Appropriate grab samples re obtained and analyzed at least once per 24 be in hours'therwise, a east HOT STA 8 Y within the next 6 .hours and in COLD SHUTDOWN nothin the followin 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b. With both the ove required radioacti 'ty monitoring leakage detection sy ems inoperable, operations ay continue for up 'to 30 days pr ided:
1. T reactor cavity sump level and flow m itoring system

,OPERABLE,

2. Appropriate grab samples are obtained and ana zed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
3. A Reactor Coolant System water inventory balance i per-formed at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during steady state operation except when operating in the shutdown coolin mode otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments RCS LEAKAGE DETECTION SYSTEMS INSE T - A 3.4.6.1 The following RCS leakage detection systems shall be OPERABLE:

a. The reactor cavity sump inlet flow monitoring system; and
b. One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTION%

a. With the required reactor cavity sump inlet flow monitoring system inoperable, perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the sump inlet flow monitoring system to OPERABLE status within 30 days'therwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours.
b. With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c. With all required monitors inoperable, enter LCO 3.0.3 immediately.
d. The provisions of Specification 3.0.4 are not applicable one of the required monitors is OPERABLE.

if at least SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a. Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.
b. Performance of the CHANNEL CALIBRATION of the required reactor cavity sump inlet flow monitoring system at least once per 18 months.

I 4 * ~ L EACTOR COOLANT SYSTEM 3/ 4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAG ETECTION SYSTEMS LIMITING C COITION FOR OPERATION Continued

c. With th containment sump level and flow monitoring stem in-operable, restore the inoperable system to OPERABLE status within 7 days or e, in at least HOT STANDBY within the ne t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUTD WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURYEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems s all be onstrated OPERABLE by:

a. Containment atmosphere gas ous d particulat monitoring systems-performance of CHANNEL HECK, CHANNEL IBRATION and CHANNEL FUNCTIONAL EST a the frequencies sp ified in Table 4.3-3, and
b. Reactor cavity sump evel a d flow monitoring system-pe ormance of CHANNEL CALIB ION TEST at least once per 18 months.

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REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEHS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant P. essure

- Boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reac or Coolant Pressure Boundary Leakage Detec-tion Systems", Hay 1973.

3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of th'. leakage can be reduced to "a threshold value of less than 1 .GPH.~i~ eshold value is sufficiently low to ensure early detection of additional leakage.

f The 10 GPH IOENTIFIEO LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The total steam generator tube leakage limit of 1 GPM for all steam generators 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 GPH limit is consistent with the assumptions used in the analysis of these accidents.

PRESSURE BOUNDARY LEAYAGE of any magnitude is unacceptab' since it may be indicative of an impending gross failure of the pressure boundary. There-fore, the presence of any PRESSURE'OUHDAPY LEAYAGE requir es the unit to be promptly placed in COLO SHUTDOWN.

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.

3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the. Reactor Coolant System is minimized and reduce the potential .or 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 ST LUCIE - UNIT 1 B 3/4 4-4 The LCO is consistent with NUREG-1432, Revision 1, and is satisfied when leakage detection monitors of diverse measurement means are OPERABLE in MODES 1, 2, 3, and 4. Monitoring the reactor cavity sump inlet flow rate, in combination with monitoring the containment particulate or gaseous radioactivity, provides an acceptable minimum to assure that unidentified leakage is detected in time to I allow actions to place the plant in a safe condition when such leakage indicates I

'ossible pressure boundary degradation.

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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments RCS LEAKAGE DETECTION SYSTEMS ATTACHMENT 4 ST LUCZE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 3/4 4-18 INSERT B Page B 3/4 4-5

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r St. Lucie Unit. 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments RCS LEAKAGE DETECTION SYSTEMS INSE T - B 3.4.6.1 The following RCS leakage detection systems shall be OPERABLE:

a. The reactor cavity sump inlet flow monitoring system; and
b. One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTION:

a. With the required reactor cavity sump inlet flow monitoring system inoperable, perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b. With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c. With all required monitors inoperable, enter LCO 3.0.3 immediately.
d. The provisions of Specification 3.0.4 are not applicable one of the required monitors is OPERABLE.

if at least SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a. Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.
b. Performance of the CHANNEL CALIBRATION of the required reactor cavity sump inlet flow monitoring system at least once per 18 months.

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0 REACTOR COOLANT SYSTEM BASES LEAKAGE DETECTION SYSTEMS Continued)

II Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3/4.4. 6. 2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of le'akage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 gpm IDENTIFIED LEAKAGE limitation provides allowances for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

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 IDENTIFIED LEAKAGE and will be considered as a portion of the allowable limit.

The total steam generator tube leakage limit of 1 gpm for all steam generators 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 0.5 gpm leakage limit per steam generator ensures that steam generator tube integr ity 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.

Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

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 fai lure due to stress corrosion. Maintaining The LCO is consistent with NUREG-1432, Revision 1, and is satisfied when leakage

'etection monitors of diverse measurement means are OPERABLE in MODES 1, 2, 3g

'nd 4. Monitoring the reactor cavity sump inlet flow rate, in combination with monitoring the containment particulate or gaseous radioactivity, provides an acceptable minimum to assure that unidentified leakage is detected in time to allow actions to place the plant in a safe condition when such leakage indicates

!possible pressure boundary degradation.

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