ML17209B003

Revised Tech Specs Pages Per Order Modifying License, Requiring Periodic Surveillance Over Life of Plant & Specifying Limiting Conditions for Operation of Primary Coolant Sys Pressure Isolation Valves

ML17209B003
Person / Time
Site:	Saint Lucie
Issue date:	04/20/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML17209B000	List: ML17209B002 ML17209B003
References
NUDOCS 8104280652
Download: ML17209B003 (7)

Text

ATTACHMENT 3 ATTACHMENT TO ORDER FOR MODIFICATION OF LICENSE DATED FACILITY OPERATING LICENSE NO.

DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

~Pa es 3/4 4-14 3/4 4-14a (added) 3/4 4-14b (added)

B 3/4 4-4

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

With the contyinment sump level and flow monitoring system in-

operable, restore the inoperable system to OPERABLE status within 7 days or 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 />.

SURVEILlANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere gaseous and particulate monitoring systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, and b.

Reactor cavity sump level and flow monitoring system-perfonnance of CHANNEL CALIBRATION TEST at least once per 18 months.

ST.

LUCIE - UNIT 1

, 3/4 4-13

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 4

3.4.6.2

~ a ~

b.

c ~

d.

e.

Reactor Coolant System leakage shall be limited to:

No PRESSURE BOUNDARY LEAKAGE, 1

GPM UNIDENTIFIED LEAKAGE, 1

GPM total primary-to-secondary leakage through steam generators, 10 GPM IDENTIFI "4".AGE from the Reactor Coolant System, and Leakage as specifiec in Table 3.4.6-1 for each Reactor Coolant System Pressure Iso. :~alve identified in Table 3.4.6-1.

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 <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.

c With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and Reactor Coolant System Pressure Isolation Valve leakage, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within 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 />.

With any Reactor Coolant System Pressure Isolation Valve leakage

'reater than the limit in 3.4.6.2.e above reactor operation may continue provided that at least two valves, including check valves, in each high pressure line having a non-functional valve are in and remain in the mode corresponding to the isolated condi.ion.

Motor operated valves shall be placed in the closed posit

..n, and power supplies deenergized.

(Note, however, that this map ':ead to ACTION requirements for systems involved.)

Otherwise, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be. in at least HOT STANDBY within 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 />.

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

a ~

Monitoring the containment atmosphere gaseous and particulate radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ST LUCIE - UNIT 1 3/4 4-14 Order dated 4/20/81

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM'LEAKAGE SURVEILLANCE RE UIREMENTS Continued b.

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

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation except when operating in the shutdown cooling mode, d.

Monitoring the reactor head flange leakoff system 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 e.

Verifying each Reactor Coolant System Pressure Isolation Valve leakage (Table 3.4.6-1) to be within limits:

1.

Prior to entering MODE 2 after refueling, 2.

Prior to entering MODE 2, whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months, 3.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

4.

The provision of Specification 4.0.4 is not applicable for entry into MODE 3 or 4.

Whenever integrity of a pressure isolation valve listed in Table 3.4.6-1 cannot be demonstrated the integr,ity of the remaining check valve in each high pressure line having a

leaking valve shall be determined and recorded daily.

In addition, the position of one other valve located in each high pressure line having a leaking valve shall be recorded daily.

ST LUCIE - UNIT 1

3/4 4-14a Order dated 4/20/81

TABLE 3.4".6-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES Check Valve No.

V3227 V3123 V3217 V311 3 V3237 V31 33 V3247 V31 43 V3124 V3114 V3134 V3144

.a@~

NOiES (a)

Maximum Allowable Leakage (each valve):

1.

Leakage rates less than or equal to 1.0 gpm are acceptable.

2.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between previous measured leakage rate and the maximum permissible rate of 5.0 gpm by 50$ or greater.

3.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces'he margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50 or greater.

4.

Leakage rates greater than 5.0 gpm are unacceptable.

(b)

To satisy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.

(c)

Mimimum test differential pressure shall not be less than 150 psid.

ST LUCIE - UNIT 1

3/4 4-14b Order dated 4/20/81

EACTOR COOLANT SYSTEM BASES 3/4.4.5 STEAM GENERATORS Continued II The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those parameter limits found to result in negligible corrosion of the steam generator tubes.

If the secondary coolant chemistry is not maintained within these parameter limits, localized corrosion may likely result in stress corrosion cracking.

The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage

=

1 gallon per minute, total).

Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of, safety to wi.hstand the loads imposed during normal operation and by postulated accidents.

Operating plants have demonstrated that primary-to-secondary leakage of 1 gallon per minute can readily be detected by radiation mon'.tors of steam generator blowdown.

Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.

Mastage-type defects are unlikely with the all volatile treatment (AVT) of secondary coolant.

However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam generator tube examinations.

Plugging will be required of all tubes with imperfections exceeding the plugging limit which, by the definition of Specification 4.4.5.4.a is 40% of the tube nominal wall thickness.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20>> of the original tube wall thickness.

Mhenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant operation.

Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations,

tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

ST.

LUCIE - UNIT 1 B 3/4 4-3

REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are

'rovided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.

These detection systems are consistent with the recommendations of Regulatory Guide 1.45.

"Reactor Coolant Pressure Boundary Leakage Detec-tion Systems",

May 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 this leakage can be r educed to a threshold value of less than 1 GPM.~i~reshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIED 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 genera. or tube rupture or steam line break.

The 1

GPM limit is consistent with the assumptions used in the analysis of these accidents.

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

There-fore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD 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 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 ST LUCIE - UNIT 1 B 3/4 4-4 Order dated 4/20/81