ML20043G631

Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements

ML20043G631
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/14/1990
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20043G625	List: B13546, Application for Amend to License DPR-61,adding Exception to Requirements of Tech Spec 4.0.4 for Performing E-bar Surveillance Prior to Entry Into Mode 1 ML20043G631
References
NUDOCS 9006200508
Download: ML20043G631 (3)

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O INDEX LIMITING CONDITIONS FOR OPERATION AND SVRVEILLANCE RE0VIREMENTS SECTION PAGI TABLE 3.3-10 RADI0 ACTIVE GASE0US EFFLVLNT MONITORING INSTRUMENTATION......................................

3/4 3 50 TABLE 4.3-8 RADI0 ACTIVE GASE0US EFFLVENT MONITORING INSTRUMENTATION SVRVEILLANCE REQVIREMENTS............

3/4 3-52 Boron Dilution Alarm.................................

3/4 3 54

?/4.3.4 INTERNAL FLOOD PROTECT 10N................................

3/4 3 55

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TABLE 3.3-11 LIQVID LEVEL INSTRUMENTATION FOR FLOODING PROTECTION.

3/4 3 56 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration.............................

3/4 4 1 Hot Standby.............................................

3/4 4 2 Hot Shutdown............................................

3/4 4-4 Col d Shutdown Loops Fill ed............................

3/4 4 6 Cold Shutdown - Loops Not filled........................

3/4 4-8 I sol ated Loop - MODES 1 and 2...........................

3/4 4 9 Isolated Loop - MODES 3, 4, 5, and 6....................

3/4 4 10 Isolated loop Startup...................................

3/4 4-11 Idled loop - MODES I and 2..............................

3/4 4-12 Idled Loop - MODES 3, 4, 5, and 6.......................

3/4 4-13 Idled loop Startup - MODES I and 2......................

3/4 4-14 Idled Loop Startup - MODES 3, 4, 5, and 6...............

3/4 4-15 3/4.4.2 SAFETY VALVES Shutdown................................................

3/4 4-16 Operating...............................................

3/4 4-17 n

d.oa.

3/4.4.3 PRESSURIZER.............................................

3/4 4 18

=$8 FIGURE 3.4-1 PRESSURIZER PROGRAMMED WATER LEVEL.................

3/4 4-19 3/4.4.4 RELIEF VALVES...........................................

3/4 4-20 i

• 5 3/4.4.5 STEAM GENERATORS........................................

3/4 4-22 8o om TABLE 4.4-1 MINIMVM NVt1BER OF STEAM GENERATORS TO BE oc 7,

INSPECTED DVRING INSERVICE INSPECTION................

3/4 4-27 TABLE 4.4 2 STEAM GENERATOR TVBE INSPECT 10N......................

3/4 4-28

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HADDAM NECK Vil Amendment No.,lar 1

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i TABLE 3.3-11 (Continued) f ACTION STATEMENTS l

ino ' erable With no channels

OPERABLE, restore an ACTION 53 a

channel (s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or wit 11n the next I hour establish a liquid level watch patrol to inspect the zone (s) without an OPERABLE channel at least once per hour.

With no channels OPERABLE for Functional Unit 9, Safety ACTION 54 Injection Pump Cubicle, the Minimum Channels OPERABLE requirement for Functional Unit 10, Condensate Return Pump Cubicle, must be met or take the action specified in ACTION 53, above.

With the number of OPERABLE channels one less than the ACTION 55 Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 7 days or within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> establish a liquid level watch patrol to inspect the zone (s) with the inoperable channel at least once per hour.

With no channels OPERACLE, take the action specified in ACTION 53, above, i

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HADDAM NECK 3/4 3-57 Amendment No. W

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TABLE 4.4-4

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REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE sii AND ANALYSIS PROGRAN 8G SAMPLE AND ANALYSIS MODES IN l4IICH SAMPLE TYPE OF MEASUREMENT z

FREQUENCY AND ANALYSIS REQUIRED g

AND ANALYSIS 1.

Gross Radioactivity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1, 2, 3, 4 1

2.

Isotopic Analysis for DOSE EQUIVA-1 per 14 days.

LENT I-131 Concentration 3.

Radiochemical for E Determination 1 per 6 months *.

1 4.

Isotopic Analysis for Iodine a)

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever 1**,

2**, 3**,

4**, S**

Including I-131, I-133 and I-135 the specific activity exceeds 1 microCi/ gram DOSE EQUIVALENT I-131 or 68/E microCi/ gram of gross radioactivity, and w) i b)

One sample between 2 and 6 1, 2, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following a THERMAL w

o' POWER change exceeding 15% of the RATED THERMAL POWER within a I-hour period.

Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was a

last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer. The provisions of Specification 4.0.4 are not applicable for entry 2

into MODE I.

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Until the specific activity of the Reactor Coolant System is restored within its ifmits.

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