B13284, Proposed Tech Spec 3.6 Re ECCS

Proposed Tech Spec 3.6 Re ECCS

ML20248C215
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/31/1989
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20248B797	List: B13284, Proposed Tech Spec 3.6 Re ECCS ML20248B793
References
B13284, NUDOCS 8908090459
Download: ML20248C215 (8)

Text

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4 Docket No. 50-213 B13284 Attachment 2 l Haddam Neck Plant Proposed Revision to Technical Specifications July 1989 89080904D9 890731 FDR ADOCK 05000213 P PDC

'3.6 . EMERGENCY CORE COOLING SYSTEMS' L, 3.6.1 ECCS SUBSYSTEMS - Tavo GREATER THAN OR E0 VAL TO 350 E LIMITING CONDITION FOR OPERATION 3.6.la Two independent Emergency Core Cooling Systems (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

-1. One OPERABLE centrifugal charging pump,

" 2. One OPERABLE High Pressure Safety Injection pump,

3. 0ne OPERABLE Low Pressure Safety Injection pump,

4. 0ne OPERABLE RHR heat exchanger, S. One OPERABLE RHR pump, and

6. An OPERABLE flow path capable of taking suction from the refueling water' storage tank on a Safety Injection signal and manually transferring suction to the containment sump during the recirculation phase of operation.

b. The flow path from the reactor cavity to the containment sump, which consists of four open reactor cavity pool seal hatches and open transfer canal drain valves shall be OPERABLE.

l APPLICABILITY: MODES 1, 2, and 3.

. ACTION:

a. . With one ECCS subsystem inoperable, test the remaining High-Pressure Safety Injection pump, Low Pressure Safety Injection pump, or the RHR pump within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 HOT SHUTDOWN the'following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. l l

b. With the flow path from the reactor cavity to the containment sump inoperable, restore the flow path to OPERABLE status within one

, hour or be in 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. In the event the ECCC is actuated and injects water into the Reactor Coolant Systen, a Special Report shall be preparW and I,

submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the l total accumulated actuation cycles to date. The current value of 4 the usage factor for each affected Safety Injection nozzla shall '

L be provided in this Special Report whenever its value exceeds l 0.70.

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l.  :

!- 3-10 I

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE0VIREMENTS Each ECCS subsystem shall be demonstrated OPERABLE:

a, At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated conditions:

Valve Number Valve function Valve Position RH-FCV-602 RHR Heat Exchanger Blocked closed. Operator air Bypass Line supply isolated.

RH-FCV-796 RHR Heat Exchanger Blocked in throttled position.

Discharge Line Operator air supply isolated.

RHR-MOV-22 Containment Sump Closed.

Suction Line Manual Operator is locked.

SI-MOV-24 RWST Line Locked open. Operator circuit breaker locked open.

SI-FCV-875 HPSI Miniflow Line Blocked and locked open.

RH-MOV-874 RHR Recirculation Locked closed. Operator Line circuit breaker locked open.*

SI-MOV-854A HPSI Pump Locked open.

Suction Line SI-MOV-854B HPSI Pump Locked open.

Suction Line SI-MOV-901 RHR/HPSI Crosstie Locked closed.

SI-M0V-902 RHR/HPSI Crosstie Locked closed.

b. On start-up prior to entering Mode 4:

VALVE NO. LOCATION ACTION l

SI-V-905 HPSI Loop 1 Valve blocked and locked Injection Line in throttled position.

SI-V-906 HPSI loop 2 Valve blocked and locked injection line in throttled position SI-V-907 HPSI loop 3 Valve blocked and locked injection line in throttled position.

SI-V-908 HPSI loop 4 Valve blocked and locked injectionline in throttled position.

SI-M0V-873 Core deluge line Valve is locked open and electrically disconnected.

• Except as permitted by Surveillance Requirement C.2.

3-10a

.s-EMERGENCY CORE C00LIN0' SYSTEMS SURVEILLAi4CE RE0VIREMENTS (Continued)

c. At least once per 31 days by:

1). Verifying that each valve (manual, power-operated or automatic) in the flow path that. is not locked, sealed, or otherwise secured in position, is in its correct position,

2) Manually cycling SI-MOV-24 from the full open position to approximately 1 inch of stem travel and returning to the full open position and cycling RH-MOV-874 from the full closed position to the full open position and back to the full closed position by use of the motor operator.

2) Verifying that each of the following pumps develops greater than or equal to the indicated discharge head pressure and differential pressure on recirculation flow when tested pursuant to Section 4.10.B.

Discharge Head Differential Pressure Pressure a) High Pressure Safety A 1392 psig 2 1374 psid Injection Pump B 1392 psig 2 1374 psid b) Low Pressure Safety .A 322 psig 2 304 psid Injection Pump B 322 psig 2 304 psid c) Residual Heat Removal A 145 psig 2 112 psid Pump B 145 psig 2 112 psid

4) Verifying the hydraulic characteristics of the centrifugal charging pumps (A and B) pursuant to Section 4.10.B.

d. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. The visual inspection shall be performed:

1) Of all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY. This includes verifying all reactor cavity pool seal hatches are open, gratings l- installed, and also that the transfer canal drain valves WD-V-203 and WD-V-970 are open, and

2) Of the areas within containment affected by the work activity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each containment entry, except for entries made only for surveillata vr inspection, when CONTAINMENT INTEGRITY is established.- In the event of nultiple containment entries, an inspection shall be performed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Inspection required by this paragraph shall be performed prior to the containment air lock testing.

3-10b

11 EMERGENCY CORE COOL}NG SYSTEMS SURVEILLANCE RE0VIREMENTS (Continuedl _

e. At least once per 18 months by:

1) Verifying that when the RCS pressure (simulated or actual) increases above 400 psig, proper interlock action occurs to protect the RHR System from being overpressurized by the RCS.

2) A visual inspection of the containment sump and verifying that the drain trenches and cover gratings are not restricted by debris and show no evidence of structural distress or abnormal corrosion.

f. At least once per 18 months, during shutdown, by:

1) Verifying that each automatic valve shown in Table 3.6-1 in the flow path actuates to its correct position on a Safety Injection Actuation test signal,

2) Verifying that valves, RH-MOV-22 and RH-V-808A, in the flow path for suction from the containment sump can be opened by manual realignment, and

3) Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation test signal:

a) High Pressure Safety Injection pump, and b) Low Pressure Safety Injection pump.

g. At least once per 18 months, during shutdown, the remotely controlled, motor-operated containment spray water valve shall be operated under a "no-flow" condition. The test will be considered satisfactory if visual observation shows that the valve has operated satisfactorily.

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I 3-10c

' I

' EMERGENCY CORE COOLING SYSTEMS l SURVEILLANCE RE0VIREMENTS (Continued)

h. Periodic leakage testing of each ECCS check valves, SI-CV-862A, SI-CV-862B, SI-CV-862C, SI-CV-8620, SI-CV-872A, and SI-CV-872B shal1 be accomplished prior to _ entering MODE 1 operation

1) After every' time the plant is placed in the cold. shutdown condition for refueling.

2) After every time the plant has been ~placed in the cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months.

3). Prior to returning the valve to' service after maintenance, repair, or replacement work is performed.

Leakage may be measured indirectly using pressure indicators, if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating compliance with the leakage criteria of Section 3.14.A.6. The minimum differential pressure across.these check valves during these leakage tests shall not be less than 150 psid.

i. The correct position of each ECCS throttle valve listed below shall be verified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.

ECCS Throttle Valves Valve Number SI-V-905 SI-V-906 SI-V-907 SI-V-908.

RH-FCV-796 3-10d

~

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) l

j. A flow balance test shall be performed, during Mode 5 or 6, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics, to verify that:

1) For the High Pressure Safety Injection pump injection lines, with a single pump running and two lines isolated, the flow rate through each line is equal to 1000 100 gpm.

2) For RHR pump discharge lines, with a single pump running, the flow rate through the discharge line is equal to 1500 i 280 gpm.

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TABLE 3.6-1 SAFETY INQECTION ACTUATED AUTOMATIC VALVES VALVE NUMBER SI POSITION SI-MOV-861A Open SI-MOV-861B Open SI-MOV-861C Open SI-MOV-8610 Open CD-MOV-871A Open CD-MOV-871B Open BA-MOV-373 Open LD-MOV-200 Closed LD-TV-230 Closed CH-MOV-257 Closed CH-50V-242 Closed 3-10f