ML20237L712

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Proposed Tech Specs,Changing Tech Specs 3.5.C.1 & 3.5.D.1 Re Reactor Operating Conditions for Which HPCI & RCIC Sys Required to Be Operable
ML20237L712
Person / Time
Site: Pilgrim
Issue date: 09/01/1987
From:
BOSTON EDISON CO.
To:
Shared Package
ML20237L699 List:
References
NUDOCS 8709090046
Download: ML20237L712 (5)
v • d • e


Text

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LililTINGCONDITIONFOROPERATION SURVEILLANGLRE@REMENT

  • 3.5.B Containment Coolino Subsystem 4.5.B Containment Coolina Subsystem (Cont'd) (Cont'd)
2. From and after the date that 2. When one containment cooling one containment cooling subsystem loop becomes subsystem loop is made or inoperable, the operable found to be inoperable for subsystem loop and its any reason, continued reactor associated diesel generator operation is permissible only shall be demonstrated to be during the succeeding seven operable immediately and the days unless such subsystem operable containment cooling loop is sooner made operable, subsystem loop daily thereafter, provided that the other containment cooling subsystem loop, including its associated diesel generator, is operable.
3. If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. HPCI Subsystem C. iDCI Subsystem

1. The HPCI Subsystem shall be 1. HPCI Subsystem testing shall be operable whenever there is performed as 'ollows:

irradiated fuel in the reactor vessel, reactor a. Simulated Once/ operating pressure is greater than 150 Automatic cycle psig, and reactor coolant Actuation temperature is greater than Test 355'F; except as specified in 3.5.C.2.and 3.5.C.3 below, b. Pump Oper- Once/ month and ability Once/ cycle from the Alternate Shutdown Station

c. Motor Once/ month Operated and Valve Once/ cycle Operability from the Alternate Shutdown Station
d. Flow Rate Once/3 months at 1000 psig
  • Conditional relief granted from this LCO for the period October 31, 1980 e. Flow Rate Once/ operating j through November 7, 1980. at 150 psig cycle 107 m

0709090046 Qh 93 PDR- ADOCK PDR n P _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

llMTING CONDITION FOR OPERATION SilRVEILLANCE RF&gIREMENT 1 .

3.5.C HPCI Subsystem (Cont'd) 4.5.C HPCI Subsystem (Cont'd)

The HPCI pump shall deliver at least 4250 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

2. From and after the date that 2. When it is determined that the the HPCI Subsystem is made or HPCI Subsystem is inoper=ble found to be inoperable for any the RCIC, the LPCI subsystem, reason, continued reactor both core spray subsystems, and operation is permissible only the ADS subsystem actuation during the succeeding seven logic shall be demonstrated to days unless such subsystem is be operable immediately. The sooner made operable, RCIC system and ADS subsystem providing that during such logic shall be demonstrated to seven days all active be operable daily thereafter.

components of the ADS subsystem, the RCIC system, the LPCI subsystem and both core spray subsystems are operable.

3. If the requirements of 3.5.C cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall j be reduced to below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.5.D Re ntor Core Isolation Cooling 4.5.D R1 actor Core Isolation Csaling_.

(RCIC) Subsystem (RCIC) Subsystem

1. The RCIC Subsystem shall se 1. RCIC Subsystem testing shall be operable whenever there is performed as follows:

irradiated fuel in the reactor vessel, reactor pressure is a. Simulated Once/ operating greater than 150 psig, and Automatic cycle reactor coolant temperature is Actuation greater than 365'F; except as Test specified in 3.5.D.2 below,

b. Pump Once/ month and Operability Once/ cycle from the Alternate Shutdown J Station
c. Motor Once/ month and 1 Operated Once/ cycle from )

Valve the Alternate )

Operability Shutdown Station 108

)

BASES:

3.5.C RPf1 The limiting conditions for operating the HPCI System are derived from the Station Nuclear Safety Operational Analysis (Appendix G; and a detailed functional analysis of the HPCI System (Section 6).

The HPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss-of-coolant which does not result in rapid depressurization of l the reactor vessel. The HPCIS permits the reactor to be shut down while I maintaining sufficient reactor vessel water level inventory until the vessel l 1s depressurized. The HPCIS continues to operate eatil reactor vessel i pressure is telow the pressure at which LPCI operat on or Core Spray System operation maintains core cooling.

The capacity of the system is selected to provide this required core cooling.

The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig. Two sources of water are available. Initially, demineralized [

water from the condensate storage tank is used instead of injecting water from the suppression poci into the reactor.

When the HPCI System begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the condensation of steam by the cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reaches equilibrium with the flow through the break. Continued depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This type of response is typical 6'T the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.

The analysis in the FSAR, Appendix G, shows that the ADS provides a single failure proof path for depressurization for postulated transients and accidents. The RCIL is required as an alternate source of makeup to the HPCI only in the case of loss of all offsite A-C power. Considering the HPCI and the ADS plus RCIC as redundant paths, reference (1) methods would give an estimated allowable repair time of 10 days based on the one month testing frequency. Considering this and the judgments of the reliability of the ADS and RCIC systems. a 7-day period is specified.

The requirement that HPCI be operable when reactor coolant temperature is greater than 365'F is included in Specification 3.5.C.1 to clarify that HPCI need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365*F is approximately equal to the saturation steam temperature at 150 psig.

116

  • BASE 6:

3.5.D RCIC System The RCIC is designed to provide makeup to the nuclear system as part of the.

planned operation for periods when the normal heat sink is unavailable. The nuclear safety analysis, FSAR Appendix G, shows that RCIC also serves as redundant makeup system on total loss of all offsite power in the event that HPCI is unavailable. In all other postulated accidents and transients, the ADS provides redundancy for the HPCI. Based on this and judgments on the i reliability of the HPCI system, an allowable repair time of seven days is specified. Immediate and weekly demonstrations of the HPCI operability during RCIC outage is considered adequate based on judgment and practicality. More frequent testing would cause undesirable steam flow interruption and thermal cycling transients.

The requirement that RCIC be operable when reactor coolant temperature is greater than 365'F is included in Specification 3.5.D.1 to clarify that RCIC need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365'F I is approximately equal to the saturation steam temperature at 150 psig.

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