ML18005A917

Proposed Tech Specs Re Boron Concentration During Refueling Operations

ML18005A917
Person / Time
Site:	Harris
Issue date:	05/16/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005A916	List: ML18005A915 ML18005A917
References
NUDOCS 8905240311
Download: ML18005A917 (4)

Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices..................................... 3/4 8-19 TABLE 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES......................+....... ~ ........ 3/4 8-21 Motor-Operated Valves Thermal Overload Protection........ 3/4 8-39 TABLE 3.8-2 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION..... 3/4 8-40 3/4.9 REFUELING OPERATIONS 3/4o9ol BORON CONCENTRATIONS ..... ~ .o.........o..o.......o....... 3/4 9-1 TABLE 3.9-1 ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURING REFUELING............................. ~ . ~ ... ...........

~ ~ 3/4 9-2 3/4+9+2 INSTRUMENTATION..... 3/4 9-3 3 /4.9.3 DECAY TIME...............o.. ....o.....oe..

~ .o. ~ ....... 3/4 9-4 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................ 3/4 9-5 3/4.9o5 COMMUNICATIONS'..o.oo..oo...oo.woo.o...o..o ~ .o.woo..o...o 3/4 9-6 3/4.9.6 REFUELING MACHINE.... 3/4 9-7 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING.......o............ 3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level......................................... 3/4 9-9 Low Water Level.......................................... 3/4 9-10 3/4.9.9 LOOPS'~ ISOLATION CONTAINMENT VENTILATION SYSTEM....o............ 3/4 9-11 3/4.9 '0 WATER LEVEL - REACTOR VESSEL........ ~ ........ .... ......

~ ~ 3/4 9-12 3/4 '.11 WATER LEVEL NEW AND SPENT FUEL POOLS. ~ ... ... LIMITS'

~ ~ ......~.. 3/4 9-13 3/4 ' '2 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM. ~ . ~ ~ ~ .... 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.. . ~ ~ ~ ~ ~ .. .. .. ..

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-1 3/4.10 ' GROUP HEIGHTq INSERTION~ AND POWER DISTRIBUTION . 3/4 10>>2 3/4.10.3 PHYSICS TESTS.................................. 3/4 10-3 3/F 10.4 REACTOR COOLANT .. . ... .. e . 3/4 10"4

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.10 POSITION INDICATION SYSTEM SHUTDOWN ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 10-,5 8905240311 S90516 PDR ADOCK 05000400 PDC SHEARON HARRIS UNIT 1 X1 Amendment No~

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9 '.a The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintai'ned uniform and sufficient to ensure that the more restxictive of the following reactivity conditions is met; either'.

(1) A K ff of 0.95 or less, or (2) A boron concentration of greater than or equal to 2000 ppm.

3.9.1.b The valves listed in Table 3.9-1 shall be in their positions required by Table 3.9-1 ~

APPLICABILITY: MODE 6 ~

ACTION:

a ~ With the requirements of Specification 3.9.1.a not 'satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, and initiate and continue boration at greater than or equal. to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until K.e ff is reduced to less than or equal to 0.95 ox the boron concentration is restored to greater than or equal to 2000 ppm, whichevex is the moxe restrictive.

b. With the requirements of Specification 3.9.1.b not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, and initiate action to return the valve(s) to the position required by Table 3.9-1.

SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the two reactivity conditions of Specification 3 gal.a shall be determined prior to'.

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis to be within the limits of Specification 3.9.1.a at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.9.1.3 At least once per 31 days, verify that the valves listed in Table 3.9-1 are in their positions required by Table 3.9-1.

SHEARON HARRIS - UNIT 1 3/4 9-1 Amendment No.

TABLE 3.9-1 ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURING REFUELING CP&L VALVE NO.

(Ebasco Valve No.) DESCRIPTION RE UIRED POSITION 1CS-149 Reactor Makeup Water to CVCS Makeup Lock closed; may be opened to permit makeup (CS-D121SN) Control System to Refueling Water Storage Tank provided valves 1CS-156 and 1CS-155 are maintained closed with their main control board control switches in "shut" position, and manual valves 1CS-274, 1CS-265 and 1CS"287 are locked closed.

1CS-510 Boric Acid Batch Tank Outlet Locked closed; may be opened provided the (CS-D631SN) boron concentration of the boric acid batch tank > 2000 ppm and valve 1CS-503 is closed.

1CS-503 Reactor Makeup Water to Boric Acid Lock closed, may be opened provided valve (CS-D251) Batch Tank 1CS-510 is closed.

1CS-93 Resin Sluice to CVCS Demineralizers Lock closed.

(CS-D51SN) 1CS-320 Boron Recycle Evaporator Feed Pump to Lock closed.

(CS-D641SN) Charging/SI Pumps 1CS-570 CVCS Letdown to Boron Thermal Closed with main control board control switch (CS-D575SN) Regeneration System in "shut" position, and BTRS function

/ selector switch maintained in "off" position; no lock required.

1CS"670 Reactor Makeup Water to Boron Thermal Lock closed.

(CS-D599SN) Regeneration System 1CS-649 Resin Sluice to BTRS Demineralizers Lock closed.

(CS-D198SN) 1CS-98 Boron Thermal Regeneration System Bypass Opened with main control board control switch (CS-D740SN) maintained in "open" position', no lock required.

~ ~

S REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING COND1TION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY: MODE 6.

ACTION:

a ~ With one or more of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b. With both of the above required monitors inoperable or not operating, in addition to Action a. above, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />'.

SURVEILLANCE RE UIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a. A CHANNEL CHECK at least once per 12 hours, b ~ An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and C ~ An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

SHEARON HARRIS - UNIT 1 3/4 9-3 Amendment No.