Text

Proposed Tech Specs 3/4.4.1.4.2 & 3/4.9.1 Allowing Periodic Chemical Addition Via Chemical Mixing Tank
	ML19332C399
Person / Time
Site:	Vogtle
Issue date:	11/21/1989
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML19332C397	List: ML19332C396; ML19332C399;
References
	NUDOCS 8911280075
	Download: ML19332C399 (9)
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ENCLOSURE 3 V0GTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3/4.4.1.4.2 AND 3/4.9.1 INSTRUCTIONS FOR INCORPORATION The proposed change to the Vogtle Unit I and Unit 2 Technical Specifications would be incorporated as follows:

Remove Pace Insert Pace

.3/4-4-6 3/4 4-6 3/4 9-1 3/4 9-1 B3/4 4-1 B3/4 4-1 B3/4 9-1 B3/4 9-1 l

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8911280075 891121 PDR ADOCK 05000424 P PDC l

PiACTOR COOLANT SYSTEM C_0LD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION ,

3.4.1.4.2 Two residual heat removal (RHR) trains s 11 be DP and at least one RHR train shall be in operation.** Rene or Makeup r Storage Tank (RMWST) discharge valves (1208-04-175, 1208-04-17 , 1208-04-17 and l_

1208-04-183) shall be closed and secured in position.

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

I- a. With less than the above required RHR trains OPERABLE, immediately initiate corrective action to return the required RHR trains to OPERABLE status as soon as possible.

b. With no RHR train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR train to operation, y

c. With the Reactor Makeup W ter Storage nk (RMWST) discharge valves j (1208-U4-175, 1208-U4-17 , 1208-U4-17 , and 1208-04-183) not closed I and secured in position, immediately close and secure in position the RMWST discharge valves.

SURVEILLANCE REQUIREMENTS 4.4.1.4.2.1 At least one RHR train shall be determined to be in operation and l

circulating reactor coolant at least once per I hours.

4.4.1.4.2.2 Valves 1208-U4-175,1208-04-17 ,1208-U4-1Tr, and 1208-U4-183 l shall be verified closed and secured in position by mechanical stops at least once per 31 days.

0ne RHR train may be inoperable for up to 2. hours for surveillance testing provided the other RHR train is OPERABLE and in operation.

l

- The RHR pump may be deenergized for up to I hour provided: (1) no operations l

are permitted that would cause dilution of the Reactor Coolant System boron i concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature, h '

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l V0GTLE UNITS - 1 & 2 3/4 4-6

, I 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION ,

i LIMITING CONDITION FOR OPERATI,0N I

3.9.1 The boron concentration of all filled portions of the Reactor Coolant Systen and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions are j met. j l

a. A K,ff of 0.95 or less, or

b. A boron concentration of greater than or qual to 2000 ppe. J Additionally, valves 1208-U4-175, 1208-U4-17 , 1208-U4-183, and 1208-04-177 l !

shall be closed and secured in position. l APPLICABILITY: MODE 6. !

ACTION:

a. With the requirements of a. and b. above not satisfied, immediately f 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,ff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2000 ppa, whichever i the more restrictive,

b. With valves 1208-U4-175, 1208-04-1 , 1208-U4-183, and 1208-U4-17 l not closed and secured in position, immediately close and secure in position, t

SURVEILLANCE REQUIREMENTS 4.9.1.1 The boron concentration of the Reactor Coolant System and the refueling l

canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 4.9.1.2 Valves 1208-04-175, 1208-04-17 08-U4-183, and 1208-U4-176 1 be l verified closed and secured in position by mechanical stops at least once per 31 days.

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V0GTLE UNITS - 1 & 2 3/4 9-1 Amendment No. 21 (Unit 1)

Amendment No. 2 (Unit 2) l f_ .._ _ _ _ ___ .. _ _ _ _ _ . __

3/4.4 REACTOR COOLANT SYSTEM t BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops ir

. operation and maintain DNBR above 1.30 during all normal operations and antici-pated transients. In MODES I and 2 with one reactor coolant loop not in operation this specification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In MODE 3..two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident; however, a single reactor coolant loop provides sufficient heat removal capacity if a bank withdrawal accident can be prevented, i.e., by opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR train provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two trains / loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two RHR trains be OPERABLE. The lockingclosedoftherequiredvalves/inMode5(withtheloopsnotfilled) f precludesthepossibilityofuncontrolledborondilu1}onofthefilledportion of the Reactor Coolant System. 4 t

l wate by :!::in; '!:g :th: ' n ::pe action 8 prevents flow to the RCS of unborated

:1 d :::t:d a:t:r. These limitations l

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are onsistent with the initial e acc dent in the safety analysis. q1ditions LThese.

assumed for the boron dilution in etces 2 of-/Anf analtjted.

The operation of one reactor coolant pump (RCP) or one RHR pump provides acequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting an RCP with one or more RCS cold legs less

thtn or equal to 350*F are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coola'nt System, which could exceed the lin.its of AppendiY G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the. limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50*F above each of the RCS cold leg temperatures.

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i 3/4.9 REFUELING OPERATI(u ,

BASES .

3/4.9.1 BORON CONCENTRATION jn e gccss of Jha+MolyEed .

The limitations on reactivity conditions during REFUELING ensu e that:

(1) the reactor will remain suberitical during CORE ALTERATIONS, a (2) a uniform boron concentration is maintained for reactivity control i the water '

volume havino direct access to the reactor vessel. The lockin ci sed of the ,

required valves l l uncontrolled bo/during refuelingheoperations ron dilution precludes filled portions th possCoolant of the Reacto bi ity of

System. T low to the RCS of unborated water 4 :'::'a j !

:g :th; Q.. actionspreven

= ; ;f ....;t:d ata. These limitations are consistent u l

with the initia onditions assumed for the Boron Dilution Accident in the r safety analysis. Boron concentration value of 2000 ppe or greater ensures ,

a K,ff of 0.95 or les nd includes a conservative allowance for calculational l uncertainties of 100 ppm boron. ,

3/4.9.2 INSTRUMENTATION The.se. l The OPERABILITY of the Source Range Neutron Flux Monitors cosures that redundant monitoring capability is available to detect changes in the reactivity condition of the core. ,

3/4.9.3 DECAY TIME The' minimum requirement for reactor suberiticality prior to movement of ;

irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the

safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS ,

The requirements on containment building penetration closure and OPERABILITY ;

ensure that a release of radioactive material within containment will be i restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

l I 3/4.9.5 COMMUNICATIONS ;

The requirement for communications capability ensures that refueling i station personnel can be promptly informed of significant changes in the l facility status or core reactivity conditions during CORE ALTERATIONS.

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REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 4

3.4 1.4.2 Two residual heat removal (RHR) trains shall be OPERABLE

and at '

least one RHR train shall be in operation.** Reactor Makeup Water Storage Tank (RMWST) discharge valves (1208-U4-175,1208-U4-176#,1208-U4-117# and l 1208-U4-183) shall be closed and secured in position, t

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION: ,

a. With less than the above required RHR trains OPERABLE, immediately ,

initiate corrective action to return the required RHR trains to ;

OPERABLE status as soon as possible. *

b. With no RHR train in operation, suspend all operations involving a #

reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR -

train to operation,

c. With the Reactor Makeup Water Storage Tank (RMWST) discharge valves :

(1208-U4-175,1208-U4-176#,1208-U4-177#, and 1208-U4-183) not closed l and secured in position, imediately close and secure in position -

the RMWST discharge valves. L SURVEILLANCE RE0VIREMENTS ,

i 4.4.1.4.2.1 At least one RHR train shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 4.4.1.4.2.2 Valves 1208-U4-175,1208-U4-176#,1208-U4-177#, and 1208-04-183 l shall be verified closed and secured in position by mechanical stops at least ,

l once per 31 days.

0ne RHR train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing l provided the other RHR train is OPERABLE and in operation.

1

- The RHR pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided: (1) no operations are permitted that would cause dilutic7 of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

RMWST discharge valves 1208-U4-176 and 1208-U4-177 may be open under administrative control provided the Reactor Coolant System is in compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.2 and the high flux at shutdown alarm is OPERABLE with a setpoint of 2.30 times background in accordance with Note 9 of Table 4.3-1.

V0GTLE UNITS - 1 & 2 3/4 4-6 l

l ._

. h/4.9 REFUELING OPERATIONS 3/4.9.1 GDRON CONCENTRATION !

LINITING CONDITION FOR OPERATIDN 3.9.1 The boron concentration of all filled portions of the Reactor Co01 ant '

System and the refueling canal shall be neintained uniform and suf ficient to :

ensure that the more restrictive of the following reactivity conditions are ;

met: ,

a. A K,gg of 0.95 or less, or

b. A boron concentration of greater than or equal to 2000 ppm.

Additionally, valves 1208-04-175,1208-U4-177#,1208-U4-183, and 1208-U4-176# l shall be closed and secured in position.

APPLICABILITY: MODE 6.

ACTION:

a. With the requirements of a. and b. above not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positity

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,gg is reduced to less than ;

or equal to 0.95 or the boron concentration is restored to greater ,

than or equal to 2000 ppm, whichever is the more restrictive, i

b. With valves 1208-U4-175,1208-U4-177#,1208-U4-183, and 1208-U4-176# l not closed and secured in position, immediately close and secure in ,

position.

SURVEILLANCE REQUIREMENTS ,

l l 4.9.1.1 The boron concentration cf the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4.9.1.2 Valves 1208-U4-175,1208-U4-177#,1208-U4-183, and 1208-U4-176# l shall be verified closed and secured in position by mechanical stops at least once per 31 days. .

1 l

RMWST discharge valves 1208-U4-176 and 1208-U4-177 may be open under administrative control provided the Reactor Coolant System is in ,

compliance with the requirements of Specification 3.9.1 and the high flux at shutdown alarm is OPERABLE with a setpoint of 2.30 times background.

For the purpose of this specification, the high flux at shutdown alarm will be demonstrated OPERABLE pursuant to Specification 4.9.2.

V0GTLE UNITS - 1 & 2 3/49-1

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. 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION j The plant is designed to operate with all reactor coolant loops in I operation and maintain DNBR above 1.30 during all nonnal operations and antici-pated transients. In MODES 1 and 2 with one reactor coolant loop not in operation this specification 9. wires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ]

In MODE 3, two reactor coolant loeps provide suf ficient heat removal capability for removing core decay heat even in the event of a bank withdrawal ,

accident; however, a sing je reactor coolant loop provides suf ficient heat i removal capacity if e bank withdrawal accident can be prevented, i.e., by i opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolent loops filled, a single l reactor coolant loop or RHR train provides sufficient heat removal capability !

for remWing decay heat; but single failure considerations require that at q 1 east two trains / loops (either RHR or RCS) be OPERABLE. ,

1 In MODE 5 with reactor coolant loops not filled, a single RHR train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a >

heat removing component, require that at least two RHR trains be OPERABLE. The i locking closed of the required valves, except valves 1208-U4-176 and 1208-04-177 for short periods of time to maintain chemistry control, in Mode 5 (with the ,

loops not filled) precludes the possibility of uncontrolled boron dilution of tht filled portion of the Reactor Coolant System. These actions prevent flow to the RCS of unborated water in excess of that analyzed. These limitations are consistent with the initial conditions assumed for the boron dilution accident in the safety analysis. ,

The operation of one reactor coolant pump (RCP) or one RHR pump provides +

adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting on RCP with one or more RCS cold legs less than or equal to 350'F are provided to prevent RCf pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the .

limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperatures.

V0GTLE UNITS - 1 & 2 B 3/4 4-1

3/4.9 REFUELING OPERATIONS BASES , _

3/4.9.1 BORON CONCENTRATION !

The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain suberitical during CORE ALTERATIONS, and (2) a i uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The locking closed of the required valves, except valves 1208-04-116 and 1208-04-117 for short periods of time to maintain chemistry control, during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portions of the Reactor Coolant System. These actions prevent flow to the RCS of unborated '

water in excess of that analyzed. These licitations are consistent with the initial conditions assumed for the Boron Dilution Accident in the safety analysis. The boron concentration value of 2000 ppm or greater ensures a ,

K,gg of 0.9S or less and includes a conservative allowance for calculational i uncertainty of 100 ppm boron. ,

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the ;

reactivity condition of the core. .

3/4.9.3 DECAY TIME The minimum requirement for reactor subtriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission .

products. This decay time is consistent with the assumptions used in the safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE. j 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of siqnificant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

V0GTLE UN115 - 1 & 2 B 3/4 9-1

ML19332C399

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