ML20052H759

Proposed Tech Specs Re Reactivity Control Sys,Rcs & ECCS

ML20052H759
Person / Time
Site:	Summer
Issue date:	05/14/1982
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20052H754	List: ML20052H753 ML20052H759
References
NUDOCS 8205210414
Download: ML20052H759 (12)

Text

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.. REACTIVITY CONTROL SYSTEMS t - FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following"thre'e boron injection flow paths shall be OPERABLE:

a. The flow path from the boric acid tanks via a boric acid transfer pump or a gravity feed connection and a charging pump to the Reactor

@ Coolant System. . .

b. Two flow paths from the refueling water storage tank via charging I pumps to the Reactor Coolant System. -

APPLICABILITY: MODES 1, 2, 3 and 4# .

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ACTION: .

With only one of the above required boron injection flow paths to the' Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System 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 I least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least (q 2 percent delta k/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ,.

SURVEILLANCE REOUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

a. At least once per 31 days by 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.

b. At least once per 18 months by verifying that the flow path required '

by Specification 3.1.2.2.a delivers at least 70 gpm to the Reactor Coolant System.

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1. 0nly one boron injection flow path is requiied to be OPERABLE whenever the g(

temperature of one or more of the RCS, cold legs is less than or equal to t?58%

300*P.

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SUMMER - UNIT 1 j/{.1-8'h.

. MAR 3 1982 8205210414 820514  !". ' , . . -

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PDR ADOCK 05000395 PDR u * - '

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REACTIVITY CONTROL SYSTEMS

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,a r CHARGING PUMPS - OPERATING 1 LIMITING CONDITION FOR OPERATION

( f .1.2.4 3 At least two charging pumps shall be OPERABLE. ,

APPLICABILITY: MODES 1, 2, 3 and 4 .

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps 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 and borated to a .

SHUTDOWN MARGIN equivalent to at least 2 percent delta k/k at 200 F 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 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next-7-days-or-be-in COLD SHUT 00WN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ,

SURVEILLANCE REOUIREMENTS 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying, on recirculation flow, a differential pressure across each pump of greater than or equal to 2472 psig is developed when tested pursuant to Specification 4.0.5.

4.1.2.4.2 All charging pumps, except the above required OPERABLE pumps, shall be demonstrated inoperable, at least once per 31 days, whenever the tempera-ture of one or more of the RCS cold legs is less than or equal to-t75"F by verifying that the motor circuit breakers have been secured in the ope \n soo"F position.

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(#' A r, tximum of one centrifugal charging pump shall be OPERABLE whenever the ature of one or more of the RCS cold legs is less than or equal to 3co *F.

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- APR 151982 l SUMMER - UNIT 1 3/4 1-10

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( REACTOR COOLANT SYSTEM I HOT SHUTDOWN (K. .

LIMITING CONDITION FOR OPERATION

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3.4.1.3 At leait'two of the Reactor- Coolant and/or residual heat removal (RHR) loops listed below shall be OPERABLE and at least one of these Reactor Coolant and/or RHR loops shall be in operation.**

ge a. Re' actor Coolant Loop A and its associated steam generator and

(~ ' Reactor Coolant pump,*

b. Reactor Coolant Loop B and its associated steam generator and Reactor Coolant pump,*

c. Reactor Coolant Loop C and its associated steam generator and Reactor Coolant pump,'* - - - ,_

d. Residual Heat Removal Loop A,

e. Residual Heat Removal Loop B, APPLICABILITY: MODE 4 ACTION:

a. With 'less than the above required Reactor Coolant gnd/or RHR loops C OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR loop, be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With no Reactor Coolant or RHR loop 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 coolant loop to operation.

900'P

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A Reactor Coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to unless

1) the pressurizer water volume is less than 1288 cubic feet and/or 2) the secondary water temperature of each steam generator is less than 50 F above each of the RCS cold leg temperatures.

L AR All Reactor Coolant pumps and decay heat removal pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core ^

outlet temperature is maintained at least 10*F below saturation temperature.

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SUMMER - UNIT 1 3/4 4-3 -

. l F REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4 At least one residual heat removal (RHR) loops shall be OPERABLE and in operation *, and.either:

a. One additional RHR loop shall be OF~RABLE , or

b. The secondary side water level of at least two steam generators shall be greater than 10 percent of wide range C4 indication.

APPLICABILITY: MODE 5 with Reactor Coolant loops filled .

ACTION:

a. With less than the above required loops-OPERABLE and/or with leu than the required steam generator level, immediately initiate corrective action to eeturn the required loops to ' -

OPERABLE status or to restore the required level as soon as possible. ,

b. With no residual heat removal loop in operation, suspend all operations involving a reduction in boron concen-a tration of the Reactor Coolant System and immediately initiate corrective action to return the required residual F( heat removal loop to operation.

SURVEILLANCE REOUIREMENTS -

4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l 4. 4.1. 4.1. 2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1. 0ne residual heat removal loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for

( surveillance testing provided the other RHR loop is OPERABLE and in operation. g

1. 1. A Reactor Coolant pump shall not be started with one or more of he Reactor

' Coolant System cold leg temperatures less than or equal to unless

1) the pressurizer water volume is less than 1288 cubic feet and/or 2) the

( secondary water temperature of each steam generator is less than 50*F above each of the Reactor Coolant System cold leg temperatures.

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

.{2 below saturation temperature.

. .. MAR 0 31984 SUMMER - UNIT 1 3/4 4-5 L- ' F3.?

REACTOR COOLANT SYSTEM f 3/4.4.9 PRESSURE / TEMPERATURE LIMITS x.

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on

) Figures leak and 3.4-2 and 3.4-3 hydrostatic during testing heatup, cooldown, criticality, and inservice with:

a. A maximum heatup of 100?F in any one hour period,

b. A maximum cooldown of 100 F in any one hour period, and

c. A maximum temperature change of less than or equal to 10?F in any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

APPLICABILITY: At all times.

ACTION:

.. With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perforni an : engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least HOT STANDBY and pressure to less than within 200 F and the 500 nextpsig, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce respectively, withinthe the RCS T*V811owing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 1

4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be

, determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

4.4.'9.1.2 The reactor vessel material irradiation surveillance specimens

) shall be removed and examined, to determine changes in material properties, at the intervals required by 10 CFR 50, Appendix H in accordance with the schedule in Table 4.4-5. The results of these examinations shall be used to update Figures 3. 4-2pmd-3. 4-3 And J. 4-4.

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SUMMER - UNIT 1 3/4 4-29

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i iREACTOR COOLANT SYSTEM 0VERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION

3.4.9.3 At least one of the.following overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) witn a lifp dehn,J 4settiag7ofRpres.V.O less than or equal to -5^5 psig, er the maximum dpmw or

b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2.7 square inches.

APPLICABILITY: MODE 4 when the -temperature of any RCS cold leg is less than or

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equal to -Ns2f, MODE 5, and MODE 6 with' the re' actor vessel head on.

aco*f ACTION:

-a. Wi.th-one-PORV-inoperaMer re sto re-the-i nope ram e-PORV-to-OPERAB t:E-status-within-7-dayslor-depressurize-and-vent-the-RGS-thrcugh st ,

-l e as t-a-Er7-s qua re-i nc h-v ent(s )-wi thi n-the -next-B-hours .

-b. With-both-PORVS-inoperaMerdepressur-ize-and-Nent the RCS- th@

-et-least-a-2r7-square-inch-vent {-s-)-withir, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, becomeS in op e r'a b l6, a, f. In th'e event either the PORV:#cr the RCS vent (:) are u;;d to mitigate--

RCS prcssure-trens+en* , a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within

/a nt 't e $ r n j any corrective action necessary to prevent recurrence.

d. The provisions of Specification 3.0.4 are not applicable.

e SUMMER - UNIT 1 3/4 4-34 0 3 g, '

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RCS COLD OVERPR E SSilRI Z A 7~ ION PROTE C rioN

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EMERGENCY CORE COOLING SYSTEMS I.(

3/4.5.3 ECCS SUBSYSTEMS - T avg < 350*F LIMITING CONDITION FOR OPERATION

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3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERA 3LE: -

a. One OPERABLE centrif~,cl charging pump,#

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling ,

water storage tank and capsb.le of being manually or automatically realigned to the suction to the RHR. sump during the recirculation

, phase of operation. .

APPLICABILITY: MODE 4.

ACTION:

(~ a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b. With no ECCS subsystem OPERABLE becaura of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T avg less than 350 F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Spccial Report shall be prepared and submitted to

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( the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor -

I for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70. .

r A maximum of one centrifugal charging pump shall be OPERABLE whenever the l temperature of one or more of the RCS cold legs is less than or equal to ap,ap, l .2OO'F l

h SUMMER - UNIT 1 3/4 5-7 MAR 031BBf l

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l I EMERGENCY CORE , 0 LING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable

( Surveillance Requirements of 4.5.2.

4.5.3.2

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All charging pumps except the above. required OPERABLE pumps, shall be demonstrated inoperable at least once per 31 days whenever the temperature of one or more of the RCS cold legs is less than or equal to 475"r by verifying that the motor circuit breakers have been secured in the open position.

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• 3'N SussER - UNIT 1 3/4 s-s

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A 3/4.4 REACTOR COOLANT SYSTEM BASES

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3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant'is' designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with one reactor coolant loop not in operation this specification requires that the plant be in at least HOT STANOBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

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In MODE 4, and in MODE 5 with reactor coIlant' 1o6ps filled, a singTe reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either RHR'or RCS) be OPERABLE.

In MODE 5"with reactor coolant loops not filled, a single RHR loop provides r(. sufficient heat removal capability for removing decay heat; but single failure

( considerations, and the unavailability of the steam generators as a heat k removing component, require that at .,1 east two RHR loops be OPERABLE.

The operation of one Reactor Coolant Pump or one RHR pump ~provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentrat. ion reductions in the Reactor Coolant System. .

The reactivity change rate associated with bcron reduction will~, therefore, be within the capability of operator recognition and control.

Soo *F The restrictions on starting Reactor Coo'lant Pump with one or more RCS cold legs less than or equal t are provided to prevent RCS pressure transients, caused by energy additions from the secondary 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

{' Appenoix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into, or (2) 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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L MAR 0319gy' SUMMER - UNIT 1 B 3/4 4-1 l

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REACTOR C00LANT' SYSTEM 7{.

W BASES PRESSURE / TEMPERATURE LIMIT _5 (Continued)

The second~ portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4T deep outside c surface flaw' isassused. -~Unlike f.he situation at the vessel inside surf _ ace,

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the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and thus tend to reinforce any pressure stresses present. These thermal stresses, of course, are dependent on both

{- the rate of heatup and the time (or coolant temperature) along the heatup ramp. Furthermore, since the thermal stresses, at the outside are tensile and increase with . increasing heatup rate, a lower bound curve cannot be defined.

Rather; each'heatup rate of interest must be analyzed on an. individual basis.

Following'the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations; the final- limit curves are produced as follows. A composite curve is constructed based on a point-by-point comparison of the steady-state and finite heatup rate data. At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves ,under consideration. ,

The use of the composite curve is.necessary to' set conservative heatup

limitations because it is possible for conditions to exist such that over the

- course 'of 'the heatup ramp the controlling condition switches from the inside

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to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.

Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the r spective curves.

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits

.are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.

300*F The OPERABILITY of two PORVs or an RCS vent opening of at least 2.7 square l

(J inches ensures that the RCS will be protected from pressure transients which

! could exceed the limits of Appendix G to 10 CF part 50 when one or more of the

) RCS cold legs are less than or equal to 4 Map. Either PORV has adequate relieving capability to protect the RCS from overpressur.ization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 50 F above the

h. RCS cold leg temperatures or (2) the start of a HPSI pump and its injection into a water solid RCS.

i MR0 319,2: 8 1 SUMMER - UNIT 1 B 3/4 4-14 l

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4 is O 3, EMERGENCY CORE COOLING SYSTEMS AYJhP9nf %;t' BASES ECCS SUBSYSTEMS (Continued) ..

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Survei] lance Requirement to verify all charging pumps except

, { the required OPERABLE charging pump to be inoperable below assurance that a mass addition pressure transient can be relieved by the rovides operation of a single PORV. soo'F The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow.from exceeding j runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with  !

the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed

'. in the ECCS-LOCA analyses.

3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the baron injection system as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown t.an be caused by inadvertent depressurization, a loss-of coolant accident or a steam line rupture.

The limits on injection tank minimum contained volume and boron concentration ensure that the assumptions used in the steam line areak analysis are met. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

The OPERABILITY of the redundant heat tracing channels associated with i the boron injection system ensure that the solubility of the baron solution will be maintained above the solubility limit of 135 F at 22,500 ppm baron.

2/4.5.5 REFUELING '4ATER STORAGE TANK L

The CPERABILITY of the Refueling Water Storage Tank (RWST) as part of the >

ECCS ensures that a sufficient supply of borated water is available for injection  :

by the ECCS in the event of a LOCA. The limits on RWST minimum volume and '

boron concentration ensure that 1) sufficient water is available within contain-ment to permit recirculation cooling flow to the core, and 2) the reactor will

{, remain suocritical in tne cold condition following mixing of the RWST and the f

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SUMMER - UNIT 1 B 3/4 S-2 l