Text

Proposed Tech Specs Allowing one-time Exceptions for Certain Tech Specs Requirements,In Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-09
	ML20235M414
Person / Time
Site:	Grand Gulf
Issue date:	02/20/1989
From:	; SYSTEM ENERGY RESOURCES, INC.
To:	;
Shared Package
ML20235M403	List: AECM-89-0038, Application for Amend to License NPF-29,allowing one-time Exceptions to Tech Spec 3.0.4 in Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-09; ML20235M414;
References
	GL-87-09, GL-87-9, NUDOCS 8902280244
	Download: ML20235M414 (16)
	v • d • e

NL89/o3 REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling made loop shall.be in operation *'

with each loop consisting of at least:

a.

One OPERABLE RHR pump; and b.

One OPERABLE RHR heat exchanger.

APPLICABILITY:

OPERATIONAL CONCITION 4.

The ProviSio"5 of SPcifi'alion 3.WI ace not opplic. awe for erdry ACTION:

from OPIM ATION A te4bITzow 5, w a.

With less than the above required RHR shutdown cooling made loops OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereaf ter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop. <

b.

With no RHR shutdown cooling made loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

c.

The previsior.: Of Specification 3.0.4 ere not eppl' cable.'"

SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method 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 .

ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for 0surveillance tes, ting provided the other loop is OPERABLE and in operation.

' *The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

The shutdown cooling mode loop may be removed from operation during hydrostatic testing.

- This exception is applicable until startup from the sec:nd refueling outage.

h4 GRAND GULF-UNIT 1 3/4 4-27 Amendment No. 38 3

8902280244 svozzo

+

PDR ADOCK 05000416 P

FDC

1 NL S%/o3 EMERGENCY' CORE COOLING SYSTEMS 3/4 5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:

The low presswe core spray (LPCS) system with a flow path capable a.

of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.

b.

Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel.

Low pressure coolant injection (LPCI) subsystem "B" of the RHR system c.

with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to.the reactor vessel.

d.

Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water tn the

-reactor vessel.

The high pressure core spray (HPCS) system with a flow path capable e.

of taking suction from one of the following' water sources and trans-ferring the. water through the spray sparger to the reactor vessel:

1.

From the suppression ~ pool, or 2.

When the suppression pool level is less than the limit or is drained, from the condensate storage tank containing at least 170,000 available gallons of water, equivalent to a level'of 18 feet.

APPLICABILITY:

OPERATIONAL CONDITION 4 and 5*.

ACTION:

With one of the above required subsystems / systems inoperable, restore a.

at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or suspend all operations that have a potential for draining the reacjor he orov_isions_of_Spesifjca h 3.Q_.4 ar at applicablg.,

ves.or en y.q9 MERAno c.ogbpso4 5 h m

}5 _j--

With both of the above required subsysteins7 systems inoperable, suspend b.

CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel.

Restore at least one subsystem / system to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or establish SECONDARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The ECCS is not required to be OPERABLE provided that the reactor vessel head N

is removed, the cavity is flooded, the reactor cavity and transfer canal gates "in'the upper containment pool are removed, and water level is maintainediwithin the limits of Specifications 3.9.8 and 3.9.9.

This exception is applicable until startup from the :=.V efueling outage.

GRAND GULF-UNIT 1 3/4 5-6 Amendment No. 42) --

fdL 29/03 The, p+rovisions e-f SpecIGudien 3,0.4 EMERGENCY CORE COOLING SYSTEMS are no opplicWe b edr b+o OPER ATzoMA l

C00DITIoN 5 from 4 or-64.y# #

LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) c With one suppression pool water level instrumentation division i

inoperable, rest 6re the inoperable division to OPERAPt.E status within 7 days or verify the suppression pool wattr

.=,%1 to be greater than or equal to 18'4-1/12" or 12'8", as applicible, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by an alternate indicator. @

d.

With both suppression pool water level instrumentation divisions inoperable, restore at least one inoperable division to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and verify the suppression pool water Ibvel to be greater than or equal to 18'4-1/12" or 12'8", as applicable, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by at least one alternate indicator.

SURVEILLANCE REQUIREMENTS 4.5.3.1 The suppression pool shall be determined OPERABLE by verifying:

a.

The water level to be greater than or equal to, as applicable:

1.

18'4-1/12" at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

12'8 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Two suppression pool water level instrumentation divisions, with 1 channel per division, OPERABLE with the low water level alarm setpoint > 18'5 " or 12'8", as applicable, by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 18 months.

4.5.3.2 With the suppression pool level less than the above limit or drained in OPERATIONAL CONDITION 4 or 5*, at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

a.

Verify the required conditions of Specification 3.5.3.b to be satisfied, or b.

Verify footnote conditions

to be satisfied.

-## 'Thh excepUon is appliccide unEI S4ebp Crom 4he. Oird febeh3 oldge, m

GRAND GULF-UNIT 1 3/4 5-9 Amendment b.

I

{

NL-M/03 CONTAINMENT SYSTEMS-3/4.6.4 CONTAINMENT AND ORYWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4 The containment and drywell isolation valves shown in Table 3.6.4-1 l

shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.4-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, and #.

ACTION:

With one or more of the containment or drywell isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a.

Restore the inoperable valve (s) to OPERABLE status, or b.

Isolate each affected penetration by use of at least one deactivated automaticvalvesecuredintheisolatedpositiog,*or c.

Isolate each affected penetration by use of at least one closed manual valve or blind flange

g Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(Tbe pcevisions. of SpeciCic.alion 3.3.4 a nA c4pplicable foc en4ry h+o condi+iew* for amax'imwm &F 10inopemble CenWnrnen+ awd arywen isotabn va)ves..**)

Isolation valves, except MSIVs, closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls

Isolation valves shown in Table 3 6.4-1 are also required to be OPERABLE when their associated actuation instrumentation is required to be OPERABLE per able 3.3.2-1.

4 Th'is excepHon i.s apphcaWe uw4il s&adap b he Wird, due,\\;n3

.t_.-

GRAND GULF-UNIT 1 3/4 6-28 Amendment No. 42)

O NL 89/03 INSERT to page 3/4 6-28 (OPERATIONAL CONDITION changes are not allowed while isolation valves are open under these administrative controls.**)

l l

i l

I

NL 89/03 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS / VALVES LIMITING CONDITION FOR OPERATION 3.6.6.2 The secondary containment ventilation system automatic isolation dampers / valves shown in Table 3.6.6.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.6.2-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *.

ACTION:

With one or more of the secondary containment ventilation system automatic isolation dampers / valves shown in Table 3.6.6.2-1 inoperable, maintain at least one isolation damper / valve OPERABLE in each affected penetration that is open, and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:

a.

Restore the inoperable damper / valve (s) to OPERABLE status, or b.

Isolate each affected penetration by use of at least one deactivated automatic damper / valve secured in the isolation positiog, or c.

Isolate each affected penetration b use of at least one closed -~

manual valve or blind flange,.

me,- +

Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, in Operational Condition

, suspend handling of irradiated fuel in the primary or secondary containment, CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.6.6.2 Each secondary containment ventilation system automatic isolation damper / valve shown in Table 3.6.6.2-1 shall be demonstrated OPERABLE:

Prior to returning the damper / valve to service af ter maintenance, repair a.

or replacement work is performed on the damper / valve or its associated actuator, control or power circuit by cycling the damper / valve through at least one complete cycle of full travel and verifying the specified isolation time.

b.

During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation damper / valve actuates to its isolation position.

By verifying the isolation time to be within its limit when tested l

c.

pursuant to Specification 4.0.5.

When irradiated fuel is being handled in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the GRAND GULF-UNIT 1 3/4 6-49 Amendment No. 42 ___

3

NL 89/03 INSERT to page 3/4 6-49 (the provisions of Specification 3.0.4 are not applicable for entry into condition

for a maximum of 10 inoperable secondary containment isolation dampers / valves #)

i

NL WQ3 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS STANOBY SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.1 Each of the following independent standby service water (SSW) system subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE SSW pump, and b.

An GPERABLE flow path capable of taking suction from the associated SSW cooling tower basin and transferring the water through the RHR heat exchangers and to -associated plant equipment, as required, shall be OPERABLE as follows:

1.

In OPERATIONAL CONDITIONS 1, 2, and 3:

two subsystems; and 2.

In OPERATIONAL CONDITIONS 4, 5, and *:

the subsystems associated with the systems and components required to be OPERABLE by Specifications 3.4.9.2, 3.5.2, 3.8.1.2, 3.9.11.1 or 3.9.11.2.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *.

ACTION:

a.

In OPERATIONAL CONDITION 1, 2 or 3:

1.

With one SSW subsystem inoperable, restore the inoperable sub-1 system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With both SSW subsystems inoperable, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN"* within the following -

l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with the SSW subsystem, which is asso-ciated with an RHR loop required OPERABLE by Specification 3.4.9.1 or 3.4.9.2, inoperable, declare the associated RHR loop inoperable and take the ACTION required by Specification 3.4.9.1 or 3.4.9.2, as appli-entry into OPERATIONAL CONDITION 1.jion 3.0.4 are not applic cable.

The provisions of Specifica

(.pfp In OPERATIONAL CONDITION 4 or 5 with the SSW subsystem, which is asso-c.

ciated.with an ECCS pump required OPERA 8LE by Specification 3.5.2, inoperable, declare the associated ECCS pump inoperable and take the ACTION required by Specification 3.5.2.

The provisions of Specifica-l.

tion 3.0.4 are not applicabl e lomech reacdor ccM4y wa4ec level 3

When handling irradiated fuel in the primary or secondary containment.

Whenever both SSW subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by.this ACTION, maintain reactor coolant temperature,as low as practical by use of alternate heat removal methods.

This exception is applicable until startup from the ::::,d refueling outage.

l

(

4%cd GRAND GULF-UNIT 1 3/4 7-1 Amendment No. 38) --.

oL.

+

' N L 19/03 PLANT SYSTEMS i

I LIMITING CONDITION FOR OPERATION l

ACTION: (Continued) l In OPERATIONAL CONDITION 5 with the SSW subsystem, which is associated.

d.

with an RHR system required OPERABLE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated RHR system inoperable and take the ACTION required by Specification

3. 9.11.1 or 3. 9.11. 2, as applicab The provisions of Specific _ation 3.0d are not applicablg.je.

p}g,,.

{,g", Q h g g In OPERATIONAL CONDITION' *,' with the SSW subsystem, which is associated e.

with a diesel generator required OPERABLE by Specification 3.8.1.2, inoperable, declare the associated diesel generator inoperable and The provisions take the ACTION required by Specification 3.8.1.2.

of Specification 3.0.3 are not applicable, In OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5 with.the SSV subsystem, f.

which is associated with a diesel generator required OPERABLE by Specification 3.8.1.1 or. 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as applicable.

SURVEILLANCE REQUIREMENTS At least the above required standby servica' water system subsystem (s) 4.7.1.1 shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed or othenvise secured in position, is a.

in its correct position.

At least once per 18 months during shutdown by verifying that each b.

automatic valve servicing safety related equipment actuates to its correct position on an actuation test signal.

This exception is applicable until startup from the seeene refueling outage.

%c]

GRAND. GULF-UNIT 1 3/4 7-2 Amendment No. 78, 3Sp

= - _ _ _ _ _______-_________--_____-_--___-__ _ _ _ _ _

.u 9L e /o3 The provis. ions, oC S ed$iaNon -3.o.4 ee nef 1 t

PLANT SYSTEMS applicedle. for-an+r'y,rdo of ER ATm4 A\\.

i 0.o m rIc9s % nd 6. "

j.

ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.1.3 At least the following independent SSW cooling tower basins, each'with:

A minimum basin water level at or above elevation 130'3" Mean Sea a.

Level, USGS datum, equivalent to an indicated level.of > 87".

Two OPERABLE cooling tower fans,#

b.

shall be OPERABLE:

In OPERATIONAL Condition 1, 2 and 3, two basins,N a.

In OPERATIONAL Condition 4, 5 and *, the basins" associated with systems b.

and components required OPERABLE by Specifications 3.7.1.1 and 3.7.1.2.

APPLICA8ILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, 5.and *.

ACTION:

In OPERATIONAL CONDITION 1, 2, 3, 4, 5 and

with one SSW cooling a.

tower basin inoperable, declare the associated SSW subsystem inoperable and, if applicable, declare the HPCS service water system inoperable, and take the ACTION required by Specifications 3.7.1.1 and 3.7.1.2, as applicable. (

b.

In OPERATIONAL CONDITION 1, 2, 3, 4 or 5 with both SSW cooling tower basins inoperable, declare the SSW system and the HPCS service water system inoperable and take the ACTION required by. Specifications 3.7.1.1 and 3.7.1.2.

e In Operational Condition

with both SSW cooling tower basins inoperable, t

c.

declare the SSW system inoperable and take the ACTION required by Specification 3.7.1.1.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.3 At least the above required SSW cooling tower basins shall be deter-mined CPERABLE at least once per:

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying basin water level to be greater than or equal a.

to 87".

b.

31 days by starting from the control room each SSW cooling tower fan not already in operation and operating each fan for at least 15 minutes.

18 months by verifying that each SSW cooling tower fan starts auto-c.

matically when the associated SSW subsystem is started.

When handling irradiated fuel in the primary or secondary containment.

The basin cooling tower fans are not required to be OPERABLE for HPCS service water system OPERABILITY.

1. n OPERABLE basin shall have a 30 day supply of water either self-contained or A

k0

{p hs

[47-4

"" ~ Amendment No. S GRAND GULF-UNIT 1 y

e w.

w NL M/03 PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency filtration system subsystems s 11 be OPERABLE.

APPLICABILITY:

All OPERATIONAL CONDITIONS and *.

ACTION:

In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency a.

filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 4, 5 or *:

1.

With one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days

.E_RABJJ.s,ubsystem i_n R

su s or initiate and maintain operation of the the_ isolation mode of oggration. The provisiens oC Spec.iVic.cdien Lo,'i FeWohNe for ehyinto'0 EgATroA)%.c.oqDIT3cQ 4 rom 5.8 2.

With o control room emergency riitration suosystems inoperabrs,-

suspend CORE ALTERATIONS, handling of irradiated fuel in the primary or secondary containment and operations with a potential for draining the reactor vessel.

The provisions' of Specification 3.0.3 are not applicable in c.

Operational Condition *.

SURVEILLANCE REQUIREMENTS 4.7.2 Each control room emergency filtration subsystem shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 continuous hours with the heaters OPERABLE.

b.

At least once per 18 months or (1) af ter any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the subsystem by:

1.

[0ELETE0]

r dary containment.

A 4t TM excep+;en is oppuc4Lle unMi s-h cfwp from he. Mccl rene.lin3 oubje.,

D GRAND GULF-UNIT 1 3/4 7-5 Amendment No -

i l

I NL 8Vo3 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode trains of the residual heat removal (RHR) system shall be OPERABLE and at least one train shall be in operation,* with each train consisting of at least:

a.

One OPERABLE RHR pump, and b.

One OPERABLE RHR heat exchanger train.

APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and tne water level is less than 22 feet 8 inches above the top of the reactor pressure vessel flange.

ACTION:

With less than the above required shutdown cooling mode trains of the RHR a.

system OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode train.

b.

With no RHR shutdowr cooling mode train in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.

The provisions of Specification 3.0.4 are not applicabl.#

c.

be ehy in% OPERrrroMAt cocorTscic 5 d

codor 16dM qeacfoMQ erl M SURVE_ILLANCE RE0VIREMENTS At least one shutdown cooling mode train of the residual heat removal 4.9.11.2 system or alternate method shall be verified 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 .

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months n

per 8-hour period.

This exception is applicable until startup from the ::ces refueling outage.

%A GRAND GULF-UNIT 1 3/4 9-19 Amendment No. 38) _.

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RF03 SCIEDULE 4

EXPLANATION OF TERMS I. PLANT CONDITION Indicates the plant operational condition and reactor cavity water level.

II. TECH SPEC Indicates the safety systems or REQUIREMENTS subsystems required to be operable by the Tech Spec Limiting Condition for Operation.

III. RF03 SCHEDULE Indicates the specific safety systems or subsystems that are scheduled to be available to meet the requirements of the Tech Spec Limiting Condition for Operation or action statements.

IV. TSPS 121 Indicates those safety systems in addition to the Tech Spec required systems that are available by SERI outage policy.

V. ADDITIONAL Indicates those safety systems in SYSTEMS addition to those required by Tech Spec AVAILABLE and TSPS 121 as they become available upon completion of required maintenance.

J14AECM89021601 - 28 l

l

. + o to AECM-89/0038 l

RF03 SCHEDULED ACTIVITIES WHICH RESULT IN NEED FOR SPECIFICATION 3.0.4 EXCEPTIONS TECH SPEC Scheduled ACTION Activity Duration 3.4.9.2a SSW/ UHS "B" maintenance 3/31/89 to 4/26/89 and cleaning results in IUB loop "B" being inoperable.

3.5.2a RHR loop "A" inoperable due 4/3/89 to 4/5/89 to keep fill alarm.

RHR loop "B" inoperable to 3/31/89 to 4/9/89 perform various maintenance activities.

RHR loop "C" inoperable due 3/31/89 to 4/26/89 to SSW loop "B" maintenance.

HPCS inoperable since Division 3/23/89 to 4/5/89 III diesel generator and HPCS 1

is undergoing maintenance and surveillance.

3.5.3c ADHRS modification and RHR loop 3/19/89 to 3/31/89 "C" surveillance require RHR loop "C" jockey pump to be out of service.

ADHRS in operation places RHR 3/31/89 to 4/14/89 loop "C" jockey pump out of service.

3.6.4b&c Various containment and drywell 3/18/89 to 4/14/89 isolation valves inoperable for maintenance, inspections and testing.

3.6.6.2b&c Various secondary containment 3/18/89 to 4/24/89 automatic isolation dampers and valves inoperable for maintenance, inspections and testing.

3.7.1.1b,c&d SSW loop "B" inoperable due to 3/31/89 to 4/26/89 maintenance and cleaning.

3.7.1.3a UHS basin "B" inoperable due 3/31/89 to 4/26/89 to basin cleaning.

3.7.2b.1 Control room emergency 4/10/89 to 4/23/89 filtration loop "B" inoperable due to maintenance and su rveillances.

J14AECM89021601 - 29

o e s to AECM-89/0038 RF03 SCHEDULED ACTIVITIES WHICH RESULT IN NEED FOR-SPECIFICATION 3.0.4 EXCEPTIONS (Cont'd.)

1ECH SPEC Scheduled ACTION Activity Duration 3.9.11.2a&b RHR shutdown cooling loop "A" 3/22/89 to 4/2/89 inoperable due to feedwater "A" local leak rate testing.

FUDI shutdown cooling loop "B" 3/19/89 to 3/22/89 inoperable due to feedwater "B" local leak rate testing.

RHR shutdown cooling loop "B" 3/31/89 to 4/9/89 inoperable to perform various maintenance activities.

SSW/ UHS "B" maintenance and 3/31/89 to 4/26/89 cleaning results in RHR shutdown cooling loop "B" inoperable.

J14AECM89021601 - 30

- _ _ _ - - _ -.

ML20235M414

Text

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