Text

Amend 58 to License NPF-29,providing One Time Exceptions to Tech Spec 3.0.4 Approved for Use Only During Third Refueling Outage
	ML20246M012
Person / Time
Site:	Grand Gulf
Issue date:	03/16/1989
From:	Reeves E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20246M018	List: ML20246M012; ML20246M020;
References
	NUDOCS 8903270015
	Download: ML20246M012 (13)
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION n.

^

h WASHINGTON, D. C. 20555 SYSTEM ENERGY RESOURCES, INC., ET AL DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE J

Amendment No. 58 License No. NPF-29 1.

The Nuclear Regulatory Commission (the Comission) has found that A.

The application for amendment by System Energy Resources, Inc.,

(the licensee), dated January 26, 1989, as supplemented February 20, March 3, and March 6, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8903270015 890316 ADOCK050g6 DR 1

' 2.

Accordingly, the license is amended by t.hanges to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 58, are hereby incorporated into this license.

System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Edward A. Reeves, Acting Director Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 16,1989

ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 4-27 3/4 4-27 4

3/4 5-6 3/4 5-6 l

3/4 5-9 3/4 5-9 3/4 6-28 3/4 6-28 3/4 6-49 3/4 6-49 3/4 7-1 3/4 7-1 3/4 7-P 3/4 7-2 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 3/4 9-19 3/4 9-19 w-._____._.-_.--.-_________--_---

REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutd9wn 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 mode 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 CONDITION 4.

ACTION:

With less than the above required RHR shutdown cooling mode loops OPERABLE, a.

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 loop.

The provisions of Specification 3.0.4 are not applicable for entry into OPERATIONAL CONDITI.ON 4 from 5.**

b.

With no RHR shutdown cooling mode 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.

I 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 0

i surveillance testing 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.

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

- This exception is applicable until startup from the third refueling outage.

l GRAND GULF-UNIT 1 3/4 4-27 Amendment No. 58 l

I

s

. EMERGENCY C' ORE 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 pressure 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 suppres,sion 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 to 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 reactor vessel.

The provisions of Specification 3.

entryintoOPERATIONALCONDITION5from5*.Q.4arenotapplicablefor b.

With both of the above required subsystems / systems inoperable, suspend 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 .

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

is removed, the cavity is flooded, the reactor cavity and transfer canal gates l

.in the upper containment pool are removed, and water level is maintained i

within the limits of Specifications 3.9.8 and 3.9.9.

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

[

GRAND GULF-UNIT 1 3/4 5-6 Amendment No. 58

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EMERGENCY CORE COOLING SYSTEMS j

1 LIMITING CONDITION FOR OPERATION (Continued)

I ACTION: (Continued) c.

With one suppression pool water level instrumentation division inoperable, restore the inoperable division to OPERABLE status within 7 days or verify the suppression pool water level to be j

greater than or equal to 18'4-1/12" or 12'3", as applicable, at i

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by an alternate indicator.

The p.ro. visions i

of Specification 3.0.4 arg not applicable for entry into OPERATIONAL CONDITION 5 from 4 or 5*

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 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 and verify the suppression pool water level 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.

1 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 .

I 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 ct 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.

U This exception is applicable until startup from the third refueling outage.

l GRAND GULF-UNIT 1 3/4 5-9 Amendment No. 58

3 i

CONTAINMENT SYSTEMS 1

3/4.6.4 CONTAINMENT AND DRYWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4 The containment and drywell isolation valves shown in Table 3.6.4-1 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 drytell 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 automatic valve secured in the isolated position,* (the provisions of Specification 3.0.4 are not applicable for entry into condition #

for a maximum of 10 inoperable containment and drywell isolation valves **), or c.

Isolate each affected penetration by use of at least one closed I

manual valve or blind flange * (the provisions of Specification 3.0.4 are not applicable for entry into condition # for a maximum of 10 inoperable containment and drywell isolation valves **).

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 SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l

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

)

CONDITION changes are not allowed while isolation valves are open under these

{

administrative controls **).

j

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 Table 3.3.2-1.

- This exception is applicable until startup from the third refueling outage.

l GRAND GULF-UNIT 1 3/4 6-28 Amendment No. 58

l i

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 j

times less than or equal to the times shown in Table 3.6.6.2-1.

j APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *.

ACTION:

With one or more of the secondary containment ventilation system automatic l

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:

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

b.

Isolate each affected penetration by use of at least one deactivated automatic damper / valve secured in the isolation position (the orovi-sions of Specification 3.0.4 are not applicable for entry into condi-tion

for a maximum of 10 inoperable secondary containment isolation dampers / valves #),or c.

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

Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, 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 .

Otherwise, in Operational Condition

, suspend handling of irradiated l

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 REQUIREMENTS 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 after maintenance, repair or a.

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.

c.

By verifying the isolation time to be within its limit when tested 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 reactor vessel.

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

GRAND GULF-UNIT 1 3/4 6-49 Amendment No. 58

a y

3/4.' 7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS STANDBY SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION I

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 OPERABLE flow path capable of taking suction from the a'ssociated i

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-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 SHUTDOWN 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 SHUTDOWN ** within the following 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-cable.

The provisions of Specification 3.

entryintoOPERATIONALCONDITION4from5.p.4arenotapplicablefor l

c.

In OPERATIONAL CONDITION 4 or 5 with the SSW subsystem, which is associated with an ECCS pump required OPERABLE 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 Specification 3.0.4 are not applicable for lowering reactor cavity l

l water level l

A When handling wradiated fuel in the primary or secondary containment.

ns Whenever both SSW subsystems are inoperable, if unable to attain COLD SHUTDOWN i

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 third refueling outage.

l GRAND GULF-UNIT 1 3/47-1 Amendment No. 58

,(a PLANT SYSTENS LIMITING CONDITION FOR OPERATION ACTION: (Continued) d.

In OPERATIONAL CONDITION 5 with the SSW subsystem, which is associated 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 applicable.

The provisions of Specification 3.0 4 are n.ot g

g applicable for lowering reactor cavity water level In OPERATIONAL CONDITION *, with the SSW subsystem, which is associated e.

with a diesel generator required OPERABLE by Specification 3.8.1.2, l

inoperable, declare the associated diesel generator inoperable and i

take the ACTION required by Specification 3.8.1.2.

The provisions of Specification 3.0.3 are not applicable.

f.

.In OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5 with the SSW subsystem, l

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 l

Specification 3.8.1.1 or 3.8.1.2 as applicable, i

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

i a.

At least once per 31 days by verifying that each valve 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 during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on an actuation test signal.

i l

l V

i t

)

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

l GRAND GULF-UNIT 1 3/4 7-2 Amendment No. 58 L _ _

1 c

e PLANT. SYSTEMS

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

a.

- A minimum basin water level at or above elevation 130'3" Mean Sea Level, USGS datum, equivalent to an indicated level of >87".

b.

Two_ OPERABLE cooling tower fans,#

\\

shall be OPERABLE:

a.

In OPERATIONAL Condition 1, 2 and 3, two basins,##

b.

In OPERATIONAL Condition 4, 5 and *, the basins ## 3ssociated with systems and components,requirad OPERABLE by Specifications 3.7.1.1 and 3.7.1.2.

APPLICABILITY:

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

ACTION:

a.

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

with one SSW cooling tower basin inoperable, declare the associated SSW subsystem inoper-able and, if applicable, declare the HPCS service water system inoper-able, and take the ACTION required by Specifications 3.7.1.1 and 3.7.1.2, as applicable.

The provisions of Specification 3.0.4 are not applicable for entry into OPERATIONAL CONDITIONS 4 and 5.**

b.

In OPERATIONAL CONDITION 1, 2, 3, 4 or 5 with both SSW cooling tower basins in9perable, 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.

c.

In Operational Condition

with both SSW cooling tower basint inoperable, 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 OPERABLE at least once per:

a.

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 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, c.

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

by means of an OPERABLE siphon.

- This exception is applicable until startup from the third refueling outage.

GRAND GULF-UNIT 1 3/4 7-4 Amendment No. 58

s PLANT SYSTE'MS 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM l

LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency filtration system subsystems shall 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 SHU100WN 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 .f 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 or initiate and maintain operation of the OPERABLE subsystem in the isolation mode of operation.

The provisions of Specifica-tion 3.0.4 are not applicable for entry into OPERATIONAL CONDI-TION 4 from 5.#

2.

With both control room emergency filtration subsystems inoperable, 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:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adscrbers 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) after 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.

[0ELETED]

x When irradiated fuel is being handled in the primary or secondary containment.

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

l l

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

a.

t l

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 i

vessel and the 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 shutdown 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 applicable for entry int c.

OPERATIONAL CONDITION 5 from 4 or lowering reactor cavity water level.g SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode train of the residual heat removal 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 .

l x

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-hour period.

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

l GRAND GULF-UNIT 1 3/4 9-19

/mendment No. 58

_ _ - _

ML20246M012

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