ML20244B109

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Proposed Tech Specs 3/4.7.1.2, Emergency Equipment Cooling Water Sys, 3/4.7.1.3, Emergency Equipment Svc Water Sys & 3/4.7.1.5 Uhs
ML20244B109
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/31/1989
From:
DETROIT EDISON CO.
To:
Shared Package
ML20244B106 List:
References
NUDOCS 8906120282
Download: ML20244B109 (9)
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Text

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PROPOSED PAGE CIA?GES

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PLANT SYSTEMS EMERGENCY EQUIPMEH1 C00t1NG WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two independent emergency equipment cooling water (EECW) system )

subsystems shall be OPERABLE gith each subsystem comprised of: I

a. One OPERABLE EECW pump, and
b. An OPERABLE flow path capable of removing heat from the associated .

safety-related equipment.

APPLICABIL11Y: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

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ACTION: I

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) SURVEILLANCE REQUIREMENTS 4

4.7.1.2 The emergency ecuipment cooling water system shall be demonstrated j OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipm position.
b. At least once per IB sonths during shutdown, by verifying that each automatic valve servicing nonsafety-related equipment actuates to its isolation position and the associated.EECW pump automatically starts on an automatic actuation test signal.

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3/4 7-3 FERMI - UNIT 2 4

INSERT ~ (PET 3/4 7-3)

ACTION:

a. . In OPERATIONAL CO!OITION 1, 2, or 3, with one EDCW system

_,. ' subsystem inoperable:

1. Take the ACTION, if any, required by Specification 3.4.9.1.
2. Within 2 hourrs:

a) Verify the ADS * -is OPERABLE, and b) Verify all required systems, subsystems, trains, components and devices that depend on the remaining-OPERABLE EBCW system subsystem are also OPERABLE.

Otherwise **, be in at least HOT SHUIDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CCLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. . Restore the inoperable EECW system subsystem 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUIDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. In OPERATIONAL CONDITION 4 or 5, declare the safety-related equignent associated with an inoperable EBCW system subsystem inoperable and take the ACTIONS required by the applicable Specifications.
  • ADS is not requirs5 to be OPERABLE when reactor steam dome pressure is less than or equal to 150 PSIG.
    • Except for an inoperable Drywell Cooling Unit, required by Specification 3.7.11, that depends on the remaining OPERABLE EBCW system subsystem. In this case, take the ACTION required by Specification 3.7.11 for the inoperability of both required l Drywell Cooling Units.

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I PLANT SYSTEMS EMERGENCY EQUIPMENT SERVICE WATER SYSTEM c

LIMITING CONDITION FOR OPERATION 3.7.1.3 Two independent emergency equipment service water (EESW) system subsystems shall be OPERABLE with each subsystem comprised of:

s. One OPERABLE emergency equipment service water pump, and

'b. AnOPERABi.Eflowpathcapableoftakingsuctionfromtheassociated ultimate heat sink and transferring the water through the associated EECW heat exchanger.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

emergency equipment service water system subsystem inoperabl n at least

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  • the inoper tem to OPERABLE status within 72 DOWN within the following urs and W8W HOT SHUTDOWN within t e ted equipment inoperable and Age,.y 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and declare the ass 3.5.1, 3.5.2, take the ACTION y specifications 3.4. . . .

3.6 . . .

3.9.11.1, and 3.9.11.2, as applicable.

SURVEILLANCE REQUIREMENTS d.7.1.3 The emergency equipment service water system shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment 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 the EESW pump automatically starts upon receipt of an actuation test signal.

S 3/4 7-4 FERMI - UNIT 2

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i' INSERT (PAGE 3/4 7-4)

ACTION:

With one EESW system subsystem inoperable, declare the associated EIXM system subsystem inoperable and take the ACTION required by Specification 3.7.1.2 u._______.____._____________ . _ _ _ . . ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

g PLANT SYSTEMS ULTIMATE HEAT 51NK

  • LIMITING CONDITION FOR OPERATION

-3.7.1.5 Two independent residual heat removal (RHR) reservoirs shall be OPERABLE with each reservoir comprised of:

a. A minimum water volume of 2,990,000 gallons, equivalent to an indicated water level of 25 feet (580 feet elevation).
b. At least one OPERABLE cooling tower with two cooling fans.
c. A maximum average water temperature of less than er equal to 80*F.
d. A minimum average water temperature of greater than or equal to 41*F.

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

ACTION:

With the requirements of Specification 3.7.1.5.a. b, or c not satisfied:

a. servoir, restore the inoperable reservoir to OPERABLE within 72 hou in at least HOT SHUTDOWN withi 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

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and in COLD SHUTDOWN wit 1 owi rs and declare the d take the ACTION

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associated safety related "*;;..m ino be required b

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ons 3.4.9.1, 3.4.9.2, 3.5.1, .. 2.2,

. 11.1 and 3.9.11.2, as applicable,

b. For both reservoirs:
1. In OPERATIONAL CONDITIONS 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

n OPERATIONAL CONDITIONS 4 or 5, declare the RHR5W system em, the EE5W system and the emergency di nerators

& [g inoperable e the ACTION required fications -]

f4 3.7.1.1, 3.7.1.2, .. nd 3 .. 1 Lue + B In Operational on *, declare ency' diesel generators

3. ,

ion 3.8.1.2.

inope nd take the ACTION required by Spe I

provisions of Specification 3.0.3 are not applicab .

With the requirements of Specification 3.7.1.5.d for one or both reservoirs not satisfied, perform a visual inspection of the reservoir (s) at least once j per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to verify that no ice has formed. If ice is observed, demonstrate  ;

the OPERABILITY of each safety related pump in the reservoir (s) by running each safety related pump at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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' INSERT A -

a .' For one reservoir, declare the associated RHRSR system subsystem, EE;SW system subsystem, and diesel generator cooling water subsystems inoperable and take the ACTION required by.

Specification s 3.7.1.l', 3.7.1.3 and 3.7.1.4.

INSERT B

2. In OPERATIONAL COtOITIONS 4 or 5, declare the RHR!M system, the EESW system and the diesel generator cooling water. system inoperable'and take the ACTION required by Specifications, 3.7.1.1, 3.7.1.3 and 3.7.1.4.

= 3. In OPERATIONAL COtOITION *, declare the diesel generator cooling

, water system inoperable and take the action required by Specification 3.7.1.4. The provisions of Specification 3.0.3 are not applicable.

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3/4.7 PLANT SYS1 EMS BASES 3/4.7.1 SERV!tE WATER SYSTEMS The OPERABILITY of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of these systers, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable Ifmits. l 3/4.7.2 CONTROL RDOM EMERGENCY FILTRATION SYSTEM The OPERABILITY of the control room emergency filtration system ensures that (1) the ambient air temperature does not exceed the allowable temperature

. for continuous duty rating for the squipment and instrumentation cooled by this system and (2) the control room will remain habitable for operations personnel during and following all design basis accident conditions. Continuous operation

(. A N of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during each 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is con-sistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.

3/4.7.3 SHORE BARRIER PROTECTION

(' The purpose of the shore barrier is to protect the site backfill from wave erosion.

Category I structures are designed to withstand the impact of waves up to 5.4 feet. So long as the backfill is in place, waves greater than 5.4 feet cannot impact Category I structures because of the lack of sufficient depth of water to sustain such waves.

The shore barrier can sustain a high degree of damage and still perform its function, protecting the site backfill from erosion. Thus the operability condition for operation of the shore barrier has been written to ensure that severe damage to the structure will not go undetected for a substantial period of time and provide for prompt NRC notification and corrective action.

j 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment. The RCIC l system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig. This pressure is substantially below that for which the low pressure core cooling systes can provide adequate core cooling for events requiring the RCIC system.

The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2, and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECC5 source of emergency core cooling when the reactor is pressurized.

FERMI - UNIT 2 B 3/4 7-1 1

INSERT (PAGE B 3/4 7-1)

When one Emergency Equipment Cooling Water (EEXM) system subsystem is i inoperable in OPERATIONAL., CONDITIONS 1, 2, or 3, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, camponents and devices, that depend on the remaining OPERABLE EEXM system subsystem are also OPERABLE. This requirement is intended to provide assurance that a loss of the normal nonsafety-related cooling supply will not result in a complete loss of safety function of critical systems during the period one of the EDCW system subsystem is inoperable. The normal nonsafety-related cooling supply may possibly be unavailable during the allowed outage period.

This is acceptable because of the requirement to perform the above verification. The term verify as used in this context means to administratively check by examining logs or other information to determine if certain cceponents are out-of-service for maintenance or other reasons. It does not mean to perform the surveillance requirements needed to demonstrate the OPERABILITY of the camponent.

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