ML20077Q734

Proposed Tech Specs Page 3/4 5-3,allowing One Time Extension of Allowable Outage Time for Each RHR Pump from 72 H to 120 H Through 950430

ML20077Q734
Person / Time
Site:	Millstone
Issue date:	01/10/1995
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20077Q711	List: B15084, Clarifies 940816 Proposed Rev to TS Re RHR Pump Allowable Outage Time,Per 941222 & 950106 Telcons W/Nrc.Footnote Added to Encl TS Page 3/4 5-3 to Read as Listed ML20077Q734
References
NUDOCS 9501190328
Download: ML20077Q734 (4)

Text

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Docket No. 50-423 j B15084 1

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Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Residual Heat Removal Pump / Heat Exchanger Allowable Outage. Time .

Marked Up Page .

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January 1995 1

P DR DO f

EMERGENCY CORE J00 LING SYSTEMS Y6

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- 3/4.5.2 ECCS SUBSYSTEMS - T GREATER THAN OR EQUAL TO 350'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be

OPERABLE with each subsystem comprised of

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE Safety Injection pump,

c. One OPERABLE RHR heat exchanger,+

d. One OPERABLt RHR pump, Y

e. One OPERABLE containment recirculation heat exchanger,

f. One OPERABLE containment recirculation pump, and

g. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and capable of automat-

• ically stopping the RHR pump and being manually realigned to transfer suction to the containment sump during the recirculation phase of operation.

APPLICABIi.ITY: MODES 1, 2, and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sror be in at least HOT STANDBY 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 />. ,

l b. In the event the ECCS is actuated and inf. 'ts water into the Reactor

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Coolant System, a Special Report shall be prepared and submitted to 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 for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

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Docket No. 50- m B15084 l

Attachment 2 l

l Millstonw Nuclear Power. Station, Unit No. 3 Proposed Revision to Technical Specifications Residual Heat Removal Pump / Heat Exchanger Allowable Outage Time i Retyped Page i

January 1995

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j - 'ENERGENCY C0RE C0OLING SYSTEMS 3/4.5.1 ECCS SUBSYSTEMS - T.,. GREATER THAN OR EQUAL TO 350*F

• LIMITING COMITION FOR OPERATION 1

i 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be .

l OPERABLE with each subsystem comprised of:  !

j a. One OPERABLE centrifugal charging pump,

b. One OPERABLE Safety Injection pump, j c. One.0PERABLE RHR heat exchanger,*

! d. One OPERABLE RHR pump,*

l l e. One OPERABLE containment recirculation heat exchanger,

f. One OPERABLE containment recirculation pump, and I g. An OPERABLE flow path capable of taking suction from the refueling

! water storage tank on a Safety Injection signal and capable of automat-

) ically stopping the RHR pump and being manually realigned to transfer suction to the constainment sump during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2, and 3.

j ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable 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 STANDBY l 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 j 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

i b. In the event the ECCS is actuated and injects water into the Reactor l Coolant System, a Special Report shall be prepared and submitted to

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

for each affected Safety Injection nozzle shall be provided in this l Special Report whenever its value exceeds 0.70.

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*The allowable outage time for each RHR pump /RHR heat exchanger may be extended to i 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> for the purpose of pump modification to change mechanical seal and other

related modifications. This exception may only be used one time per RHR pump /RHR l heat exchanger and is not valid after April 30, 1995.

NILLSTONE - UNIT 3 3/4 5-3 Amendment No.

0277