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Corrected Amend 78 to License NPF-12,correcting Typos on Pages 3/4 3-5,3/4 3-13 & 3/4 3-14
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Issue date:	06/28/1989
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, ATTACHMENT TO LICENSE AMEN 0 MENT NO. 78 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix Technical Specifications with the enciosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-5

'3/4 3-5 3/4 3-7 3/43-7(overleaf) 3/4 3-8 3/4 3-8 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 (overleaf) 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 890~r050039 890628 PDR ADOCK 05000395 P

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TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 - With the number of channels OPERABLE'one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron' Flux Interlock) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Intermediate Range Neutron Flux Interlock).

setpoint but below 10 percent of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior.to increasing THERMAL POWER above 10 percent of RATED THERMAL POWER.

ACTION 4 - With the riumber of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

ACTION 5 - With the number of OPERABLE channels one less then the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total.

Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the'next required OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3 l

l l~

SUMMER - UNIT 1 3/4 3-7

1 l

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TABLE 3.3-1 (Continued) 1 ACTION STATEMENTS (Continued)

ACTION 8 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel.may be bypassed for up to i

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

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ACTION 9 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

ACTION 10 - With the number of OPERABLE Channels less than the Total Number of Channels operation may continue provided the inoperable channels are placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 11 - With one of the diverse trip features (undervoltage or shuntf trip attachment) inoperable, restoro it to OPERABLE status w{ thin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker OPERABLE status.

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SUMMER - UNIT 1 3/4 3-8 Amendment No. 78

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TABLE NOTATION With the reactor trip system breakers closed and the control rod y

drive system capable of rod withdrawal.

Below P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

(1)

If not performed in previous 7 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER._

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2 percent.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

i (3)

Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3 percent.

The provisions l

of Specification 4.0.4 are not applicable for entry into MODE 2 or,1.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

l (5)

Detector plateau curves shall be obtained evaluated and compared to manufacturer's data.

For the Power Range Neutron Flux Channels the provisions of Specification 4.0.4 are not applicable for entry L

into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock setpoint.the required OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive annunciator window.

(9)

Monthly Surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(10) -

Setpoint verification is not required.

(11) -

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

)

(12) -

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the

. Reactor Trip Breakers.

(13) -

Local manual shunt trip prior to placing breaker in service.

(14) -

Automatic undervoltage trip.

SUMMER - UNIT 1 3/4 3-14 Amendment No. 73, 78 4

1

ML20245K168

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