ML17213B355

Amend 58 to License DPR-67,revising Tech Spec Surveillance Requirements & Limiting Operating Conditions Re Grid Voltage Protection Equipment & Procedures

ML17213B355
Person / Time
Site:	Saint Lucie
Issue date:	05/03/1983
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML17213B356	List: ML17213B355 ML17213B357 ML17213B358 ML17273A125 ML17301A029
References
NUDOCS 8305120153
Download: ML17213B355 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 8( LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No.

DPR-67 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power 8 Light Company, (the licensee) dated December 10,

1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) 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 common 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 Commission's regulations and all applicable requi rements have been satisfied.

8305120153 830503

PDR'ADOCK 05000335 P.,

PDR

I k

2.

Accordingly, Facility Operating License No.

DPR-67 is amended by changes to the Technical Specifications as indicated in the Attach-ment to this license amendment, and by amending paragraph 2.C(2) to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised. through Amendment No.

58

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR"REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications p

<.c-.'- (

. l.'('i<<-'.:-:(-

Robert A. Clark, Chief Operating Reactors Branch g3 Division of Licensing Date of Issuance:

May 3,

>g83

ATTACHMENT TO LICENSE AMENDMENT NO.

58 TO FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document com-pleteness.

Paqes 3/4 3-11 3/4 7-13 3/4 3-15 3/4 3-19

TABLE 3.3-3 Continuedg ENGiNFERED SAFETY FEATURE ACTUATION SYSTEtl IHSTRUf'1ENTATIOH FUNCTIONAL UNIT 5.

COHTAIHtiEHT SUi 1P RECIRCULATION (RAS)

a. tlanual RAS (Trip Buttons)

b. Refueling Water Tank-Low 6.

LOSS OF POWER TOTAL NO.

CHANNELS OF.. CHANNELS TO TRIP HIHI t lUtl CHANNELS OPERABLE APPLICABLE tlODES 1, 2, 3, 4

1, 2, 3

ACTION.

a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)*

2/Bus

b. 4.16 kv Emergency Bus Under-voltage (Degraded Voltage)

(1) Undervoltage Device IIl*

(2) Undervoltage Device II2*

c.

480 V Emergency Bus Under-voltage (Degraded Voltage)*

2/Bus 2/Bus 2/Bus 2/Bus 2/Bus 1/Bus 1/Bus 1/Bus 1/Bus 1

2 3

1, 2, 3

1, 2, 3

1, 2, 3

12 12 12 12 7.

AUXILIARY FEEDWATER AUTOt1ATIC START Steam Generator (SG)

Level Instruments 4/SG 2/SG I

2/SG 1,2,3 1/

2/SG for either steam, generator will start one train of AFW.

This specification will be effective prior to Cycle 7 restart.

TABLE 3.3-3 Continued)

TABLE NOTATION (a)

Trip function may be bypassed in this MODE when pressurizer pressure is

< 1725 psia; bypass shall be automatically removed when pressurizer pressure is

> 1725 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Tr'ip function may be bypassed in this MODE below 685 psig; bypass shall be automatically removed at or above 685 psig.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 8 ACTION 9 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a

~

The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

b.

Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a.

above for the inoperable channel.

c.

The Minimum Channels

.OPERABLE requirement is met;

however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ST.

LUCIE - UNIT 1

3/4 3-12 Amendment No. /iki 45

TABLE 3.3-3 (Continued TABLE NOTATION ACTION 10 ACTION 1 1 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition.

.and the Minimum Channels OPERABLE requirement is demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Sepcifica-tion 4.3.2.1.1.

Instrument operability requirements are contained in the Reactor Protection System requirements for Reactor Trip on Steam Generator Level.

If an Automatic Start channel is inoperable, operation may continue provided that the affected pump is verified to be OPERABLE per Specification 4.7.1.2.a within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 7 days thereafter; and the Automatic Start channel shall be restored to OPERABLE status within 30 days or the reactor shall 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 />.

ACTION 12-I )

With the number of OPERABLE Channels one less than the Total Number of Channels operation may proceed until per formance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condi tion within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ST.

LUCIE - UNIT 1

3/4 3-13 Amendment No. /Ip, /3V/, 5 g

TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES FUNCTIONAL UNIT 1.

SAFETY INJECTION (SIAS) a.'anual (Trip Buttons) b.

Containment Pressure High c.

. Pressurizer Pressure Low 2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons) b.

Containment Pressure. High-High 3.

CONTAINMENT ISOLATION (CIS) a.

Manual (Trip Buttons) b.

Containment Pressure High c.

Containment Radiation High TRIP SETPOINT Not Applicable

< 5 psig

> 1600.psia Not Applicable

< 10 psig Not Applicable

< 5 psig

< 10 R/hr ALLOWABLE VALUES Not Applicable 5 psig

> 1600 psia Not Applicable

< 10 psig Not Applicable 5 psig

< 10 R/hr d.

= SIAS (See FUNCTIONAL UNIT 1 above) --

4.

MAIN STEAM LINE ISOLATION (MSIS) a.

Manual (Trip Buttons) b.

Steam Generator Pressure

- Low 5.

CONTAINMENT SUMP RECIRCULATION (RAS) a.

Manual RAS (Trip Buttons) b., Refueling Water Tank Low Not Applicable 585 psig Not Appli cable 48 inches above tank bottom Not Applicable

> 585 psig Not Appl icabl e 48 inches above tank bottom

TABLE 3. 3-4 Continued ENGINEERED SAFETY FEATURE ACTUATIOH SYSTEM IHSTRUHENTATIOH TRIP VALUES

~

~

FUNCTIONAL UNIT TRIP VALUE ALLOl<ABLE VALUES C:

6.

LOSS OF POWER I

a.

(1) 4.16 kv Emergency Bus Undervol tag e (Loss of Voltage)*

b.

4.16 kv Emergency.Bus Undervoltage (Degraded Voltage) 2900

+ 29 volts with a 2900

+ 29 volts with a 1

+.5 second time delay 1

+.5 second time delay (1)

Undervoltage Device h'1*

(2)

Undervoltage Device f/2*

3675

+ 36 volts with a 7 +

1 minute time delay 3592

+ 36 volts with a 18 + 2 second time delay 3675

+ 36 volts with a 7 +

1 minute time delay 3592

+ 36 volts with a 18 + 2 second time delay c.

480 volts Emergency Bus Undervoltage (Degraded Voltage)~

429

+ 5-0 volts with a 429

+ 5 -0 volts with a 7 +

1 second time delay 7 +

1 second time delay 7.

AUXILIARY FEEDWATER

> 30Ã level

> 30Ã level O

This specification will be effective prior to Cycle 7 r estart.

V CJl CO

TABLE 3.3-5 ENGINEERED SAFETY FEATURES

RESPONSE

TIMES INITIATING SIGNAL AND FUNCTION 1.

Manual RESPONSE'IME IN SECONDS a.

SIAS Safety Injection (ECCS)

Containment Fan Coolers Feedwater Isolation Containment Isolation Not Applicable Not Applicable Not Applicable Not Applicable b.

CSAS Containment Spray c.

CIS Containment Isolation Shield Building Ventilation System d.

RAS Containment Sump Recirculation e.

MSIS Main Steam Isolation Feedwater Isolation 2.

Pressurizer Pressure-Low a.

Safety Injection (ECCS) b.

Containment Isolation'**.

c.

Containment Fan Coolers d.

Feedwater Isolation Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable 30 0*/1 9 5**

30 5*/20 5**

30 0*/1/ 0**

< 60.0 ST.

LUCIE - UNIT 1

3/4 3-16 Amendment No. 77, )7, 49

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IHS RUl1ENTATION SURVEILLANCE RE UIRENENTS

~

~

FUNCTIONAL UNIT 6.

LOSS OF POWER a.

4.16 kv Emergency Bus Under-voltage (Loss oP Voltage)*

b.

4.16 kv Emergency Bus Under-voltage (Degraded Voltage)

(1) Undervoltage Device /f1*

(2) Undervoltage Device f/2*

b.

480 V Emergency Bus Under-voltage (Degraded Voltage)*

CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL TEST tlODES IH WHICH SURVEILLANCE

~ftfUIREI 1,2,3 1

2 3

1, 2, 3

1, 2, 3

7.

AUXILIARY FEEDWATER a.

Auto Start b.

Steam Generator (See Survei 1 lance 4.7.1

~ 2. b)-----------

(See RPS Table 4.3-1)

This specificatio'n will be effective prior to Cycle 7 restart.

O V

~t

TABLE 4.3-2 Continued TABLE NOTATION (1)

The logic circuits shall be tested manually at least once per 31 days.

ST.

LUCIE - UNIT 1

3/4 3-20