ML17216A402

Amend 72 to License DPR-67,revising Tech Specs to Support Installation of Safety Grade Auxiliary Feedwater Actuation Sys

ML17216A402
Person / Time
Site:	Saint Lucie
Issue date:	01/15/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:	Florida Power & Light Co
Shared Package
ML17216A403	List: ML17216A402
References
DPR-67-A-072 NUDOCS 8601230067
Download: ML17216A402 (16)

Text

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UNITEDSTATES N

LEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 8t LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

72 License No.

DPR-67 1.

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

A.

The application for amendment by Florida Power

& Light Company, (the licensee) dated October 22, 1985, 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 requirements have been satisfied.

860i230067 860<>5 ~

~,

PDR ADOCK 05000335,';.

p

2.

Accordingly, Facility Operating License No.

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

(2)

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

72, 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 Asho C. Thadani, Director PWR oject Directorate P8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 15, 1986

ATTACHMENT TO LICENSE AMENDMENT NO.

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 completeness.

~RP Insert Paqes 3/4 3-11 3/4 3-13 3/4 3-15 3/4 3-16 3/4 3-17 3/4 3-19 6-8 3/4 3-11 3/4 3-13 3/4 3-15 3/4 3-16 3/4 3-17 3/4 3-19 6-8

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Cn Pl FUNCTIONAL UNIT 5.

CONTAINMENT -SUMP RECIRCULATION (RAS) a.

Manual RAS (Trip Buttons)

b. Refueling Mater Tank - Low 6.

LOSS OF POMER

a. 4.16 kv Emergency Bus Under-voltage (Loss of Voltage}*

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

(1) Undervoltage Device $1*

(2} Undervoltage Device f2~

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

7.

AUXILIARYFEEDMATER (AFAS}

a. Manual (Trip Buttons)

b. Automatic Actuation Logic c.

SG Level (1A/1B) - Low TOTAL NO.

OF CHANNELS 2/Bus 2/Bus 2/Bus 2/Bus 4(SG 4/SG 4/SG CHANNELS TO TRIP 1

2 2/Bus 2/Bus 2/Bus 2/Bus 2/SG 2/SG 2/SG MINIMUM CHANNELS OPERABLE 1/Bus 1(Bus 1/Bus 1/Bus 4/SG 3/SG 3/SG APPLICABLE MODES 1, 2, 3, 4 1, 2, 3

1,2,3 1 ~ 2.

3 1 $

2 j 3 1, 2, 3

1 $ 2 ~

3 1,2,3 1, 2, 3

ACTION 8

9k'2 12 ll 8

138, 14

~

O

'CA V

150 8.

AUXILIARYFEEDMATER ISOLATION

a. I 1A -

SG 18 Differential

.Pressure

b. Feedwater Header SG lA - SG 1B Differential 4/SG 2/SG Pressure 4/SG 2/SG I

• This specification will be effective prior to Cycle 7 restart.

3/SG 3/SG 1>

2~

3 1, 2, 3

I I I (go S

138, 14

138, 14

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 pmssurizer pressure is

> 1725 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

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

¹ The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 8 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 />.

ACTION 9 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. ilk 45

ACTION 10-TABLE 3.3-3 Continued TABLE NOTATION With the number of OPERABLE channels one less thap the Total Number of Channels, operation may proceed provigeB the inoperable channel is placed in the bypassed candition 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 Specification 4.3.2.1.1.

ACTION 11 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channels 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 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 />.

ACTION 12-ACTION 13-ACTION 14-With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in 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 />. If the inoperable channel is bypassed,.the-desirability.of.

maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5.1.6m.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

With the number of channels OPERABLE one less than the Minimum Channels

OPERABLE, STARTUP and/or POWER OPERATION may continue provided that one of the inoperable channels has been bypassed and the other inoperable channel has been placed in the tripped condition 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.

$$,$7,$ B, 72

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

SAFETY INJECTION (SIAS) a.

Manual (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 TRIP SETPOINT Not Applicable

<'5 psig

> 1600 psia Not Applicable

< 10 psig Not Applicable

< 5 psig ALLOWABLE VALUES Not Applicable

< 5 psig

> 1600 psia Not Applicable

< 10 psig Not Applicable

< 5 psig c.

Containment Radiation - High d.

SIAS

< 10 R/hr

.< 10 R/hr

- (See FVNCTIONAL UNIT 1 above) 4.

MAIN STEAM LINE ISOLATION (MSIS) a.

Manual (Trip Buttons)

,)s,) i

<<.-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 Applicable 48 inches above tank bottom Not Applicable l

> 585 psig,.

Not Applicable 48 inches above tank bottom

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES FUNCTIONAL UNIT 6.

LOSS OF POWER a.

(1) 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)*

b.

4.16 kv Emergency.Bus Undervoltage (Degraded Voltage)

(1)

Undervoltage Device 01*

(2)

Undervoltage Device f2*

c.

480 volts Emergency Bus Undervoltage (Degraded Voltage)*

7.

AUXILIARYFEEDWATER (AFAS) a.

Manual (Trip Buttons)

.:, <b, Automatic Actuation Logic c.

SG 1A 5 1B Level Low TRIP VALUE 2900

+ 29 volts with a 1

+.5 second time delay 3675 + 36 volts with a 7 +

1 minute time delay 3592 + 36 volts with a 18 + 2 second time delay 429 + 5-0 volts with a 7 +

1 second time delay Not Applicable Not Applicable

>29.0Ã ALLOWABLE VALUES 2900

+ 29 volts with a 1

+.5 second time delay 3675 + 36 volts with a 7 +

1 minute time delay 3592 + 36 volts with a

'8

+ 2 second time delay 429 + 5 -0 volts with a 7 +

1 second time delay I

Not Applicable Not AppliCa)1e,

>28. 5l 8.

AUXILIARYFEEOWATER ISOLATION a.

Steam Generator hP-High

<275 psid b.

Feedwater Keader Kigh aP

<150.0 psid

• This specification will be effective prior to Cycle 7 restart.

<281 psid

<157,.5 psid

TABLE 3.3-5 ENGINEERED SAFETY FEATURES

RESPONSE

TIMES INITIATINGSIGNAL AND FUNCTION l.

Manual a.

SIAS Safety Injection (ECCS)

Containment Fan Coolers Feedwater Isolation Containment Isolation b.

CSAS Containment Spray c.

CIS Containment Isolation Shield Building Ventilation System d.

RAS Containment Sump Recirculation e.

MSIS Main Steam Isolation Feedwater Isolation AFAS Auxiliary Feedwater Actuation 2.

Pressurizer Pressure-Low a.

Safety Injection (ECCS) b.

Containment Isolation ***

c.

Containment Fan Coolers d.

Feedwater Isolation

RESPONSE

TIME IN SECONDS

'ot Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable

~ 30.0~/19.5**

30 5*/$0 54*

30.+/P 04*

< 60.0 ST.

LUCIE - UNIT 1 3/4 3-16 Amendment No.

$7,$7,g, 72

TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES

RESPONSE

INITIATING SIGNAL AND FUNCTION 3.

Containment Pressure-Hi h

a.

Safety Injection (ECCS) b.

Containment Isolation***

c.

Shield Building Ventilation System d.

Containment Fan Coolers e.

Feedwater Isolation 4.

Containment Pressure Hi h-Hi h a.

Containment Spray 5.

Containment Radiation-Hi h

a.

Containment Isolation***

b.

Shield Building Ventilation System 6.

Steam Generator Pressure-Low a.

Main Steam Isolation b.

Feedwater Isolation 7..

Refuelin Water Stora e Tank-Low a.

Containment Sump Recirculation 8.

Steam Generator Level-Low a.

Auxiliary Feedwater TIMES RESPONSE TI ES IN SECONDS 3P P*/19 5**

30 5*/PP 5**

< 30.0*/14.0**

30 P*/1 7 P**

< 60.0

< 30.0*/18.5**

3P 5*/2P 5**

< 30.0*/14.0**

< 6.9

< 60.0

< 91.5 pp5**

< 6pp*

TABLE NOTATION

• Diesel generator starting and sequence loading delays included.

• • Diesel generator starting and sequence loading delays not- +luded.

Offsite power available.

• • • Notapplicable to containment isolation valve I-MV-18-1. '.

ST.

LUCIE - UNIT 1

3/4 3-17 Amendment No.

dT7,$7,Q, 72

TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT

. 1.

SAFETY INJECTION (SIAS) a.

Manual (Trip Buttons) b.

Containment Pressure - High c.

Pressurizer Pressure - Low d.

Automatic Actuation Logic CHANNEL CHECK N.A.

S S

N.A.

CHANNEL CALIBRATION N.A.

R R

N.A.

CHANNEL FUNCTIONAL TEST R

M M

M(1)

MODES IN WHICH SURVEILLANCE RE VIREO N.A.

1, 2, 3

1, 2, P 1, 2, 3

2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons) b.

Containment Pressure High - High c,

Automatic Actuation Logic N.A.

S N.A.

N.A.

R N.A.

M M(1)

N.A.

1, 2, 3 1, 2, 3

3.

CONTAINMENT ISOLATION (C IS) a.

Manual (Trip Buttons) b.

Containment Pressure - High c.

Containment Radiation - High d.

Automatic Actuation Logic e.

SIAS N.A.

'S S

N.A.

N.A.

N.A.

R R

N.A.

N.A.

R M(1)

R N.A.

1, 2, 3

1, 2, 3, 4 1, 2, 3

N.A.

4.

MAIN STEAM LINE ISOLATION (MSIS) a.

Manual (Trip Buttons)

N.A.

b.

Steam Generator Pressure - Low S

'<<'c..

~

Automatic Actuation Logic N.A.

~g q ~

~.(

5.

CONTAINMENT SUMP RECIRCULATION RAS) a.

Manual RAS Trip Buttons)

N.A.

b.

Refueling Water Storage Tank - Low c.

Automatic Actuation Logic N.A.

R N.A.

N.A.

R N.A.

R M(1)

M M(1)

N.A.

1, 2, 3

i12, 3 I,)4 ~,

~

I N.A.

1 $

2$

3 1,2,3

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 6.

LOSS OF POWER a.

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

b.

4.16 kv Emergency Bus Under-voltage (Degraded Voltage)

(1) Undervoltage Device 81*

(2) Undervoltage Device 82*

b.

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

7.

AUXILIARYFEEDWATER (AFAS) a.

Manual (Trip Buttons) b.

SG Level (A/B) - Low c.

Automatic Actuation Logic 8.

AUXILIARYFEEDWATER ISOLATION 8.a..

SG Level (A/B) - Low and ap i.

SG Differential Pressure (BtoA/AtoB) - High CHANNEL CHECK N.A.

N.A.

N.A.

CHANNEL CALIBRATION N.A.

N.A.

FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE

<RE UIRED 1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3

1, 2, 3 1, 2, 3

1, 2, 3

'~'h',2,3 b.

SG Level (A/B) - Low and Feedwater Header Differential Pressure (BtoA/AtoB) - High N.A.

R

• This specification will be effective prior to Cycle 7 restart.

1,2,3

TABLE 4.3-2 Continued TABLE NOTATION (1)

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

ST.

LUCIE - UNIT 1

3/4 3-20

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the FRG Chair man to serve'on a temporary basis;

however, no more than two alternates shall participate as voting members in FRG activities at any one time "

MEETING FRE UENCY 6.5.1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

gUORUM 6.5.1.5 The quorum of the FRG necessary for the performance of the FRG respons ibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates RESPONSIBILITIES 6.5.1.6 The Facility Review Group shall. be responsible for:

a ~

b.

c ~

d.

e.

Review of (1) all procedures required by Specification 6.8 and changes

thereto, (2) all programs required by Specification 6.8 and changes

thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.

Review of all proposed tests and experiments that affect nuclear safety.

Review of all proposed changes to Appendix A Technical Specifications Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua tion and recommendations to prevent recurrence to the Vice President Nuclear Operations, Group Vice President Nuclear Energy, and to the Chairman of the Company Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of unit operations to detect potential nuclear safety hazards Performance of special reviews, investigations or anhlgses and reports thereon as requested by the Plant Manager or..the Company Nuclear Review Board.

ST.

LUCIE - UNIT 1

6-7 Amendment No. Q, 69

ADMINISTRATIVE CONTROLS Review of submittal Board.

Review of submi ttal Board.

the Security Plan and implementing procedures and of recommended changes to the Company Nuclear Review the Emergency Plan and implementing procedures and of recoranended changes to the Company Nuclear Review k.

Review of every unplanned on-site release of radioactive material to the environs including the preparation of reports 'covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President Nuclear Operations and to the Company Nuclear Review Board.

1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADWASTE TREATMENT SYSTEMS.

m.

Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last FRG meeting.

AUTHORITY 6.5.1.7 The Facility Review Group shal-1:

a.

Recommend in writing to the Plant Manager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.

b.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6 a through e

above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear Operations, the Group Vice President Nuclear Energy, and the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FQG'ctivities performed under the responsibility and authority provisions ~Mesc Technical Specifications.

Copies shall be provided to the Vice'resident Nuclear Operations, the Group Vice President Nuclear Energy and the Chairman of the Company Nuclear Review Board.

ST.

LUCIE - UNIT 1

6-8 Amendment No. Q,72