Text

Amend 130 to License DPR-72,changing Tech Specs to Allow Elimination of Automatic Simultaneous Operation of motor-driven Emergency Feedwater Pump & Low Pressure Injection Sys When Offsite Power Not Available
	ML20043E703
Person / Time
Site:	Crystal River
Issue date:	06/04/1990
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20043E705	List: ML20043E703; ML20043E707;
References
	NUDOCS 9006130302
	Download: ML20043E703 (12)
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NUCLE AR REGULATORY COMMISSION c.

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FLORIDA POWER CORPORATION CITY OF ALACHUA, CITY OF BU5HNEl.T CITY OF 6AINE5VILLE CITY OF KI55IPPIEE CITY OF LEE 55URG CITY OF NEW SMYRNA BEACH AND U1TETTTYTTORRTYSION. CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES N D CITY OF ORLANDO SEBRING UTILITIE5 COMMISSION SEMINOLE ELECTRIC COOPERATIVE. INC.

CITY OF TALLAMA55EE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.I30 License No. DPR-72 1.

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

A.

The application for amendment by Florida Power Corporation, et al.

(thelicensees)datedFebruary 13, 1990, complies with the standards and requirements of the Atomic Energy Act-of 1954, as amerded (the Act), and the Comission's rules and regulations set forth in-10 CFR l

Chapter I; B.

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

Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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9006130302 900604 DR ADOCK 0500 2

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operatirig License No. DPR-72 is hereby amended to read as follows:

l Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This'11 cense amendment is effective as'of its date of issuance and shall be implemented within 30 days of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION s

He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Cnanges to the Technical Specifications Date of Issuance: June 4, 1990 i

ATTACHMENT TO LICENSE AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment nun 6er and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

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Remove Insert E

3/4 3-10 3/4 3-10 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-17 3/4 3-17 n

b 3/4 7-4 3/4 7-4 1

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INSTRUMENTATION' g..

3/4.3.2 ENGINEERED $AFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERA _ TION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumen-tation channels shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3s3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

With an ESFAS instrumentation channel trip setpoint less a.

conservative than the value shown in the Allowable Values L

L column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip setpoint Value.

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b.

With an ESFAS instrumentation channel inoperable, take the action shown in Table 3.3-3.

j SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION t

and CHANNEL FUNCTIONAL TEST operations during the MODES and at the f requencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANi.il FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

L 4.3.2.1.3 The ENGhNEERED SAFETY FEATURES RESPONSE TIME of each E function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18' months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No of Channels" Column of Table 3.3-3.

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. CRYSTAL RIVER - UNIT 3 3/4 3-9 0

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.m oq TABLE 3.3-3 h,

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION r-Wy MINIMUN M

TOTAL NO.

' CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CH4fetELS TO TRIP OPERABLE MODES ACTION E

1.

SAFETY INJECTION g

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a. High Pressure injection

l. Manual Initiation 2

1 2

1, 2, 3, 4 13

2. Reactor 81dg. Pressure High 3

2 2

1, 2, 3 98

3. RCS Pressure Low 3

2 2

1, 2, 3*

98

4. RCS Pressure low-Low 3

2 2

1, 2, 3**

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5. Automatic Actuation Logic 2

1 2

1, 2, 3, 4 to

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b. Low Pressure Injection o

1. Manual Initiation 2

1 2

1, 2, 3,*4 13

2. Reactor 81dg. Pressure High 3

2fffff 2

1, 2, 3 98 l

3. RCS Pressure low-tow 3

2 2

1, 2, 3**

98

4. Automatic Actuation Logic 2

1 2

1, 2, 3, 4 10 l

2. REACTOR 8t0G. COOLING l

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a. Manual Initiation 2

1 2

1, 2, 3, 4 13 j

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b. Reactor 81dg. Pressure

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2 2-1, 2, 3 98 g

c. Automatic Actuation Logic 2-1 2

1, 2, 3, 4 20

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Tant.E 3.3-3 (Cent 94 n

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d ENGINEERED SAFETY FEATURE ACTUATION SYSTEsA We57RtMAINSTATION_

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h TOTAL 900.

CHANNELS CHANNELS - APPt.ICAHLE M2 FUNCTIONAL UNIT OF CHANNELS TO TRIP _

OPERAllLE

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ACT90N l 1

p N

3.

REACTOR Bt.DG. ISOLATION C

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2-l 2

1, 2, 3, 4 83 j

3 m.

Manant Initiation n

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b.

Reactor Bldg. Pressure 3

2 2

1, 2, 3

- W High w

c.

Automette Actuetten Logic 2

1 2

I, 2, 3, 4 IO

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Deieted

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3 2

2 i, 2, 3-i3-9eri ssotation) 2 l

2 1, 2, 3, 4 le

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l TABLE 3.3 3 (Continued)

I TABLE NOTATION i

" Trip function may be bypused in this, MODE with RCS preuure below 1700 psig. Bypus shall be automatically removed when RCS preuure exceeds 1700 P518-

" Trip function may be bypaned in this MODE with RCS preuure below 900 psig.

Bypus shall be automatically removed when RCS presure exceeds 900 psig.

"' Trip function may be bypassed in this MODE with steam generator preuure I

l' below 750 psig. Bypus shall be automatically removed when steam generator pressure exceeds 750 psig.

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The provisions of Speci5 cation 3.0.4 are not applicable.

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# Trip automatically bypused below 20 percent of RATED THERMAL POWER.

1. 1. Trip function may be bypaued. below 10 percent of RATED THERMAL POWER.

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1. 1. 1. Manual trip function occurs if two channeh in the same train are actuated.

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1. ### Trip function for LPI pump start is automatically bypaned when of site power is not available. Bypass is automatically removed when oE site power is restored.

i AC'T10N STATEMENTS ACTION 9 With the number of OPERABL.E Channeh one less than the Total Number of Channels, opration may proceed until performance of the nextrequiredCHANNE FUNCIlONALTESTprovided theinoperable 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 10. With the number of OPERABLE channeh one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ami in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one chael 1

p may be bypassed for up to 1 bour for Surveillance testing per i

Specification 4.3.2.1.1.

AC710N 11. With less than the Minimum Channeh OPERABLE, operation may continue provided the containment purge and exhaust valves' are maintained closed.

L CRYSTAL RIVER UNIT 3 3/4314 Amendment No. 36,98,130 L

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w y-TABLE 3.3 3 (Continued) i ACTION STATEMENTS (Continued)

ACTION 12 With the number of OPERABLE Channels one Itu than the Total Number of Channels, operation may proceed provided the inopenble channel is placed in the bypaned condition and the minimum channels OPERABLE required is demonstrated.within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional channel may be bypaned for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Surveillance testing per Speci5 cation 43.2.1.1.

ACTION 13 With the number of OPERABG Channels one leu than the Total r

Number of Channels, 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 be in at least HOT STANDBY within the next -

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHU1DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AC710N 14 - With the number of OPERABLE Channels one leu than the Total p

Number of Channels, operation may proceed provided the inoperable L

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 , one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Surveillance testing per Specification 43.2.1.1.

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CRYSTAL RIVER UNIT 3 3/4 314a Amendment No.130-

6.

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Tant.E 3.3 4 (Cenelmsed

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ENGINEERED SAFETY FEATURE ACTUATION SYSTERE INSTRURRENTATION TItIP SETFOINTS i

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i po FUNCTIONAL UNtf TRIP SETFOINT ALLOWARt.E vat.UES E

Q 3.

REACTOR Bt.DC. ISOLATION c

e. - E5 Actustion "A" and "B" z

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1.

ManusIInitiation Not AppIlcable Not AppIIcable 2.

Reactor BIdg. Pressure High

( 4 psig f 4 psig -

3.

Automatic Actuation Logic Not AppIlcoble

. Not AppIlcable t

g 4.

Deleted Y

3.

RC5 Pressure Low i

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(HPIIsolation) 21300 psig 21300 psig I

6.

Automatic Actantlen Logle (HPIIsolation)

Not Applicable Not AppIIcable 3

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TABLE D.5 i

l ENGINEERED SAFETY FEATURES RESPONSE TIMER 1

INITIATINO SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1, Manual a.

.High Pressure Injection Not Applicab!c b.

- Low Pressure Injection Not Appucable c.

Reactor Building Cooling Not AppUcable d.

Reactor Building Isolation Not Applicable e.

Reactor Building Spray Not Applicable f.

Reactor Building Purge Isolation Not Applicable g.

MFW and MSL isolation.

1.

Emergency Feedwater Aeruation Not Applicable 2,

Feedwater Isolation Not Applicable 3.

Steam Une Isolation Not Applicable b.

. Emergency Feedwater Actuation Not AppUcable 2.

Reactor Building Pressure High a.

High Pressure Injection 35*

b._

!.ow Pressure Injection 35' c.

Reactor Building Cooling 25*

d.

Reactor Building Isolation 60*

3.

Reactor Building Pressure Wh.High (with HPI signan a.

Reactor Building Spray 56*

4.

RCS Pressure 12w a.

High Pressure Injection 35' l

b.

HPI Isolation 60*

5.

RG Premre Izw Imw s.

High Pressure Injection 35*

b.

Low Pressure Injection 35*

6.

Irw Steam Generator Pressure L

a.

Feedwater Isolation 34 b.

Steam Une Isolation 5

c.

Emergency Feedwater Actuation Not AppUcable i

CRYSTAL RIVER UNTT 3 3/4317 Amendment No. 38,98,130

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l TABLE 4.1-1

'G g

STEAM LINE SAFETY VM.VES j

h VALVE HUMBER LIFT SETTING (f.11) (psig)

ORIFICE SIZE (teches) r-E STEAM GENERATOR 3A i

M

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w Main stem Itne Al e

c MSV

~34 1050 4.515

^

HSV - 38 1970 4.515 HSV.- 43 1990 4.515 :

MSV - 40 1100 3.750 F

Main stem ilne A2 i

t I

MSV - 33 ~

1950 4.515

.MSV - 31 1970 4.515 MSV - 42 '

1090 4.515 i

t HSV - 46 1100 4.515 s

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2, STEAM GENERATOR 38 j

Main stem line 81 MSV - 35 ~

1050 4.515 MSV - 39.*

1970 4.515 MSV - 44 "

1990 4.535 i

HSV.- 47 1100 4.515' 3

8 Main ste m line 82

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MSV - 36 1950 4.515

.j MSV - 41 1970 4.535-j MSV - 45/

1990 4.545 i

..i MSV - 48 1100 3.750

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PLANT SYSTEMS 4

- EMERGENCY FEEDWA*fER SYSTEM i

LIMTITNG CONDITION FOR OPERAT10N 3.7.1.2 Two independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABG with:

One emergency feedwater pump" capable of being powered from an l

a.

OPERABLE emergency bus, and b.

One emergency feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABTLITY: MODES 1,2, and 3.

ACTION:

With one emergency feedwater pump and/or associated Gow path a.

inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2 SURVElll.ANCE REQUIREMENTS l-4.7.1.2 Each emergency feedwater sptem shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that the steam turbine driven pump develops a discharge pressure greater than or e<ual to 1100 psig on recirculation flow when the secondary steam supp'y pressure is greater than 200 psig.*

2.

Verifying that the motor driven pump develops a discharge pressure of greater than or equal to 1100 psig on rectreulation Dow.

When not in MODES 1,2, or 3, surveillance shall be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months aher l

entering MODE 3 and prior to entering MODE 2.

" Except when off site power is not available and Reactor Coolant System pressure is less than 500 psig and Low Pressure Injection is not bypassed.

CRYSTAL IUVER UNIT 3 3/474 Amendment No. H,64,130 3

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ML20043E703

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