Text

Amend 50 to License NPF-58,clarifying Logic for Instrumentation Used to Isolate HPCS Test Return Valve
	ML20056F350
Person / Time
Site:	Perry
Issue date:	08/11/1993
From:	Robert Stransky; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20056F351	List: ML20056F350; ML20056F353;
References
	NUDOCS 9308270019
	Download: ML20056F350 (11)
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UNITED STATES

~ j NUCLEAR REGULATORY COMMISSION W ASHINGTON, D.C. 200Ei6-0001 l

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l THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.

DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. NPF-58 1.

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

A.

The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company,' Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company- (the licensees) dated October.30,1991, complies with the standards and requirements of the' Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i

regulations set forth in 10 CFR Chapter I; B.

The facility will operate 'in conformity with the application, the i

provisions of the Act, and the rules and regulations of the i

Commission; C.

There is reasonable assurance (1) 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-i have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby-amended to read as follows:

)

9308270019 930811:

-i PDR ADOCK 05000440 P

PDR I

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1 i' i (2)

Technical Specifications

)

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised l

through Amendment No. 50 are hereby incorporated into this i

license.

The Cleveland Electric Illuminating Company shall i

operate the facility in'accordance with the Technical Specifi-cations and the Environmental Protection Plan.

j l.

3.

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

i 1

FOR THE NUCLEAR REGULATORY COMMISSION I-l

,~ ;/:%-O etrert3. Stransky, Project Manager Project Directorate III-3 l

Division of Reactor Projects III/IV/V j

Office of Nuclear Reactor Regulation '

i l

Attachment Changes to the Technical l

Specifications l

l Date of issuance:

August 11, 1993 l

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, _. ;, _ L,.._

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ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET N0. 50-440 l

Replace the following pages of the Appendix "A" Technical Specifications with l

the attached pages.

The revised pages are identified by Amendment number and l

contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.

Remove Insert 3/4 3-11 3/4 3-11 l

3/4 3-15 3/4 3-15 l

l 3/4 3-16 3/4 3-16 3/4 3-30 3/4 3-30 t

3/4 3-31 3/4 3-31 l

i i

l'

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TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION

5 OPER L ANNELS hk L

g TRIP FUNCTION PER TRIP SYSTEM (a)

COND ON ACTION

[

1.

PRIMARY CONTAINMENT ISOLATION f*beyY'h'Dh!Io k2) o 2

1, 2, 3 and i 20 b.

Wate Level -

Reactor V sse Low,Leve$2 Divls50n3) 4(d) 1, 2, 3 and #

28 Y5mlo!'I'l"21-Hih c.

9 2

i, 2, 3 20 q

d.

g{frgsure-High 4ca) 1, 2, 3 28 hu" ES ladl tion us$ 1 n 4

High 2cb3 1, 2, 3 and

21 f.

{ectgysgelWaterLevel-2 1, 2, 3 and i 20 f$y"isio I $"

2(*)

1, 2, 3 and

22 9'

e g

h.

ggugigt 3c.)

1, 2, 3 and

28 ation 2.

MAIN STEAM ISOLATION ysgelWaterLevel-

{e t

a.

2 1, 2, 3 20 N$h7a! Yon"- $gh.

2 1, 2 23 I

c.

Main Steam.ine a

Pressure

.ow 2

1 24

$!$h 2/line 1, 2, 3 23

?

e.

Condenser Vacuum - Low 2

1, 2**, 3**

23 E

f.

Main Steam Line Tunnel i

Temperature - High 2-1, 2, 3 23

$*be"mh'$In YgS 2

1,2,3 23 9'

l h.

Turbine Building Main Steam Line Temperature - High 2

1,2,3 23 1.

Manual Initiation 2

1, 2, 3 22 i

I

3 TABLE 3.3.2-1 (Continued) g ISOLATION ACTUATION INSTRUNENTATIO_N e

g NININUM APPLICABLE q

TRIP FUNCTION OPERABLE CHANNELS OPERATIONAL PER TRIP SYSTEN (a)

_ CONDITION ACTION N

3.

SECONDARY CONTAIMENT ISOLATION a.

Reactor Vessel Water Level - Low, Level 2 2

1, 2, 3 and #

25 1

b.

Drywell Pressure - High 2

1,2,3 25 l

c.

Manual Inftfatton 2

1,2,3 22 2

25 4.

REACTOR W TER CLEANUP SYSTEN__ ISOLATION a.

A Flow - High 1

1,2,3 27 b.

A Flow Tfeer 1

1,2,3 27 D

c.

Equipment Area Temperature -

y Nigh 1

1, 2, 3 27 U

d.

Equipment Area a Temperatum - High 1

1,2,3 27 e.

Reacter Vessel Water Level -

i Low, Level 2 I

2 1,2,3 27 f.

Main Steam Line Tunnel Ambient Temperature - High L

1 1,2,3 27 S

p.

Mafn Steam Line Tunnel a

[g=,

Temperature - High 1

1,2,3 27

=3 h.

SLCS Initiation 1

1,2,3 27 hE f.

Manuel Inftfation 2

1,2,3 26 2

i i

e j

f'*

TABLE 3.3.2-1 (Continued) i ISOLATION ACTUATION INSTRUMENTATION I,

ACTION

}

ACTION 20 In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

In OPERATIONAL CONDITION f, suspend CORE ALTERATIONS and 1

operations with a potential for draining the reactor vessel.

Close the affected system isrlation valve (s) within one hour or:

ACTION 21 a.

In OPERATIONAL CONDITICA 1, 2 or 3, be in at least HDT SHUTDOW within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOW within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In Operational Condition *, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary containment and operations with a potential for draining the reactor vessel.

ACTION 22 Restore the manual initiation function to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or:

a.

In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOW within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOW within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling of irradiated fuel in the primary containment.

ACTION 23 Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOW within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTJON 25 Verify SECONDARY CONTAINMENT INTEGRITY with the annulus exhaust gas treatment system operating within one hour.

ACTION 26 Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and declare the affected system inoperable.

Close the affected system isolation valves within' one hour and ACTION 27 declare the affected system inoperable.

ACTION 28 Within one hour lock the affected system isolation valves closed, or verify, by remote indication, that the valve (s) is closed and electrically disarmed, or isolate the penetration (s) and declare l

the affected system inoperable.

NOTES When handling irradiated fuel in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When any turbine stop valve is greater than 90% open and/or the key locked Condenser Low Vacuum Bypass Switch is in the normal position.

During CORE ALTERATIONS and operations with a potential-for draining the reactor vessel.

PERRY - UNIT 1 3/4 3-15 Amendment No.30,A?,50-

TABLE 3.3.2-1 (Continued)-

ISOLATION ACTUATION INSTRUMENTATION ACTION NOTES (Continued)

(a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Containment and Drywell Purge System inboard and outboard isolation valves each use a separate two out of two isolation logic.

(c) There is only one (1) RCIC manual initiation channel for RCIC system containment isolation valves.

(d) Division 3 has only one trip system consisting of four channels logically combined in a one-out-of-two-twice configuration which only closes the HPCS Suppression Pool Test Return Valve (1E22-F023).

(e) Division 3 Manual Initiation consists of a single channel in a single trip system.

PERRY - UNIT 1 3/4 3-16 Amendment No. (g,50

O TABLE 3.3.3-1 (Continued) h EMERGENCY CORE COOLING SYSTEM ACTDATION INSTRUMENTATION 4

MINIMUM OPERABLE APPLICABLE CHANNELS PER OPERATIONAL TRIP FUNCTION (a)

CONDITIONS ACTION e

]

TRIP FUNCTION B.

DIVISION 2 TRIP SYSTEM 1.

RHR 8 AND C (LPCI MODE) a.

Reactor Vessel Water level - Low, Level 1 2

1, 2, 3, 4*, 5*

30 b.

Drywell Pressure - High 2

1,2,3 30 c.

Reactor Vessel Pressure - Low (LPCI Injection 1

1,2,3 31 Valve Permissive) 4*, 5*

32 d.

LPCI Pump B Start Time Delay Relay 1

1, 2, 3, 4*, 5*

31 e.

LPCI Pump Discharge Flow - Low (Bypass) 1/ pump 1, 2, 3, 4*, 5*

39 f.

Manual Initiation 1

1, 2, 3, 4*, 5*

33 AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B"#

2.

a.

Reactor Vessel Water Level - Low,' Level 1 2(b) 1, 2, 3 30 b.

Manual Inhibit 1

1,2,3 33 c.

ADS Timer 1

1,2,3 31 d.

Reactor Vessel Water Level - Low, Level 3 (Permissive) 1 1,2,3 31 e.

LPCI Pump B and C Discharge Pressure - High (Permissive) 2 1,2,3 31 f.

Manual Initiation 2

1,2,3 33 i

i

- + - -

u

TABLE 3.3.3-1 (Centinued)

EMERGCMCY CORE COOLING SYSTEM ACTUATION INSTRIBENTATION

R E

MINIMUM OPERABLE APPLICABLE 4

l OPERATIONAL CHANNELS PER I*)

TRIP FUNCTION CONDITIONS ACTION E

TRIP FUNCTION U

C.

DIVISION 3 TRIP SYSTEM 1.

HPCS SYSTEM 4(b) 1, 2, 3, 4*, 5*

34 Reactor Vessel Water Level - Low, level 2 a.

IDI Drywell Pressure - High" 4

1, 2, 3 34 b.

4 *)

1, 2, 3, 4*, 5" 34 I

Reactor Vessel Water Level - High, Level 8 c.

Id) d.

Condensate Storage Tank Level - Low 2

1, 2, 3, 4*, 5*

35 Id) 2 1, 2, 3, 4*., 5*

35 Suppression Pool Water Level - High e.

f.

HPCS Pump Discharge Pressure - High (Bypass) 1 1,2,3,4*,5*

39 1

1, 2, 3, 4*, 5*

39 R

g.

HPCS System Flow Rate - Low (Bypass) b h.

Manual Initiation" 1

1,2,3,4*,5*

36 MINIMUM APPLICABLE TOTAL NO. CHAf8tELS OPERA 8LE OPERATION 4L OF CHANNELS TO TRIP CHANNELS CONDITIONS ACTION '

i D.

LOSS OF POWER 4.16 kw Emergency Bus Undervoltage #

2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**

3?

1.

g

-(Loss of Voltage) g, E

2.

4.16 kw Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**

38

=

l (Degraded Voltage)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during periods of required (a)

E survelliance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

o (b) Also actuates the associated divisten diesel generator.

(c) Provides signal to close HPCS pump injection valve only.

Provides signal to HPCS pump suction valves only.

(d)

When the system is required to be OPERA 8tE per S-;wcification 3.5.2 or 3.5.3.

Required when ESF equipment is required to be OPERABLE.

Not required to be OPERA 8tE when reactor steam dome pressure is less than or equal to 100 psfg.

The injection function of Drywell Pressure - High and Manual Initiation are not required to M

be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level 8 setpoint coincident with the reactor pressure less than 450 psig.

N# The Loss of Voltage and Degraded Voltage functions are common to Olvisions 1, 2 and 3.

b ec-

-e

=v=ei

-e---m---->-e%=

-ce m

=%*eg r

-a---ry m

m m.

m.

1 I

L.-

l TABLE 3.3.3-1(Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSYRLMENTATION ACTION 1'

ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within one hour or declare the i

associated system inoperable.

i b.

With more than one channel inoperable, declare the associated j

system inoperable.

I ACTION 31 -

With the number of OPERABLE channels less than required by the

{

Minimum OPERABLE Channels per Trip Function requirement

{

declaretheassociatedADStripsystemorECCSinoperable.

i ACTION 32 With the number of OPERABLE channels less than the Minimum i

CPERABLE Channels per Trip Function requirement, place the i

inoperable channel in the tripped condition within one hour.

l ACTION 33 -

With the number of OPERABLE channels less than required by the j

Minimum 0PERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the associated ADS valve or ECCS inoperable.

ACTION 34 -

With the number of OPERABLE channels less than required by i

the Minimum OPERABLE Channels per Trip Function requirement,

{

place the inoperable channels (s) in the tripped condition j

within one hour or declare the HPCS system inoperable.

/

4 ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour, or align the NPCS system to take suction from the j

suppression pool, or declare the HPCS system inoperable, i

ACTION 36 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within l

one hour or declare the NPCS system inoperable.

}

ACTION 37 -

With the number 0/ OPERABLE channels less than the Total Number i

of Channels, declare the associated emergency diesel nonerator

{

inoperable and take the ACTION required by Specificat' on 3.8.1.1 l

or 3.8.1.2, as appropriate.

l ACTION 38 -

With the number of OPERABLE channels less than the Total Number i

of Channels, place the inoperable channel in the tripped condi-i tion within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then continue until perform-j ance of the next required CHANNEL FUNCTIONAL TEST.

l ACTION 39 With the number of OPERABLE channels less than required by the 1

Minimum 0PERABLE Channels per Trip Function requirement, place I

the inoperable channel in the tripped condition within one hour.

Restore the inoperable channel to OPERABLE status within 7 days

]

or declare the associated system inoperable.

PERRY - UNIT 1 3/4 3-31 Amendment nom 50, im

~

A TABLE 3.3.3-2 E

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS e

g ALLOWABLE y

TRIP FUNCTION 1 RIP SETPOINT VALUE A.

DIVISION 1 TRIP SYSTEM 1.

RHR-A (LPCI MODE) AND LPCS SYSTEM

a. -Reactor Vessel Water Level - Low, level 1

> 16.5 inches

1 14.3 inches b.

Drywell Pressure - High i 1.68 psig i 1.88 psig c.

LPCS Pump Discharge Flow - Low (Bypass) 1 1350 gpm 2 1200 gpm d.

Reactor Vessel Pressure - Low (LPCS Injection 577.7 1 15 psig 577.7 + 30. -95 psig Valve Permissive) e.

Reactor Vessel Pressure - Low (LPCI Injection 502.5 + 5. -10 psig

. 502.5 + 10, -40 psig Valve Pemissive) f.

LPCI Pump A Start Time Delay Relay i 5 seconds i 5.25 seconds g.

LPCI Pump A Discharge Flow - Low (Bypass) 3 1650 gpa 2 1450 gpa h.

Manual Initiation NA NA 2.

AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"

[

-a.

Reactor Vessel Water Level - Low, t 16.5 inches *

> 14.3 inches N

Level 1 b.

Manual Inhibit NA NA l

c.

ADS Timer

< 105 seconds

< 117 seconds d.

Reactor Vessel Water Level - Low, Level 3

[177.7 inches *

[177.1 inches (Permissive) i e.

LPCS Pump Discharge Pressure - High 1 145-psig, increasing 1 125 psig, increasing (Permissive) f.

LPCI Pump A Discharge Pressure - High 1 125 psig, increasing

-1 115 psig, increasing l

(Permissive) g.

Manual Initiation NA NA I

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ML20056F350

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