Text

Amend 93 to License NPF-58,revising TS Tables 3.3.5.1-1, Emergency Core Cooling Sys Instrumentation & 3.3.6.1-1, Primary Containment & Drywell Isolation Instrumentation, by Revising Allowable Values for Selected Plant Process
	ML20153D025
Person / Time
Site:	Perry
Issue date:	09/15/1998
From:	Pickett D; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20153D029	List: ML20153D025; ML20153D031;
References
	NUDOCS 9809240278
	Download: ML20153D025 (9)
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UNITED STATES g

,, j NUCLEAR REGULATORY COMMISSION o

f WA8HINGTON, D.C. 200 6 0001 kO o

CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.

DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-58 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The applicationfor amendmentby the Cleveland Electric illuminating Company (CEICO),

Centerior Service Company, Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc., Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated August 29,1995, supplemented June 25,1998, 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 facilitywill operate in conformity with the application, the provisions of the Act, and the rules and regulations of tne 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 amendmentwill 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.

2.

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 Operating License No. NPF-58 is hereby amended to read as follows:

9909240278 980915 PDR ADOCK 05000440 P

PDR

- (2) Technical Soscifications The Technical Specifications contained in Appendix A and the Environmenta! Protection Plan contained in Appendix B, as revised through Amendment No. 93 are hereby incorporatedinto this license. The Cleveland Electric illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendmentis effective as of its date of issuance and shall be implemented not later than 90 days afterissuance.

FOR THE NUCLEAR REGULATORY COMMISSION C, _

v' Wd Jtd Douglas V. Pickett, Senior Project Manager Project Directorate ill-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 15, 1998

ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 s

Replace the following pages of the Appendix "A" Technical Specificationswith the attached pages.

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

Remove Insert 3.3-39 3.3-39 3.3-40 3.3-40 3.3-42 3.3-42 3.3-43 3.3-43 3.3-54 3.3-54 3.3-63 3.3-63 4

a 4

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ECCS Instrum:ntMion 3.3,5.1 i

L, l

Table 3.3.5.1 1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPUCABLE CONDmONS MODES OR

. REQUIRED REFERENCED FUNCTION CO D S

-F ON Q R E S 1.

Low Pressure Coolant Pressure Co(LPCI) and Low injection-A re Spray (LPCS) Subsystems a.

Reactor VesselWater 1,2,3, 2(b)

B SR 3.3.5.1.1 a 14.3 inches Level - Low Low Low, SR 3.3.5.1.2 Level 1 4(a) 5(a)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 i

b.

Drywell Pressure - High 1,2,3 2(b)

B SR 3.3.5.1.1 s 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 c.

LPCI Pump A 1,2,3, 1

C SR 3.3.5.1.2 s 5.25 Start - Time Delay SR 3.3.5.1.4 seconds Relay 4(a) 5(a)

SR 3.3.5.1.6 d.

Reactor Vessel 1,2,3 1

C SR 3.3.5.1.1 a 482.7 psig Pressure - Low (LPCS SR 3.3.5.1.2 and injection Valve SR 3.3.5.1.3 s 607.7 psig Permissive)

SR 3 3 5.1.5 SR J.3.5.1.6 4(a) 5(a) 1 B

SR 3.3.5.1.1 a 482.7 psig SR 3.3.5.1.2 and SR 3.3.5.1.3 s 607.7 psig SR 3.3.5.1.5 SR 3.3.5.1.6 e.

Reactor Vessel 1,2,3 1

C SR 3.3.5.1.1 a 490.0 psig l

Pressure-Low SR 3.3.5.1.2 and lejection Valve (LPCI SR 3.3.5.1.3 s 537.1 psig l

Permissive)

SR 3.3.5.1.5 SR 3.3.5.1.6 4(a) 5(a) 1 B

SR 3.3.5.1.1 a 490.0 psig l

SR 3.3.5.1.2 and SR 3.3.5.1.3 s 537.1 psig l

SR 3.3.5.1.5 SR 3.3.5.1.6 f.

LPCS Pump Discharge 1,2,3, 1

E SR 3.3.5.1.1 a 1200 gpm Flow Low (Bypass)

SR 3.3.5.1.2 4(a) 5(a)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 (continued)

(a) When associated subsystem (s) are required to be OPERABLE.

(b) Also required to initiate the associated diesel generator and AEGT subsystem.

I PERRY - 1. NIT 1 3.3 39 Ara n ait No. 93

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l ECCS Instrumsntation 3.3.5.1 Table 3.3.5.1 1 (page 2 of 5)

Emergency Core Cooling System Instrumentation i.

Eks FUNCTION CN i S fun oN N

E TS l

i 1.

Low Pressure Coolant injection-A Pressure Co(LPCI) and Low re Spray l

(LPCS) Subsystems l(

(continued) g.

LPCI Pump A Discharge-1,2,3, 1

E SR 3.3.5.1.1 a 1450 gpm l

Flow - Low (Bypass)

SR 3.3.5.1.2 l

4(a) 5(a)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 h.

ManualInitiation 1,2,3, 1

C SR 3.3.5.1.6 NA 4(a) 5(a) 2.

LPCI B and LPCI C i.

Subsystems -

a.

Reactor VesselWater 1,2,3, 2(b)

B SR 3.3.5.1.1 a 14.3 inches -

Level Low Low Low, SR 3.3.5.1.2 Level 1 4(a) 5(a)

SR 3.3.5.1.3

~

SR 3.3.5.1.5 SR 3.3.5.1.6 b.

DrywellPressure High 1,2,3 2(b)

B SR 3.3.5.1.1 s 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 4

SR 3.3.5.1.6

)

B Start -

1,2,3, 1

C SR 3.3.5.1.2 s 5.25 LPCI Pu$ay Relay c.

Time De SR 3.3.5.1.4 seconds

)

4(a) 5(a)

SR 3.3.5.1.6 d.

ReactorVessel 1,2,3 1

r C

SR 3.3.5.1.1 a 490.0 psig

'l Pressure - Low (LPCI subs tem SR 3.3.5.1.2 and s 537.1 psi i

injection Valve SR 3.3.5.1.3 for LPCI B;g Permissive)

SR 3.3.5.1.5 SR 3.3.5.1.6 and a 490.0 psig l

and s 537.1 psig

'l for LPCI C 4(a) 5(a) 1 per B

SR 3.3.5.1.1 a 490.0 psig l

subsystem SR 3.3.5.1.2 and for LPCI B;g l

SR 3.3.5.1.3 s 537.1 psi SR 3.3.5.1.5 4

SR 3.3.5.1.6 and a 490.0 psig l

and s 537.1 psig l

for LPCI C (continued)

(a). When associated subsystem (s) are required to be OPERABLE.

(b) Also required to initiate the associated diesel generator and AEGT subsystem.

L PEIRY - LNIT 1 3.340 Amerrhent No. 93

ECCS InStrum ntation 3.3.5.1 1

Table 3.3.5.1 1 (page 4 of 5)

Emergency Core Cooling System Instrumentation M E R REoVIRED REF NCED FUNCTION CoND N3 FUN ION UR ENTS 3.

High Pressure Core l

Spray (HPCS) System

)

(continued) f.

HPCS Pump 1,2,3, 1

E SR 3.3.5.1.1 a 120 psig Discharge SR 3.3.5.1.2 Pressure - High 4(a) $(a)

SR 3.3.5.1.3 (Bypass)

SR 3.3.5.1.5 SR 3.3.5.1.6 g.

HPCS System 1,2,3, 1

E SR 3.3.5.1.1 2 600 gpm Flow Rate Low.

SR 3.3.5.1.2 (Bypass) 4(a) $(a)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 h.

ManualInitiation 1,2,3, 1

C SR 3.3.5.1.6 NA 4(a) 5(a) 4.

Automatic Depressurization System (ADS) Trip System A a.

Reactor Vessel 1,2(d) 3(d) 2 F

SR 3.3.5.1.1 a 14.3 inches Water Level-Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 b.

ADS Initiation 1,2(d) 3(d) 1 G

SR 3.3.5.1.2 a 100.5 seconds Timer SR 3.3.5.1.4 and SR 3.3.5.1.6 s 109.5 seconds c.

Reactor Vessel 1,2(d) 3(d) 1 F

SR 3.3.5.1.1 a 177.1 lnches Water Level Low, SR 3.3.5.1.2 Level 3 SR 3.3.5.1.3 (Confirmatory)

SR 3.3.5.1.5 SR 3.3.5.1.6 d.

LPCS Pump 1,2(d) 3(d) 2 G

SR 3.3.5.1.1 a 125 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 e.

LPCI Pump A 1,2(@,3(@

2 G

SR 3.3.5.1.1 a 115 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 f.

ManualInitiation 1,2(d) 3(d) 2 G

SR 3.3.5.1.6 NA (continued)

(a) When associated subsystem (s) are required to be OPERABLE.

(d) With reactor steam dome pressure > 150 psig.

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PERRY I. NIT 1 3.3 42

/,radiat No. 93

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ECCS Instrum:nt tion 3.3.5.1 Table 3.3.5.1 1 (page 5 of 5)

Emergency Core Cooling System Instrumentation l

E R REQUIRED RE CED FUNCTION co OT NS F

ION Q R E S U

i l

S.

ADS Trip System B l

a.

Reactor VesselWater 1,2(d) 3(d) 2 F

SR 3.3.5.1.1 a 14.3 inches i

Level - Low Low Low, SR 3.3.5.1.2 Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 b.

ADS Initiation Timer 1,2(d) 3(d) 1 G

SR 3.3.5.1.2 a 100.5 SR 3.3.5.1.4 seconds and SR 3.3.5.1.6 s 109.5 seconds c.

Reactor VesselWater 1,2(d) 3(d) 1 F

SR 3.3.5.1.1 a 177.1 Level Low, Level 3 SR 3.3.5.1.2 inches (Confirmatory)

SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 d.

LPCI Pumps B & C 1,2(d) 3(d) 2 per pump G

SR 3.3.5.1.1 a 115 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 e.

Manualinitiation 1,2(d) 3(d) 2 G

SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig.

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l PERRY LNIT 1 3.3 43 k a s a t No. 93

Primary Cont:inment and Dryw:ll isolation Instrum*ntation 3.3.6.1 Table 3.3.6.1 1 (page 1 of 6)

Primary Contalrunent and Drywell isolation instrumentation APPLICABLE CON 0lil0NS MODES OR REQUIRED REFERENCED oTNER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWA8LE FUNCTION CON 0lil0NS SYSTEM ACTION C.1 REQUIREMENTS VALUE 1.

Main Steam Line Isolation a.

Reactor VesselWater 1,2,3 2

D SR 3.3.6.1.1 a 14.3 inches Level-Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.3 SR 3.3.6.1.4 SR. 3.3.6.1.5 SR 3.3.6.1.6 b.

Main Steam Line 1

2 E

SR 3.3.6.1.1 2 795.2 psig l

Pressure Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 c.

Main Steam Line 1,2,3 2 per MSL D

SR 3.3.6.1.1 s 189.3 psid l

Flow - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 d.

Condenser Vacuum -

1,2(a) 2 D