ML20097D830

Amend 43 to License NPF-58,revising TS 3.3.2-2 & Deleting Footnote Re Setpoint Adjustments Found During Startup Test Program

ML20097D830
Person / Time
Site:	Perry  (NPF-58-A-043, NPF-58-A-43)
Issue date:	05/28/1992
From:	Hall J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20097D831	List: ML20097D830 ML20097D834
References
NUDOCS 9206110152
Download: ML20097D830 (7)

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UNITED STATES p,

NUCLEAR REGULATORY COMMISSION

y WASHINGTON, D. C. 20ss5

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.

DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE j

Amendment No. 43 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 February 8, 1988, as supplemented March 14, 1990 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 i_n 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 secur ty or to the health'and safety of-the public; and i

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

+

9206110152 920528 P

' ADOCK 05000440 PDR PDR

(2) Technical Specifications i

The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 43 are hereby incorporated into this license.

The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, y

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3.

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

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FOR T'!E NUCLEAR REGULATORY COMMISSION n.LL es R. Hall, Sr.-Project Manager l

Project Directorate III l Division of Reactor Projects _III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical 4

j Specifications Date of issuance: May 28,1992 1

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

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

Overleaf pages are provided to maintain document completeness.

Remove Inse_rt 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 t

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l-TABLE 3.3.2-2 t

-ISCLATION ACTUATION INSTRUMENTATION SETPOINTS o

ALLOWABLE y

TRIP FUNCTION TRIP SETPOINT VALUE 7

1.

PRIMARY CONTAINMENT ISOLATION

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i

' c:

a.

Reactor Vessel Water Level -

j j

Low, Level 2 1 129.8 inches *

> 127.6 inches i

b.. Drywell Pressure - liigh 1 1.68 psig 1 1.88 psig c.

Containment and Drywell Purge L

Exhaust Plenim Radiation - High

< 2.mR/hr above. background.

1 4 mR/hr above background l

I d.

Reactor Vessel Water Level -

i-

. Low, Level 1

> 16.5 inches *

> 14.3 inches i

-i e.

Manual.: Initiation NA NA j-2.

MAIN STEAM LINE ISOLATION j

Y a.

Reactor Vessel Water Level -

- C

. Low,-. Level 1

> 16.5 inches *

> 14.3 inches b.

Main Steam Line Radiation "igh 1 3.0 x full power' background

< 3.6 x full power background c.

Main Steam Line Pressure'- Low

> 807.0.psig

> 795.0 psig f

~

d. ~ Main Steam Line Flow - High-

< 183 psid i 191 psid j

e.

CondenserJacuum - Low i

. _ 8.5 inches Hg. vacuum

> 7.6 inches Hg. vacuum I

h f.

Min. Steam Line Tunnel-

. g Temperature - High

< 154.4*F

< 158.9*F l

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g.. Main. Steam Line Tunnel

~

a Temperature - High

< 103.6*F-

< 107.4*F l

h.

Turbine Building Main Steam Line

- O Temperature.- High

< 134.4 F

< 138.9*F-r

i. Manual Initiation

.NA NA i

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F TABLE 3.3.2-2 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

'N j8 ALLOWABLE

{

TRIP FUNCTION TRIP SETPOINT VALUE-E 3.

SECONDARY CONTAINMENT ISOLATION U

a.

. Reactor Vessel Water Level -

Low, Level 2

> 129.8 inches *

> 127.6 inches b.

Drywell Pressure - High 1.68 psig 1.88 psig c.

Manual Initiation

-NA RA 1

l 4.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High.

1 68 gpm 1 17.1 gpm l

b.

A Flow Timer

-< 45 seconds

< 47 seconds t

,L Aw

c. -Equipment Area TemperatureL-High u.

w 1.

RWCU Hx Room

< 136.4*F

< 138.9*F d

2..

Pump Rooms, Valve Nest Room i135.4F 5137.9*F-d.

Equipment Area a Temperature - High 1.

RWCU Hx Room.

< 76.65 F

< 78.4*F i28.65F i30.4*F 2.

.RWCU Pump Rooms, Valve Nest' Room k

e'. - Reactor Vessel Water Level -

8.

-Low, Level 2

'>-129.8 inches *

> 127.6 inches

,y a

g f.

Main ~ Steam Line Tunnel Ambient 154.4 F.

< 158.9'F l'

Temperature - High x

P

g.. Main Steam Line Tunnel' A Temperature' High 1.103.6*F 1 107.4*F l

i.

F, I,

h. : SLCS. Initiation -

NA-NA l

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i i.- Manual Initiation NA

. NA 1

L.

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=an,.

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TARIE 3.3.2-2 (Continued) y ISOLATION ACTUAfl0N INSTRUMENTATION SETPOINTS 5

ALLOWABLE

[

TRIP FUNCTION TRlP SETPOINT VALUE z

Q 5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a..

RCIC Steam Line Flow - High 1 290" H O

< 298.5" H O l

2 2

b.

RCIC Steam Supply Pressure - Low

> 60 psig y_ 55 psig c.

RCIC Turbine Exhaust Diaphragm Pressure - High 1 10 psig i 20 psig d.

RCIC Equipment Room Ambient Temperature - High

< 143.4*F

< 145.9'F w

e.

RCIC Equipment Room a g

Temperature - High

< 95.9 F

< 97.2*F f.

Main Steam Line Tunnel Ambient Temperature - High 1 154.4 F 1 158.9 F g.

Main Steam Line Tunnel a Temperature - High

< 103.6*F

< 107.4*F h.-

Main Steam Line Tunnel Temperature Timer 1 29 minutes 1 30 minutes

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i.

RHR Equipment Room Ambient y

Temperature - High

< 157.4*F

< 159.9'F

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RHR Equipment Room y

a Temperature - High

< 50.65*F

< 52.4 F k.

RCIC Steam Flow High Timer 3 seconds i t i 13 seconds 3 seconds i t i 13 seconds 1.

Drywell Pressure - High 1 1.68 psig i 1.88 psig m.

Manual Initiation NA NA 1

=

r TABLE 3.3.2-2 (Continued) i o

g.

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS t

ALLOWABLE 4

e i:

y TRIP FUNCTION TRIP SETPOINT VALUE z.

6.

. RHR SYSTEM ISOLATION E

a.

-RHR Equipment Area _ Ambient j

[

Temperature - High-

< 157.4*F

< 159.9'F 4:

b.

RHR Equipment Area a Temperature -

High

< 50.65*F 1 52.4*F 7.

c..

RHR/RCIC Steam Line Flow:- High 1 52.1" H O 1 55.6" H O i

2 2

ld..

' Reactor Vessel Water Level Low

_m.

A-Level.3-

> 177.7 inches *

> 177 1 inches w-43 -

e. :

Reactor Vessel (PHR Cut-in 6

. Permissive) Pressure - High

< 135 psig.

1 150 psig-f.

Drywell Pressure High 1 1.68 psig i.88 psig 1

g. -

Manual - Initiation '

NA

-NA 2

. R

• See Bases Figure B 3/4 3-1.

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