ML20101B293

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Correction to Amend 79 to License NPF-58.Correction Due to Page Being Inadvertently Deleted During Reproduction of Document
ML20101B293
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/08/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20101B297 List:
References
NUDOCS 9603140190
Download: ML20101B293 (7)
v • d • e


Text

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4 UNITED STATES a

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 y.....j 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.

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 November 22, 1993, supplemented Nay 5 and December 20, 1995, 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.

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:

9603140190 960308 PDR ADOCK 05000440 P

PDR

ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications including the issued but not yet implemented Improved Technical Specifications (ITS) with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 3-23 3/4 3-23 e

3/4 3-24 3/4 3-24 3/4 3-25 3/4 3-25 3/4 3-N 3/4 3-26 1

d.

4 1

J 1 -

e d

b TABLE 4.3.2.1-1 la

/

fi

-ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

CHANNEL OPERATIONAL t

5 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

[

TRIP FUNCTION CHECK _

TEST CALIBRATION SURVEILLANCE REQUIRED 1.

PRIMARY CONTALNMENT ISOLA" ION

a. Reactor Vesse' Water Level -

Low. Level 2 S

0 R(""*"d'

1. 2. 3 and #
b. Drywell Pressure - High #

S Q

R'*'

1. 2, 3
c. Containment and Drywell Purge Exhaust Plenum Radiation -

High S

0 R'd' -

1. 2. 3 and *
d. Reactor Vessel Water Level -

Low. Level 1 S

Q R* * **'

1. 2. 3 and i
e. Manual Initiation R

NA Rcd)

NA 1, 2. 3 and

  • i l

2.

MAIN STEAM LINE ISOLATION Y

a. Reactor Vessel Water Level -

i3 Low. Level 1 S

0 R(6Hexd>

1. 2. 3
b. Main Steam Line Radiation -

High S

Q R(*"d)

c. Main Steam Line Pressure -

i Low S

Q R(6' 1

d. Main Steam Line Flow - High S

0 R(6'

1. 2. 3
e. Condenser Vacuum - Low S

0 R(6'

1. 2**. 3**

~

f. Main Steam Line Tunnel Temperature - High R

1.

Division 1 and 2 S.

SA R

1. 2. 3 i

8 2.

Division 3 and 4 S

Q R.

1, 2. 3 g

g.

Main Steam Line Tunnel A Temperature - High 1.

Division 1 and 2 S

SA R

1. 2. 3 i

is 2.

Division 3 and 4 S

Q R

1. 2. 3
h. Turbine Building Main Steam 12 Line Temperature - High S

0 R

1. 2. 3 g
1. Manual Initiation NA R

NA

1. 2, 3
a r

?w to

A

o E

lii TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION

_ CHECK TEST M

SURVEILLANCE REQUIRED 3.

SECONDARY CON"AINMENT ISOLATION

[

a. Reactor Vesse' Water Level - Low. Level 2 S

Q R(6"*"*

1. 2, 3 and #
b. Drywell Pressure - High ##

S Q

R(6)

1. 2. 3
c. Manual Initiation NA R

NA

1. 2. 3 and
  • R 4.

REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow High S

Q R

1. 2. 3 y
b. A Flow Timer NA Q

R

1. 2. 3 y
c. Equipment Area Temperature -

i High S

SA R

1, 2. 3

d. Equipment Area Ventilation i

A Temperature - High S

SA R

1. 2. 3
e. Reactor Vessel Water Level - Low. Level 2

-S Q

R(6"*xe

1. 2. 3
f. Main Steam Line Tunnel Ambient i

Temperature - High S

SA R-

1. 2. 3 l
g. Main Steam Line Tunnel y

A Temperature - High S

SA R

1, 2. 3 i

t g

h. SLCS Initiation NA Q*

NA

1. 2. 3 g-
1. Manual Initiation NA R

NA

1. 2. 3 2

1 r+

0

~

i t

k A

i m

TABLE 4.3.2.1-1 (Continued) f g

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL.

FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK -

TEST CALIBRATION SURVEILLANCE REQUIRED 5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High S

Q R(

1. 2. 3 b.

RCIC Steam Supply Pressure -

[

Low S

Q R(6'

1. 2. 3 i.

c.

RCIC Turbine Exhaust Diaphragm Pressure - High S

0 R(6'

1. 2, 3 d.

RCIC Equipment Room Ambient m;

Temperature - High S

SA R

1. 2. 3 l

e.

Deleted f.

Main Steam Line Tunnel Ambient l

OI Temperature - High S

SA R

1. 2. 3 l

f g.

Main Steam Line Tunnel l

A Temperature - High S

SA R

1. 2. 3 l

r h.

Main Steam Line Tunnel Temperature Timer NA SA R

1. 2. 3 1

i.

RHR Equipment Room Ambient i

Temperature - High

'S SA R

1. 2. 3 l

j.

RHR Equipment Room A Temperature - High S

SA

.R

1. 2. 3 l

F k.

RCIC Steam Line Flow High Timer NA Q

R

1. 2, 3 y

1.

Drywell Pressure - High S

0 R

1. 2. 3 i

i g

m.

Manual Initiation NA gm NA

1. 2. ' 3 p

a ji

~

l

=

TARIF 4.3.2.1-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

CHANNEL OPERATIONAL CHANNEL.

FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION

. CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

.t 6.

RHR SYSTEM ISOLATION a.

RHR Equipment Area Ambient Tenperature - High S

SA R

1. 2. 3 -

l i

b.

RHR Equipment Area A Temperature - High S

SA R

1. 2. 3 c.

RHR/RCIC Steam Line i

g Flow - High S

Q R*

1, 2. 3 y

d.

Reactor Vessel Water Level -

g Low, Level 3 #

S Q

R'"" *""

1. 2. 3 l

e.

Reactor Ves el (RHR Cut-in Permissi e) Pressure - High S

Q R,g,x.

1, 2, b r

f.

Drywell Pressure - High #

S Q

R*"*

1. 2. 3 g.

Manual Initiation NA R(*

NA

1. 2. 3 g

with a potential for draining the reactor vessel.

g-

    • When any turbine stop valve is greater than 90% open and/or the key locked bypass switch is g

in the normal )osition.

      • OPERATIONAL C04DITION 1 or 2 when the mechanical vacuta pump lines are not isolated.

g

  1. During CORE ALTERATION and operations with a potential for draining the reactor vessel.

(a) Each train or logic channel shall be tested at least every other 92 days.

(b) Calibrate trip unit setjoint at least once per 92 days.

3

  1. These Trip Functions (1). 3b. 6d. and 6f) utilize instruments which are conson to RPS instrumentation.

N fcl CHANNEL CALIBRATION may be extended to be performed during the fifth refueling outage.

jN (d) LOGIC SYSTEM FUNCTIONAL TEST may be extended to be performed during the fifth refueling outage.

5

Mr. Donald C. Shelton Perry Nuclear Power Plant Centerior Service Company Unit Nos. I and 2 cc:

Jay E. Silberg, Esq.

Mr. James W. Harris, Director Shaw, Pittman, Potts & Trowbridge Division of Power Generation 2300 N Street, N. W.

Ohio Dept. of Industrial Relations Washington, D. C.

20037 P.O. Box 825 Columbus, Ohio 43216 Ms. Mary E. O'Reilly Centerior Energy Corporation The Honorable Lawrence Logan 300 Madison Avenue Mayor, Village of Perry Toledo, Ohio 43652 4203 Harper Street Perry, Ohio 44081 Resident Inspector's Office U. S. Nuclear Regulatory Commission The Honorable Robert V. Orosz Parmly at Center Road Mayor, Village of North Perry Perry, Ohio 44081 North Perry Village Hall 4778 Lockwood Road Regional Administrator, Region III North Perry Village, Ohio 44081 U. S. Nuclear Regulatory Commission 801 Warrenville Road Attorney General Lisle, Illinois 60532-4531 Department of Attorney General 30 East Broad Street Lake County Prosecutor Columbus, Ohio 43216 Lake County Administration Bldg.

105 Main Street Radiological Health Program Painesville, Ohio 44077 Ohio Department of Health P.O. Box 118 Ms. Sue Hiatt Columbus, Ohio 43266-0118 OCRE Interim Representative 8275 Munson Ohio Environmental Protection Mentor, Ohio 44060 Agency DERR--Compliance Unit Terry J. Lodge, Esq.

ATTN: Mr. Zack A. Clayton 618 N. Michigan Street, Suite 105 P.O. Box 1049 Toledo, Ohio 43624 Columbus, Ohio 43266-0149 Ashtabula County Prosecutor Mr. Thomas Haas, Chairman 25 West Jefferson Street Perry Township Board of Trustees Jefferson, Ohio 44047 3750 Center Rd., Box 65 Perry, Ohio 44081 Mr. James D. Kloosterman Regulatory Affairs Manager State of Ohio Cleveland Electric Illuminating Public Utilities Commission Company East Broad Street Perry Nuclear Power Plant Columbus, Ohio 43266-0573 P. O. Box 97, E-210 Perry, Ohio 44081 Mr. Richard D. Brandt, Plant Manager Cleveland Electric Illuminating Mr. James R. Williams, Chief of Company Staff Perry Nuclear Power Plant Ohio Emergency Management Agency P.O. Box 97, SB306 2825 West Granville Road Perry, Ohio 44081 Worthington, Ohio 43085

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