ML19289E864

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Tech Spec Change Request 72,Addendum 1,adding New Safety Sys Setting
ML19289E864
Person / Time
Site: Oyster Creek
Issue date: 05/23/1979
From:
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19289E853 List:
References
NUDOCS 7905290198
Download: ML19289E864 (6)
v • d • e


Text

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q JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION Provision Operating License No. DPR-16 Operating License Change Request No. 72, Addendum 1 Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No. 72, Addendum 1, to the Oyster Creek Nuclear Generating Station Operating License, changes to incorporate a new safety system setting to Section 2.3 of Appendix A.

JERSEY CENTRAL POWER & LIGHT COMPANY BY V

' bid ff /.YI' h VICE PRES ENT /

STATE OF NEW JERSEY )

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COUNTY OF MORRIS )

Sworn and subscribed to before me this JJ m,.' day of 7' a.y , 1979.

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Notary Public PM'/'_'..*3 A. :"C3 1:0 TAP.'l kT.'0 C? .':E'/l JERSEY 1,1y C:mmini= Er;. cs ,k;.16,1973 2047 193 7905290198

- UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF )

) DOCKET NO. 50-219 JERSEY CENTRAL POWER & LIGHT COMPANY)

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 72, Addendum 1, for the Oyster Creek Nuclear Generating Station Operating License, was filed with the U. S. Nuclear Regulatory Commission on May 23, 1979 , and has this 23rd day of May 1979 been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Mary Lc,u Smith Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08731 JERSEY 5 3RAL POWER & LIGHT COMPANY

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BY VICE PRESIDENT v

y DATED: May 23, 1979 204/ .?94

, si Jersey Central Power & Ught Company I j ,/

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Ig T Madison Avenue at Punch Bowl Road Momstown, New Jersey 07960 (201)455-8200 May 23, 1979 The Honorable Mary Lou Smith Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08731 De.ar Mayor Smith:

Enclosed herewith is one copy of Technical Specification Change Request No. 72, Addendum 1, for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the U. S. Nuclear Regulatory Commission on May 23, 1979.

Very truly yours,

'

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' , hh),'lj, J J! -l[?] V Ivan R. Finf ock, dr.

Vice President la 2047 195 Jerse, Centra Power & Lignt Company is a Member of the Genera' Publ.: Uti:.tiet. System

JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATIO3 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Applicant hereby requests the Commission to change Appendix A to the License as follows:

1. Sections to be changed:

2.3; Table 3.1.1

2. Extent of changes:

Addition of new safety system setting and revision of LCO Table 3.1.1

3. Changes requested:

Replace page 2.3-3 with attached page 2.3-3 Replace page 3.1-8 with tne attached page 3.1-8.

4. Discussion:

This Technical Specification Change adds a new safety systen setting for the isolation condensers. On reactor low-low water level the isolation condensers will be initiated within 3 seconds.

Table 3.1.1 has been changed to reflect the new safety systen setting.

204~/ ?96

,' . FUNCTION LIMITING SAFETY SYSTEM SETTINGS 2:825 psig

7) Low Pressure Main Steam Line, MSIV Closure
8) Main Steam Line Isolation Valve 510% Valve Closure from full Closure, Scram open
9) Reactor Low Water Level, Scram 2:11',5" above the top of the active fuel as indicated under normal operating condition
10) Reactor Low-Low Water Level, 2: 7',2" above the rop of the Main ~ Steam Line Isolation Valve active fuel as indicated under Closure. normal operating conditions.
11) Reactor Low-Low Water Level, E 7'2" above the top of the Core Spray Initiation active fuel.
12) Reactor Low-Low Water Level, 2: 7'2" above the top of the Isolation Condenser Initiation active fuel with time delay 1 3 seconds.
13) Turbine Trip Scram 10 percent turbine stop valve (s) closure from full open.
14) Generator Load Rejection Scram Initiate upon loss of oil pressure from turbine acceleration relay.

BASES: Safety limits have been established in Specifications 2.1 and 2.2 to protect the integr3 *y of the fuel cladding and reactor coolant system barriers. Av.omatic protective devices have been provided in the plant design to take corrective action to prevent the safety limits from being exceeded in normal operation or operational transients caused by reasonable expected single operator error or equipment malfunction. This Specification establishes the trip settings for these automatic protection devices.

The Average Power Range Monitor APRM( } , trip setting has been established to assure never reaching the fuel cladding integrity safety limit. The APRM system responds to changes in neutron flux.

However, near rated thermal power the APRM is calibrated, using a plant heat balance, so that the neutron flux that is sensed is read out as percent of rated thermal power. For slow maneuvers, those where core thermal power, surface heat flux, and the power transferred to the water follow the neureon flux, the APRM will read reactor thermal power. For fast transients . he neutron flux will lead the power transferred from the claddi to the water due to the effect of the fuel time constant-. Theref- when the neutron flux increases to t ae scrsm setting, the percent li... ease in heat flux and power transferred to the water will be less than the percent increase in neutron flux.

The APRM trip setting will be varied automatically5 with recirculation flow with the trip setting at rated flow 61.0 x 10 lb/hr or greater being 115.7% of rated neutron flux. Based on a co=plete 2047 197

L' V ,3.1-8 ', ,

TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS (CONTD)_ .,'

Hin. No. of Min. No. of Operable Reactor Modes Operable or Instrument in Which Function Operating Channels Per Must Be Operable (Tripped) Trip Operable Action Function Trip Setting Shutdown Refuel Startup Run Systems Trip Systems Required

1. Low-Low Reactor ** X X X X 2 2 and close isola-Water Level tion condenser vent valves, or
2. liigh Flow in 3 120% rated X X X X 2 2 placo in cold Main Stoam- shutdown condi-line A tion
3. liigh Flow in 3 120% rated .X X X X 2 2 Main Steam-line B
4. liigh Tempera- 3 Ambient at X X X X 2 2

,, ture in Main Power + 50 F c Steamline h Tunnel N

5. Low P roanuro ** X 2 2 e in Main Steam-oc line .
6. liigh Radiation 3 10X Normal X X X X 2 2 in Hain Steam Background Tunnel C. Isolation Condenser
1. liigh Reactor ** X X X X 2 2 Place plant in Pressure cold shutdown onndttlen
2. Tow-Low Ruoctor ** X X X X 2 2 Water .

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