ML19289E862
| ML19289E862 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/23/1979 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905290194 | |
| Download: ML19289E862 (1) | |
Text
.,
.TQ
^'T Jersey Central Powar & Light Company i
d*_<
[f' [
h JE r
j Madison Avenue at Punch Bowl Road Morristown. New Jersey 07960 (201)455-8200 May 23, 1979 Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 72, Addendum 1 Technical Specification Change Request No. 72 was submitted by letter dated May 19, 1979.
In subsequent discussions with your staff, it was requested that we add an additional limiting safety system setting under section 2.3 of the Technical Specifications.
The attached Technical Specification Change Request No. 72, Addendum 1, presents the requested change for your approval.
Isolation Condenser initiation on a reactor low-low water level signal has been added to section 2.3 as a Limiting Safety System Setting, and Table 3.1.1 of section 3.1 has been revised to reflect this change.
This Technical Specification Change Addendum has been reviewed and approved by the Station Superintendent, the Plant Operations Review Committee, and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.
The required fee for the review of Technical Specification Change Request No. /2 was submitted to your office by letter dated May 21, 1979.
This submittal is an addition to Change Request No. 72; therefore, no additional fee is required.
Very truly yours,
!]
[
Id/lf A11 A(2 ]
Ivan R. Finf ock,'Jr.
Vice President la 2047 543 7905z90l97 4 Jersey Central Power & Light Company is a Member of the General Public Utilities System
Jersey Central Power & Ught Company h
"
- ha.mff y Madison Avenue at Punch Bowl Road T
Morn _stown, New Jersey 07960 (201)455-8200 May 23, 1979 Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 72, Addendum 1 Technical Specification Change Request No. 72 was submitted by letter dated May 19, 1979.
In subsequent discussions with your staff, it was requested that we add an additional limiting safety system setting under section 2.3 of the Technical Specifications.
The attached Technical Specification Change Request No. 72, Addendum 1, presents the requested change for your approval.
Isolation Condenser initiation on a reactor low-low water level signal has been added to section 2.3 as a Limiting Safety System Setting, and Table 3.1.1 of section 3.1 has been revised to reflect this change.
This Technical Specification Change Addendum has been reviewed and approved by the Station Superintendent, the Plant Operations Review Committee, and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.
The required fee for the review of Technical Specification Change Request No. 72 was submitted to your office by letter dated May 21, 1979.
This submittal $s an addition to Change Request No. 72; therefore, no additional fee is required.
Very truly yours, th.!
,, # P -
Ivan R. Fi frock, Jr.
Vice Presi ent la 2047 544 Jersey Centraf Power & Light Company is a Member of the General Pubhc Utat:es System
JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLIAR 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 j
/
BY /
lN ff, EN $
v' VICE PRES ENT
/
STATE OF NEW JERSEY )
)
COUNTY OF MORRIS
)
Sworn and subscribed to before me this JJs2 day of W ig
, 1979.
(
<ib,/,-
r
,i t
Notary Public FM'/L. 3 A. KC3 NOTAR'l FSUC CF : E". ERSEY
},;y C=misin Exp cs ic ;.16,1973 204/
$45 kW 79op9od8
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISCION IN THE MATTER OF
)
)
DOCKET NO. 50-219 JERSEY CENTEAL 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,n the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Mary Lou Smith Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08731 JERSEY CENTRAL POWER & LIGHT COMP'ANY hI1f[ f f' ks BY VICE ESIDENT DATED:
May 23, 1979 2047 546 rggG5290173
Jersey Central Power & Light Company av ff y Madison Avenue at Punch Bowl Road Morristown, 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
Dear 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, 9
'o 9
hlaj),' }l/, MR )(7,' v'
~, lvan R. Finf ock, r.
Vice President la 2047 547 Jersey Central Power & Light Company is a Member of the Genera! Pubhc Ut.hties System
JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION 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 paga 3.1-8 with the attached page 3.1-8.
4.
Discussion:
This Technical Specification Change adds a new safety system 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 system setting.
k L
.)
FUNCTION LIMITING SAFETY SYSTEM SETTINGS
- 7) Low Pressure Main Steam Line, 2:825 psig MSIV Closure
- 8) Main Steam Line Isolation Velve
$ 10% Valve Closu.
from full Closure, Scram open 9)
Reactor Low Water Level, Scram Ell',5" above the top of the active fuel as indicated under normal operating conditions 10)
Reactor Low-Low Water Level, 2: 7',2" above the top 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 Sprey Initiation active fuel.
12)
Reactor Low-Low Water Level, 2: 7'2" above the top of the Isole ion Condenser Initiation active fuel with time delay i 3 seconds.
- 13) Turbine Tv.s 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 integrity of the fuel cladding and reactor coolant system barriers. Automatic 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 b 7 reasonable expected single operator error or equipment malfuncti na.
This Specification establishrs the trip settings for these automatic protection devices.
The Average Power R inge 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 neutron flux, the APRM will read reactor thermal power.
For fast transients, the neutron flux will lead the power transferred from the cladding to the water due to the effect of the fuel time constant.
Therefore, when the neutron flux increases to the scram setting, the percent increase 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 automatically with recirculation 5 lb/hr or flow with the trip setting at rated flow 61.0 x 10 greater being 115.7% of rated neutron flux.
Based on a complete 2047
$49
3.1-8 TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIRF} TENTS (CONTD)
Min. No. of Min ho. of Operable Reactor Modes Operable or Instrument in Which Function Operating Channels Per Must Be Operable (Tripped) Trip Operable Action Function Trip Setting Shutdowt Refuel Startup Run Systems Trip Systems Required
- B.
Reactor Isolation Close main steam isolation valves
- 1. Low-Low Reactor X
X X
X 2
2 and close isola-Water Level tion condenser vent valves, or
- 2. liigh Flow in 120% rated X
X X
X 2
2 placo in cold 3
Main Stonm-shutdown condi-line A tion
- 3. liigh Flow in 3 120% rated
.X X
X X
2 2
Main Steam-line B
- 4. Iligh Tempera-3 Ambient at X
X X
X 2
2 0
ture in Main Power + 50 F Steamline g.
c;,
Tunnel s
N 5. T.ow P ronnuro X
2 2
in Main Steam-
{
line O
- 6. High Radiation 3 10X Normal X
X X
X 2
2 in Main Steam
Background
Tunnel C.
Isolation Condenser 1.
liigh Reactor X
X X
X 2
2 Place plant in Pressure cold shutdown condition 2.
Lew-Low Reactor X
X X
X 2
2 Water
)
)
)
-