ML20214A022
| ML20214A022 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/07/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214A026 | List: |
| References | |
| NUDOCS 8611190165 | |
| Download: ML20214A022 (5) | |
Text
.-.
/
'o UNITED STATES 8"
~k NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20666 t.,..... o*
GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET N0. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No,113 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated March 11, 1986, as supplemented by letter dated September 5, 1986, complies with the standards and reauirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 comon 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 Comission's regulations and all applicable requirements have been satisfied.
8611190165 861107 PDR ADOCK 05000219 P
. 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 Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 113, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1, D b
(/
k N. Donohew, Jr.,
o ect Manager PWR Project Directorate #1 iDivision of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 7, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 113 PROVISIONAL OPERATING LICENSE NO. DFR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3.2-1 3.2-1 3.2-2 3.2-2*
r
.i w ot at
- a wa p
. e 'Jl r T'-
tet -
- D e r,.
r-a -
Pagination change only
./
.... _ ~.. J.T....~.. T _Ti.: J.~..T.'C ~
- 3. 2 REACTIVITY CONTROL Applicability: Applies to core reactivity and the operating status of the reactivity control systems for the reactor.
Objective:
To assure reactivity control capability of the reactor.
Specification:
A.
Core Reactivity The core rr. activity shall be limited such that the core could be made subtritical at any time during the operating cycle, with the strongest operable control rod fully withdrawn and all other operable rods fully inserted.
B.
Control Rod System 1.
Tne control rod drive housing support shall be in place during power operation and when the reactor coolant system is pressurized above atmospheric pressure with fuel in the reactor vessel, unless all control rods are fully inserted and Specification 3.2. A is met.
2.
The Rod Worth Minimizer (RWM) shall be operable during each reactor startup until reactor power reaches 10% of rated power except as follows:
(a) Sheuld the RWM become inoperable after the first twelve rods have been withdrawn, the startup may continue provided that a second licensed operator verifies that the licensed operator at the reactor console is following the rod program.
(b) Should the RWM be inoperable before a startup (see NOTE l
below) is commenced or before the first. twelve rods are withdrawn, one startup during each calendar year may be performed without the RWM provided that the second licensed operator verifies that the licensed operator at the reactor console is following the rod program and provided that a reactor engineer from the Core Engineering Group also verifies that the rod program is being followed.
A startup without the RWM as described in this subsection shall be reported in a special report to the Nuclear Regulatory Commission (NRC) within 30 days of the startup stating the reason for the failure of the RWM, the action taken to repair it and 1
the schedule for completion of the repairs.
NOTE:
Durina Cycle 11 only, unlimited reactor startups are permitted without the RWM.
The Control Rod Pattern Templates must be used during Cycle 11 when the RWM is bypassed or inoperable until 50% control rod density (black and white pattern) is achieved or 10% power is reached whichever occurs first. All other provisions of Specification 3.2.B.2.b remain in effect.
OYSTER CREEK 3.2-1 Amendment No.: 75, 113
{
~-
Control rod withdrawal sequences shall be established with a banked position withdrawal sequence so that the rod drop accident design limit of 280 cal /gm is not exceeded.
For control rod withdrawal sequences not in strict compliance to BPWS, the maximum in sequence rod worth shall be 11.0% AK.
3.
The average of the scram insertion times of all operable control rods shall be no greater than:
Rod Length Insertion Time Inserted (Percent)
(Seconds) 5 0.375 20 0.900 50 2.00 90 5.00 The average of the scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array shall be no greater than:
Rod Length Insertion Time Inserted (Percent)
(Seconds)
, up
-+m-5 0.398 20 0.954 50 2.120 90 5.300 Any four rod group may contain a control rod which is valved out of service provided the above requirements and Specification 3.2.A are met. Time zero shall be taken as the de-energization of the pilot scram valve solenoids.
4.
Control rods which cannot be moved with control rod drive pressure shall be considered inoperable.
If a partially or fully withdrawn control rod drive cannot be moved with drive.or scram pressure the reactor shall be brought to a shutdown' condition within l
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless investigation demonstrates that the cause of the failure is not due to a failed control rod drive rechanism collet housing.
Inoperable control rods shall be valved out of service, in such positions that Specification 3.2.A is met.
In no case shall the number of rods valved out of service be greater than six during the power operation.
If this specification is not met, the reactor shall be placed in the shutdown condition.
5.
Control Rods shall not be withdrawn for approach to criticality
}
unless at least two source range channels have an observed count rate equal to or greater than 3 counts per second.
C.
Standby Liquid Contral System 1.
The standby liquid control system shall be operable at all times when the rea: tor is not shut down by the control rods such that Specificatio1 3.2.A is met and except as provided in Specificatio) 3.2.C.3.
OYSTER CREEK l
3.2-2 Amendment No.: 75,113
{
i