ML20027D352
| ML20027D352 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek (DPR-16-A-064, DPR-16-A-64) |
| Issue date: | 10/28/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027D348 | List: |
| References | |
| NUDOCS 8211040187 | |
| Download: ML20027D352 (8) | |
Text
.
e ncy o,
UNITED STATES
{. y,sc ' )
l' NUCLEAR REGULATORY COMMISSION
.j.. /,y WASHINGTON. D. C. 20555
)
5'rt h/p#
9, 5
4 GPU NUCLEAR CORPORATION
~
AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219
~
0YSTER CREEK NUCLEAR GENERATING STATION
~~"
AMENDMENT TO AMENDED PROVISIONAL OPERATING LICENSE Amendment No. 64 License No. DPR-16 l'. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated May 22, 1980, 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 I
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities l
will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the I
common defense and security or to the health and safety of the public; and l
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.
l 8211 OSO PDR t
a
. 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 /mendment No. 64 are
~""'
hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance s
with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGULdTORYCOMMISSION Dennis M. Crutc 1 eld, ie Operating Reactors Br ch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 28, 1982 4
l
ATTACHMENT TO LICENSE AMENDMENT N0. 64 PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages contain the captioned amend-ment number and vertical lines indicating the area of change.
Remove Pages Insert Pages s
i i
1.0-1 1.0-1 1.0-1a*
3.0-1 3.1-1 3.1-1
- This page is included for pagination purposes only.
TABLE OF CONTENTS Secticn 1 Cef-?aitians 1.1 Operable 1.0-1 1.2 Operating 1.0-1 1.3 Pcwer Operation 1.0-1 1.4 Startup Mode 1.5 Run Mode 4:0-1 1.0-1 1.6 Shutdewn Condition 1.0-1 1.7 Cold Shutdcwn 1.0-1 1.8 Place in Shutdcwn Condition 1.0-2 1.9 Place in Cold Shutdcwn Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 1.12 Refueling Outage 1.0-2 1.13 Primary Containment Integrity -
1.0-2 '
-~"
1.14 Secondary Containment Integrity 1.0-2 1.15 Deleted 1.0-3 1.16 Rated Flux 1.0-3 1.17 Reactor Thennal Power-to-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-4 1.19 Instrumentation Surveillance Definitiens 1.0-4 1.20 FDSAR 1.21 Core Alteration.
l.0-4 1.0-5 1.22 Minimum Critical Pcwer Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 1.24 Surveillance Requirements 1.0-5 1.25 Fire Suppression Water Systen 1.0-5 Section 2 Safety Limits and Limitifig Safety Systam Settings 2.1 Safety Limit - Fuel Cladding Integrity 2.1-1 2.2 Safety Limi - Reactor Ccolant System Pressure 2.2-1 2.3 Limiting Safety System Seetings 2.2-3 Secticn 3 Limiting Conditiens for Operaticn i
~
3.0 Limiting Conditions for Operation (General) 3.0-1 1
3.1 Protective Instrumentation 3.1-1 3.2 Reactivity Control 3.2-1 3.3 Reactor Ccolant 3.3-1 3.?
Emergency Cooling
.3.4-1 3.5 Containment 3.5-1 3.5 Radioactive Effluents 3.6-1 3.7 Auxiliary Electtical Pcwer 3.7-1 3.3 Isolaticn Condenser 3.5-1 3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 3.12 Fire Protecticn 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1
- cendment No. X, J,,2(
64 f
j n--,
2 1.0-1 SECTION I DEFINITIONS The following frequently used terms are defined to aid in the uniform interpretation of the specifications.
1.1 OPEPABLE-OPERABILITY A system, subsystem, train, cm:ponent, or device shall be OPERABLE or have OPEPABILITY when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendent ;---
instrumentation, c~ ntrols, normal and eniergency electrical power sources, o
cooling of seal water, lubrication or other auxiliary equipment that ard required for the system, subsystem, train, component or device to perform its function (s) are also capable of performi1g their related support function (s).
1.2 OPFSATING Operating means that a system or ca ponent is performing its required function.
1.3 PCWER OPERATION Power operation is any operation when the reactor is in the startup mode or run mode except when primary containment integrity is not required. -
1.4 STARTUP MDDE The reactor is in the startup mode when the reactor mode switch is in the startup mode position.
In this mode, the reactor protection system scram trips initiated by condenser low vacuum and main steam line isolation valve cicsure are bypassed when reactor pressure is less than 600 psig; the low pressure main steamline isolaticn valve closure is bypassed; the IPM trips for red block and scram are cperable; and the SPM trips for rod block are operable.
1.5 RUN MODE
~
The reactor is in the run mode when the reactor mode switch is in the run mode position. In this mode, the reactor protection system is energizedwith APPM protection and the control rod withdrawal interlocks are in service.,
1.6 S-!!?IDOW CC;DITIOi The reactor is in a shutdown conditicn when the reactor mode switch is
,in the shutdown mode position a,d there is fuel in the reactor vessel.
In this condition, the reactor is subcritical, a centrol rod block is initiated, all cperable control rods are fully inserted, and specification 3.2-A is met.
1.7 COLD S*r!LTJDWN The reactor is at cold shutdown when the mode switch is in the shutdown Amendment No. I f(, 64
i 1.0-1s i
mode position,there is fuel in the reactor vessel, all operable control. rods are fully inserted, and the reactor coolant system maintained at less than 212 F and vented.
i s
f 4
l 4
l i
i l
l Amendment No. 44, 64 1
i t
--ywv--m-v,,---e-w; - m __..
-v---,,e,-w-g.~~-
p
~ ~ ~. - - -, - -~.-~~,---
.e---
,o-
- - - = <
1 SECTION 3 3.0-1 LIMITIMG CONDITICGS FCR CPERATICN 3.O LIMITING CO:IITICNS FCR CPERATICN (GD;EML)
Acclic:bility: Applies to all Limiting Conditions for Operation.
Objective: To preserve the single failure criterion for safety systems.
Specifications:
A.
In the ever$t Limiting Conditions for Operation (IECs) and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in COLD SiithTG;N within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed tnat permit operation under the permissible action statements for the specified time interval as measured from initial discovery or until the reactor is placed in a condition in which tne scecificaticn is not
~J ~ -
applicable.
Exceptions to the recuirements shall be stated in the individual specifications.
B.
When system, subsystem, train, component or device is determined to be inoperable solely because its emergency pcwer source is inoperable, or solely because its normal power source is inoperable, it may be considered CPEFABLE for the purpose of satisfying tne requirements of applicable LCOs., provided (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), sub-system (s), train (s), component (s) and deyice(s) are OPERAELE, or,likewise satisfy the require-ments of tnis specification. Unless both conditions (1) and (2) are satisfied, the unit shall b placed in CCLD StiLYDCW.4 within the follcwing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> er witnin the time specified in tne applicable specificaticn.
Tnis specification is not applicable in CCLD Sii"IDC..:4 cr tne Fi.FCEL MODE.
Eases: Specifica:icn 3.0.A delineates tne acticn to be taken for circumstances directly prcvided for in the systems LCOs and wncse occurrence would violate nc:
tne intent cf tne specification.
Specification 3.0.3 delineates what additional conditions must be satisfied to permit cperation to centinue, consistent with the specificaticns for power sources, wnen a ncrmal or emergency pcwer source is not cperable.
It allcys cgr:ticn to be gcVerned by tne ti: e limits of the specificctions associated witn tne LCCs for tne normal or emergency power source, not tne individual crecificaticns fcr each system, sucsystem, train, component er device that is deurmined to be incperable solely because of tne inoperability of its normal or e ergqncy pcuer scurce.
In additicn, it specifically prchicits c eration wnen ene division is incperable because its normal or emergency pcwer source is inoperable and a safety subsystem, train, ccmpenent, or device in anotner division is incporable fcr another reason.
Amendment No. 64
f 3.1-1 3.1 FROTECTIVE INSTRUMENTAT7.ON -
Apolicability:
Applies to the operating status of plant instruhentation which perfor=s a protective function.
Obiective:
To assure the operability of protective instrumentation.
Soccifientions:
A.
The following operating requirc=cnts for plant protective instrumentation are given in Table 3.1.1:
~
1, ' The reactor rode in which a specified function gust be s
operable including allovable bypass conditions.
2.
The minimum number of operable instrunent channels per operable trip syste=.
3.
The trip settings which initiate autoratic. protective
- action, 4
The action required when the li=iting conditions for
' operation are not satisfied.
3, 1
Failure of fcur cha=bers assigned' to any one A?RM shall-
=ake the APRII inoperable.
2 Failure of two chambers fro = one :: dial core location in any one A?pJ! shall =ake that A??Of incperable.
C.
1 Any two (2) L?RM ass 2=blics which are input to the AFKM syste= and are separated in distance by less than three (3) ti=cs the control rod pitch cay not ecntain a conbi-ndtion of nere than three (3) inope'rable detectors. (i.e.,
A?nM channel f ailed or bypassed, er L?R: datectors failed or bypassed) out of the four (4) detectors located in either the A and B, or the C z:d D levels.
2.
A Travelling In-Core ? robe (TI?) cha=ber =sy be used as an A?FM input to neet the criteria of 3.1.3 and 3.1.C.1, provided the T ? is positiened in clcse proxi=i*y to one of the failed LPRM's.
If the criteria of 3.1.3.2 or 3.1.C.1 cannot be me; power operation may continue at up to rated power level provided a control rod withdrawal block is cperating or at power levels less than 61% of rated power until the TIP ccn be connected, positioned and satisfactorily tested, as long as Specification 3.1.3.1 and Table 3.1.1 are satisfied.
hendrent No. 64
.