ML20154L315
| ML20154L315 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/14/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154L320 | List: |
| References | |
| NUDOCS 9810190229 | |
| Download: ML20154L315 (6) | |
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UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20555 4001 i
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I GPU NUCLEAR. INC.
bHD JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.199 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear, Inc. et al., (the licensee), dated August 21,1998, 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 co ' ducted without endangering the health and safety of the public, and (ii) that suc., 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 ragulations and all applicable requirements have been satisfied.
9810190229 981014
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. 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 Facility Operating License No. DPR-16 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.199
, are hereby incorporated in the license.
GPU Nuclear, Inc. shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION c' f0. u M94#&
Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 14, 1998
2 ATTACHMENT TO LICENSE AMENDMENT NO. 199 i
FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A, Technical Specifications, with the attached -
pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
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Remove Insert
-l 3.1 3.1-16
'3.4-3 3.4-3 3.4-4 3.4-4 l
I
TABLE 3.1.1 (CONT'D)
Action required when minimum conditions for operation are not satisfied. Also permissible to trip inoperable trip system. A channel may be placed in an inoperable status for up to six hours for required surveillance without placing the trip system in the tripped condition piovided at least one OPERABLE instrument channel in the same trip system is monitoring that peameter.
See Specification 2.3 for Limiting Safety System Settings.
Notes:
Permissible to bypass, with control rod block, for reactor protection system reset in REFUEL a.
MODE.
t b.
Permissible to bypass below 600 psig in REFUEL and STARTUP MODES.
One (1) APRM in each OPERABLE trip system may be bypassed or inoperable provided the c.
requirements of Specification 3.1.C and 3.10.C are satisfied. Two APRM's in the same quadrant shall not be concurrently bypassed except as noted below or permitted by note.
Any one APRM may be removed from service for up to six hours for test or calibration without insening trips in its trip system only if the remaining OPERABLE APRM's meet the requirements of Specificatica 3.1.B.1 and no control rods are moved outward during the calibration or test. During this short period, the requirements of Specifications 3.1.B.2,3.1.C and 3.10.C need not be met.
d.
The IRMs shall be inserted and OPERABLE until the APRMs are OPERABLE and reading at least 2/150 full scale.
Offgas system isolation trip set at <2,000 mrem /hr. Air ejector isolation valve closure time e.
delay shall not exceed 15 minutes.
f.
Unless SRM chambers are fully inserted.
g.
Not applicable when IRM on lowest range.
h.
With one or more instrument channel (s) inoperable in one ADS trip system, place the relay contact (s) for the inoperable initiation signal in the tripped coadition within 4 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3.
With one or more instrument channel (s) inoperable in both ADS trip systems, restore ADS initiation capability in at least one trip system within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or declare ADS inoperable and take the action required by Specification 3.4.B.3.
Individual electromatic relief valve control switches shall not be placed in the "Off" position for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (total time for all control switches) in any 30-day period and only one relief valve control switch may be placed in the "Off" position at a time.
OYSTER CREEK 3.1-16 Amendment No.: 75, 08,l l0,l'!, P,190, !", ' 95199
9.
If Specifications 3.4.A.7 and 3.4.A.8 cannot be met, the requirements of Specification 3.4. A.6 will bt. met and work w ill be initiated to meet minimum operability requirementsof 3 A.A.7 and 3.4.A.8.
10.
The core spray system is not required to be operable when the following conditions are met:
The reactor mode switch is lockec' ~ :Se " refuel"or " shutdown" position.
a.
b.
(1)
There is an operable flow path capable of taking suction from the condensate storage tank and transferringwater to the reactor
)
vessel.and 4
(2)
The fire protection system is operable.
c.
The reactor coolant system is maintained at less than 212 F and vented (except during reactor vessel pressure testing).
d.
At least one core spray pump, and system components necessary to deliver rated core spray flow to the reactor vessel, must remain operable to the extent that the pump and any necessary valves can be started or operated from the control room or from local control stations,and the torus is mechanicallyintact.
e.
(1)
No work shall be performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4'8" above the top of the active fuel and :he condensate storage tank level is greater than thirty (30) feet (360,000 gallons).
At least two redundant systems including core spray pumps and system components must remain operable as defined in d. above OR (2)
The reactor vesse! head, fuel pool gate, and separator-dryerpool gates are removed and the water level is above elevation 117 feet.
NOTF: When filling the reactor cavity from the condensate storage tank end draining the :cactor cavity to the condensate storage tank, the 30 not limit does not apply provided there is sufficient amount of svater to complete the dooding operation.
B.
Automatic Depressurization Syste'm 1.
Five electromatic relicfvalves, which provide the automatic depressurization and pressure relief functions, shall be operable when the reactor water temperature is greaterthan 212*F and pressurized above 110 psig, except as specified in 3.4.B.2 and during Reactor Vessel Pressure Testing consistent with Specifications 1.39 and 3.3.A.(i).
OYSTER CREEK 3.4-3 Amendment No.: 75,120,l53 199
2.
If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.
3.
If Specifications 3.4.B.1 and 3.4.B.2 are not met; reactor pressure shall be reduced to 110 psig or less,within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
The time delay set point for initiation after coincidence of low-low-low reactor water level and high drywell pressure shall be set not to exceed two minutes.
C.
Containment Spray System and Emernency Service Water System 1.
The containment spray system and the emergency service water system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications 3.4.C.3,3.4.C.4,3.4.C.0 and 3.4.C.8.
2.
The absorption chamber water volume shall not be less than 82,000 ft' in order for the containment spray and emergency service water system to be considered operable.
3.
If one emergency service water system loop becomes inoperable,its associated containment spray system loop shall be considered inoperable. Ifone containment spray system loon and/or i's associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in operason for a period not to exceed 7 days provided the remaining containment spray system loop and its associated emergency service water system loop each have no inoperable components and are verified daily to be operable.
4.
If a pump in the containment spray system or en ergency service water system becomes inoperable,the reactor may remain in operation for a period not to exceed 15 days provided the other similar pump is verified daily to be operable. A maximum of two pumps may be inoperable provided the two pumps are not in the same loop. If more than twu pumps become inoperable,the limits of Specification 3.4.C.3 shall apply.
5.
During the period when one diesel ls inoperablc,the containment spray loop and emergency service water system loop connected to Ihe operable diesel shall have no inoperablecomponents.
6.
If primary containmentintegrityis ot required (see Specification 3.5.A),the s
containment spray system may be made inoperable.
i OYSTER CREEK 3.4-4 AmendmentNo.: 75,153,167,17^ 199