ML20216H498
| ML20216H498 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/24/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216H503 | List: |
| References | |
| NUDOCS 9910010403 | |
| Download: ML20216H498 (5) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
%,*****/g WASHINGTON. D.C. 20666-0001 g
GPU NUCLEAR. INC.
6.tiQ JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMEN' TO FACILITY OPERATING LICENSji Amendment No. 209 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 December 23,1998, 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 conducted without endangering the health and safety of the 4
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 common defense and security or to the health and safety of the public; and i
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.
9910010403 990924 PDR ADOCK 05000219 P
2-2.
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 l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.209are hereby incorporated in the license. GPU Nuclear, Inc. shall operate the facility in accordance with the Technical 4
Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 30 days of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Chief, Section 1 Project Directorate i Division of Licensing Project Managment Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 24, 1999 l
ATTACHMENT TO LICENSE AMENDMENT NO. 209
. FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of ther Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginallines indicating tne areas of change.
Remove Insert 3.8-2 3.8-2 4.8-1 4.8-1 i
l
1 0*
Each csndenser containing a minimum total water volume of 22,730 gallons provides 11,060 gal above the condensing tubes. Based on scram from a reactor power level of 1950 MWt (the desik 1
power level for the isolation condensers) the condenser system can accommodate the reactor d heat (2,3)(corrected for U-239 and NP-239) for I hour and 40 minutes withou One condenser with a minimum water volume of 22,730 gallons can accommodate the reactor heat for 45 minutes after scram from 1950 MWt before makeup water is required. In order to accommodate a scram from 1950 MWt and cooldown, a total of 107,500 gallons ofmakeup water would be required either from the condensate storage tank or from the fire protection system. Since the rated reactor power is 1930 M'Vt, the above calculations represent conservative estimates of tim isolation condenser system cepability.
The vent lines from each of the isolation condenser loops to the main steam lines downstream of the main steam lines isolation valven.n provided with isolation valves which close automatically on isolation condenser actuation or on signals which close the main steam isolation valves. High temperature sensors in the isolation condenser and pipe areas cause alarm in the control room s alert the operator of a piping leak in these areas.
Specification 3.8.E allows reduction in redundancy ofisolation capability for isolation condenser inlet (steam side) isolation valves. Reasonable assurance ofisolation capability is provided by testing the operability of the redundant valve. Specification 3.8.F allows short term inoperability of the AC motor-operated isolation condenser outlet (condensate retum) valve. It is not necessary to test the redundant I
i DC motor-operated valve as this valve is normally in the closed position. These specifications per troubleshooting and repair as well as routine maintenance, such as valve stem packing addition or replacement, to be performed during reactor operation without reducing the redundancy of the isolation condenser heat sink function. The out of service time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with that permitted for primary containment isolation valves.(5)
- Either of the two isolation condensers can accomplish the purpose of the system. If one condenser is found to be inoperable, there is no immediate threat to the heat removal capability for the reactor and
)
reactor operation may continue while repairs are being made. Therefore, the time out ofservice for one of the condensers is based on considerations for a one out of two system.(4) The test interval for operability of the valves required to place the isolation condenser in operation is once/3 months
- (Specification 4.8). The allotted out of service time for an isolation condenser is conservatively set at i
seven days. However, ifat the time the failure is discovered and the repair time is longer than 7 days, the reactor will be placed in the cold shutdown condition. If the repair time is not more than 7 days the reactor may continue in operation, but as an added factor of conservatism, the motor operated isolation condenser and condensate makeup valves on the operable isolation condenser are tested daily.
Expiration of the 7 day period or inability to meet the other specifications requires that the reactor be placed in the cold shutdown condition which is normally expected to take no more than 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. The I
out of service allowance when the system is required is limited to the run mode in order to require system availability, including redundancy, at startup.
OYSTER CREEK 3.8-2 Change No. 7 Amendment No.:#, )%' 203,209
r 4.g ISOLATION CONDENSER Anoticabiliev:
Applies to periodic testing requirements for the isolation condenser system.
Qitigatigg:
To verify the operability of the isolation condenser system.
Sancification:
A.
Surveillance of each isolation condenser loop shall be as follows:
llEm faalsagr
- 1. Operabilityofmotor-Once/3 months l
operatedisolation valves and condensate makeup valves.
- 2. Automaticactuationand functionaltest.
Each refueling outage (intervalnot to exceed 20 months)orfollowing mqjor repair.
- 3. Shellside watervolume check Once/ day
- 4. Isolation valve (ream side) '
- a. Visualinspection -
- b. Extemalleakage check Each refbeting outage Each primarysystem Laak test
- c. Areaumperaturecheck once/shiA Baala: Motor operated valves on the isolation condenser steam and condensase Unos and on the condensate makeup line that are normally on standby Aould be exercised periodically to make sure that they are free to ymrate. The valves will be stroked fbil length every time they are
. sessed to verify proper fbnctionalperformance. This frequency of testing is consistent with instrumentation tests discussed in Specification 4.1. Testing of these components per ASME section XI
. ence every 3 months provides assurance ~ofavailability ofthe system. Also, at this.%p..cy oftesting, waarout should not be a problem throughout the life of the plant.
The automatic actuation and ihnetional test will demonstrate the automatic opening ofthe condensme return line valves and the automatic closing of the isolation valves on the vent lines to the main steam lines. Automatic closure ofthe isolation condenser steam and condensets lines on actuation of the condenser pipe break detectors
' will also be verifad by the test. It is during a mqjor analatenance or
_ repair that a system's design intent may be violated accidentally.
This makes the functional test necessary aAer every mq)or repair operation.
By virtue of normal plant operation the operators daily observe the water level in the isolation condensers. In addition, isolation condenser shell side water level sensors provide control room annunciation r#condenaer high or low water level.
4.g.1 Amendment No. 209
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