ML20096G679
| ML20096G679 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/12/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20096G682 | List: |
| References | |
| DPR-16-A-158 NUDOCS 9205260202 | |
| Download: ML20096G679 (6) | |
Text
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UNITED STATES -
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NUCLEAR REGULATORY. COMMISSION I
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E JCLEAR CORPORATION AtiQ JERSEY CENTRAL POWER & LIGHT COMPANY DQCKET NO. 50-219 OYSTER CREEK NVCLEAR GCNERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. DPR.
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
- The application for amendment by GPU Nuclear Corporation, et al.,
(the licensee)', dated February 15,_1990, as supplemented January 22,-1992, complies with the standards and requirements'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..
1There is; reasonable assurance _ (1).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 Comission's regulations; JD.-
The ' issuance of this amendment willsnot.be inimical to.the comon defense and security or to the itealth 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.--
'3 9205260202 920512
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' ADCCK 05000219.
.i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachtrent to this license amendment, and paragraph ?.C.(2) of facility Operating Liceno No. OPR-16 is hereby amended tc read as follows:
(2) In hpical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.158, are hereby incorporated in the license.
GPU Nrselear Corporation 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.
FOR THE NUCLEAR REGULATORY COMMIS$10N 9-John F. Stolz, ir or Proj<!ct Directorate I A Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to t
'echnical Specificat Date of Issuance: May 12, 1992 l
.+
ATTACHMENT TO LICENSE AMENDMENT NO.158.
FACltlTY OPLRATING LICENSE NO. DPR-li QQ{KET NO. 50-219 Replace the following pages of the Appendix A Technical 3pecifications with the enclosed sages as indicated. The revised pages are identified by amendment num)er and contain vertical lines indicating the areas of change.
Remove Jnsert 3.13-1 3.23-1 3.13-2 3.13-2 3.13-3 3.13-3 l
e 3.83 ACC2 DENT MON 2 TOR R ?NSTIwHENTAT20N Acelicability:
Applies to the operating status of accident monitoring instrumentation.
Obiective To assure operability of accident monitoring instrumentation.
SpecificatiED:
A.
Relief Valve Position Indicatolf 1.
The accident monitoring instrumentation channels shown in Table 3.13.1 shall be OPERABLE when Lhe mod 4 switch is in the startup or Run positions.
2.
With the nLmber of OPERABLE accident monitoring instrumentation channels less than the Total Namber of Channels shown in Table 3.13.1, either restore the inoperable shannels to OPERABLE status within 7 days, or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With the number of OPERAPLE accident monttcal.79 instrumentation channele less than this Minimum Channels operable requirements of Tarle 3.13.1, either restoiw the inoperable enar.nel(s) to the OPRAABLE status with4n 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Safety Valve Positien Indicatorg 1.
During POWXR OPERATION, both primary
- and bat,;p**
safety valve monitoring instruments are requi.v1 to be OPERABLE steept as provided in 3.13.B.2.
l 2.
If the primary
- accident monitoring instrument on a l
safety vsive becomes inoperable, the primary =
accident monitoring instrument on an adjacent valve, if OPERABLE, must have its set point appropriately reauced. When a reduced setpoint causes an alarm condition due to background noise, the setpoint may be returned to normal.
If the backup ** accident monitoring instrument on a safety valve becomes inope able, no action is requirede The provisions of Specification 3.0. A do not apply.
' Acoustic Monitor
- Thermocouple OYSTER CREEK 3.13-1 Amendment No.:
54, 57, 96, 123,158
~*
C.
In tho cv:nt thtt cny of th003 monitoring chtnn31s b come inoperable, they shall be made OPERABLE prior to startup following the next COLD SMUTDOWN.
\\
D.
gi_de Rance Torus Water Level Monitor 1.
Two wide range torus water level monitor channels shall be continuously indicated in the control room during POWER OPERATION.
With the namber of OPERABLE accident monitoring l
channels less than the total Ncabar of Channels shv.m in Table 3.13.1, restore the inoperable channel (s) to CPERABLE status within 7 days or place the reactor in the $#UTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With the number of CPARABLE accident monitoring l
instrumentation channels less than the Minimum Channels operable requirements of Table 3.13.1, restore the inoperable channel (s) to CPERABLE status within 48 hrurs or place the reactor in the SHUTDOWN CONDITION wiwhin the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Wide Ranom Drvwell Pressure Monitor 1.
Two Wide Range Drywell Pressure monitor channels shall be continuously indicated in the control room during POWER CPERATION.
l 2.
With the number of CPERABLE accident monitoring l
chatsnels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel (s)'to CPERABLE status within 7 days or place the reactor in the SHUTDOWN CONDITION within the next 24 hoitre.
3.
hith the number of OPERABLE accident monitoring l
instrumentation channels less than the Minimum channels operable requirements of 3.13.1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the reactor in the SHVfDOWN CONDITION within the ner. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e F.
Drywell H Monitor g
1.
Two drywell hydrogen monitor channels shall be capable of continuously indicating in the control room during POWER OPERATION.
l OYSTER C?.dEK' 3.13-2 Amendment No.:
54, 57, 94, 96, 123,158 I
il
2.
With th3 number cf OPERABLE ch:nn:1s 10:s than th3 l
tctc1 number of channelo chown in Tcblo 3.13.1, rOatcra th3 in perOb'c chtnn:1 to OPERABLE stCtu3 within 30 days or place the reactor in the SRUTDOWN CONDITION with the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With the number of OPERABLE channels less than the l
Minimum Channels operable requiremtnts of Table 3.13.1, restore at least one channel to OPERABLE l
status within 7 days or place the reactor in the SRUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l G.
Containment Hich-Rance Radiation Meniter 1.
Two in-containment high range radiation monitors shall be OPERABLE at all times except for COLD SHUTDOWN and other times when primary containment is not required.
2.
In case of failure of one or more monitors, appropriate actions shall be taken to restore its OPERABLE capability as soon as possible. Also, l
refer to Table 3.1.1 for any additional action which may be required.
3.
If the monitor or monitors are not restored to OPERABLE condition within 7 days after the failure, l
a special report shall be submitted to the NRC within 14 days following the event, outlining the cause of inoperability, actions taken and the planned schedule for restoring the equipment to OPERABLE status.
l Dh3LEt The purpose of the safety / relief valve accident monitoring instrumentation is to alert the operator to a stuck open safety / relief valve which could result in an inventory threatening event.
As the safety valves present distinctly dif Jrent concerns than those related to relief valves, the technical specifications are separated as to the actions taken upon inoperability. Clearly, the actuation of a safety valve will be immediately detectable by observed increase in drywell pressure.
Further confirmation can be gained by observing reactor pressure and water level. Operator action in response to these symptoms would be taken regardless of the acoustic monitoring system status.
Acoustic monitors act only to confirm the ressating of the safety valve.
In actuality, the operator actions in response to the lifting of a safety valve will not change whether or not the safety valve ressats. Therefore, the actions taken for inoperable acoustic monitors on safety valves are significantly lees stringent than that taken for those monitors associated with relief valves.
Should an acoustic monitor on a safety valve become inoperable, the setpoint on an adjacent monitor, if operable, will be reduced to assure alarm actuation should the safety valve lift. When a reduced setpoint results ir having the acoustic monitor on an adjacent valve in an alarm condition due to background noise, the actpoint may be returned to normal. This will ensure that the adjacent valve's acoustic monitor remains operable. Analyses, using very conservative blowdown OYSTER CREEK 3.13-3 Amendment No.: 54, 57, 94, 116,158 l
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