ML20033C766
| ML20033C766 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/25/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033C767 | List: |
| References | |
| NUDOCS 8112040128 | |
| Download: ML20033C766 (6) | |
Text
r.o rar UNITED STAfES
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JERSEY CENTRAL POWER & LIGHT COMPANY.
DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT T0' PROVISIONAL OPERATING LICENSE Amendment No. 57 License No..DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicatio'n for amendment by Jersey Central Power & Light Company (the licensee) dated November 24, 1981, as supported by letter dated November 23, 1981, 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
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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 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 Par,t 51 of the Commission,'s regulations and all applicable ; requirements have been satisfied.
8112040128 81112 '
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.
DPR-16 is hereby amended to read as follows:
L.B Technical Specifications The Technical Specifications contained in Append' ices A and B, as revised through Amendment No. 57, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the
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Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Techni' cal Speci fi cations Date of Issuance: November 25, 1981 k
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages a e identified by captioned amendment number and contain vertical lines indicating the area of change.
PAGES 3.13-1 3.13-2 3.13-3 I
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'3.13 ACCIDENT MONITORING INSTRUMENTATION Applicability:
A'pplies to the operating status of accident monitoring instrumentation.
Objective:
Tn assure operability of accident monitoring instrumentation.
Speci fication:
A.
Relief Valve Position Indicators l
1.
The accident monitoring instrumentation channels shown in Table 3.13.1 shall be operable when the mode switch is in the Startup or Run positions.
2.
With the number of operable accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.13.1, either restore the inoperable channels to operable status within 7 days, or place the reactor in the shutdown position within 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 acciderit monitoring instrumentation channels. less than the Minimum Channels Operable requirements of Table 3.13.1, either restore the inoperable. channel (s) to the 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 cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Safety Valve Position Indicators 1.
During power operation, both primary
- and backup **. safety valve monitoring instruments are required to be operable except as provided in 3.13.B.2 and 3.13.B.3.
2.
If either the primary
- or backup ** accident monitoring instruments un a valve become inoperable, the primary
- accident moaitoring instrument on an adjacent valve must be operable, and its set point appropriately reduced.
3.
If both the primary
- and backup **-accident monitoring instruments on a valve become.
inoperable and the printary* accident monitoring instrument on an adjacent valve is operable, either restore the inoperable channel (s) to an operable status within 7 days, or place the Reactor in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
If the requirements of Section 3.13.B.2 or 3.13. B.3 cannot be met within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, place the
. reactor in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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C.
In the event that any of these monitoring channels become inoperable, tFev shall.be made operable prior to startup following tb
- 'old shutdown.
- Acoustic Monitor
- Thermocouple 1
AmendmentNo.p,57
T BASES 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 threatsning event.
As the safety valves present distinctly different 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 reseating 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 reseats. Therefore, the actions taken' for inoperable acoustic monitors on safety valves are significantly less stringent than that' i
taken for those monitors associated with relief valves.
Should an acoustic monitor'on a safety valve become inoperable, setpoints on adjacent monitors will be reduced to assure alarm actuation should the safety valve lift, since it is of no importance to the operator as to which valves lift but only that one has lifted. Analyses, using very conservative blowdoso forces and a,ttenuation factors, show that reducing the alarm setpoint on adjacent monitors to <l.4g will assure alarm actuation should the adjacent i
safety valve lifc. Minimum blowdown force considered was 30g with~a maximum attenuation of 27dB.
In actuality, a safety val.ve lift would result in considerably larger blowdown force. The maximum attenuation of 27 'dB was
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determined based on actual testing of a sidilar monitoring system installed in a similar configuration.
3.i3-2 AmendmentNo.h,57 a
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TABLE 3.13.1 ACCIDENT MONITORING INSTRUMENTATION TOTAL NO. OF MINIMUM CHANNELS INSTRUMENT CHANNELS OPERABLE I1.
Relief Valve Position Indicator 1/ valve 1/ valve (Primary Detector *)
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Relief Valve Position Indicator 1/ valve (Backup Indications **)
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- Ac'oustic Monitor
- Thermocouple 3.13-3 Amendment No. [ 57