ML20086R042
| ML20086R042 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/13/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co |
| Shared Package | |
| ML20086R047 | List: |
| References | |
| NPF-73-A-041 NUDOCS 9112310128 | |
| Download: ML20086R042 (5) | |
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NUCLE AR REGULATORY COMMKSION 5
t WASHINGTON, D C. 20566
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DtIQtIESNE LIGHT COMPANY OH10EDlSONCOMPAfd THE CLEVELAND ELECTRIC ILLllMll4ATING COPPANY THE TOLEDO E0lS0tl COMPAliY DOCKETNO.!g,412 EE AVER VALLEY POWER STATION, UtilT ?
Al'Ektt'ENT TO FACltlTY OPERAT1tiG LICENSE Amendment flo.41 License 110. I;P F-73 1.
The I:uclear Regulatory Concission (the Concission) has found that:
A.
The application for amendnent by Duquesne Light Corpany, et al.
(the licensee) dated April 1?,1991, con: plies with the standards and requiren,ents of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter 1; R.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Concission; C.
There is reasonable assurance (i) that the activities authorized by this an.endrzent can be conducted without endangering the health and sefety of the public, at:d (ii) that such ee'ivities will t e c tr: duct eci ir, cotpliar.t e w'.th it.e :crJ..it sion's r quiet ions; D.
The issuance of this amendment will not be inimical to the conman defense and security or to the health and safety of the public; and E.
The issuance of this aniendn+ent is in accordance with 10 CFR Part 51 of the Consission's regulations and all appiicabic requirements have been satisfied.
9112310128 911213 PDR ADOCK 05000412 P
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Accordingly, the license is an, ended by changes to the Technical Specifications as indicated in the attachment to this Hcense arnendment, and paragraph 2.C.(2) of f acility Operating License No. Npf-73 is hereby amended to read as follows:
(2)
Technical Sp,ec,ifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 41 and the Environrnental protection plan cont 6tred in Appendix B both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environnental protection plan.
3.
i is license aniendnient is effective as of the date of its issuance, to be i.apier.ented within 60 days of issuance.
FOR THE NUCLEAR RCGULAT0p' COPJ41SS10N M
h John N Stolz, Director WojctDirectorate1-4
( M ision of Reactor projects - 1/11 Office of Nuclear Reactor Regulation Attachtnent:
Changes to the Technical Specifications Date of 1ssuance: December 13, 1991 4
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ATTACH! DENT TO LICENSE A!4ENOMENT NO. 41 FAClQT,Y,0P_ERATING_LICEf4SE_NO.NPF-73 DOCKET NO. _50 412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.
The revised pages are identified by amendment nunber and contain vertical lines indicating the areas of change.
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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 shall be OPERABLE.The accident monitoring instrumentation channels shown in lable 3.3.11 APPLICABILITY:
MODES 1, 2 and 3.
ACTION With the number of OPERABLE accident monitorin instrumentation chann a.
less than the Total Number of Channels shown iTable 3.3.11 either restoretheinoperablechannel(s)toOPERABLEstatuswithinYdaysorbe in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except for the PORV(s) which may be isolated in accordance with Specification 3.4.11.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.11 either restore the inoperable channel orbeinatleastHOTSHUTDOWNwithin(s)toOPERABLEstatuswithin48 hours the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Wi'h the number of OPERABLE Reactor Coolant System Subcooling Ma c.
i Monitor instrumentation channels less than the Minimum Channels O EpABLE requirements of Table 3.3.11, either restore the inoperable channel (s) to
-OPERABLE status within 7 days or be in a least HOT SHUTDOWN within the next 12-hoors.
l d.
The pruvisions of Specification 3.0.4 are not applicable.
SURVEILLANCE n10UIREMENTS 4.3.3.8 Each accident' monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CAltBRATION operations at the frequencies shown in Table 4.3-7.
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BEAVER YALLEY - UNIT 2 3/4 3-57 Amendment No.--2&- 41
TA,BLE 3.3-11 ACCIDENT MONITORING INSTRUMENTATION HINIMUM TOTAL NO.
CHANNELS IN51RUMENT OF CHANNELS OPERABLE ACTION 1.
Pressurizer Water Level 3
2 a, b 2.
Auxiliary Feed.>ater flow Rate 2 per steam 1 per steam a, b generator generator 3.
Reacto* Coolant System Subcooling Margin Monitor 2
1 c
4.
PORY Limit Switch Position Indicator 1/ valve 0/ valve a, b 5.
PORV Block Valve Limit Switch Position Indicator 1/ valve 0/ valve a, b 6.
Safety Valve Position Indicator 1/ valve 0/ valve a, b 7.
Safety Valve Temperature Detector 1/ valve 0/ valve a, b 8.
Containment Sump Wide Range Water Level 2
1 a, b 9.
Containment Wide-Range Pressure 2
1 a, b 10.
Reactor Vessel Level Indication System 2
1 a, b 11.
Core Exit Thermocouples 4/ core 2/ core a, b quadrant quadrant BEAVER VALLEY - UNIT 2 3/4 3-58
/cendment No. 41 1
1
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