ML20133Q058
| ML20133Q058 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/15/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133Q060 | List: |
| References | |
| NUDOCS 8511010349 | |
| Download: ML20133Q058 (5) | |
Text
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DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated July 12, 1985, complies with the standards and re of the Atomic Energy Act of 1954, as amended (the Act) quirements and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There 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; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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-66 is hereby amended to read as follows:
1 l
8511010349 851015 PDR ADOCK 05000334 l
P PDR l
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented within 30 days after issuance.
ULATORY COMMISSION FpTHENUC e
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Operating Reactors anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 15, 1985 l
l 1
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 2-8 3/4 2-8 3/4 2-9a B 3/4 2-5 B 3/4 2-5 4
POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F H LIMITING CONDITION FOR OPERATION N
3.2.3 F
shall be limited by the following relationship:
3H N
F 1.55[1+0.3(1-P)]
l 3
where P THERMAL POWER
=
RATED THERMAL POWER APPLICABILITY:
MODE 1 ACTION:
N With F exceeding its limit:
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within a.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to 5 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, N
b.
Demonstrate thru in-core mapping that F is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or Nduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and Identify and correct the cause of the out of limit condition prior c.
to increasing THERMAL POWER, subsequent POWER OPERATION may proceed N
provided that F is demonstrated through in-core mapping to be AH within its 1.imit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL power, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.
BEAVER VALLEY - UNIT 1 3/4 2-8 Amendment No. 97
l POWER DISTRIBUTION LIMITS BASES Fuel rod bowing reduces the value of the DNB ratio.
Credit is available to offset this reduction in the generic margin.
The generic design margins, totaling 9.1% DNBR, and completely offsets any rod bow penalties (< 3% for the worst case which occurs at a burnup of 33,000 MWD /MTU).
This margin includes the following:
1.
Design Limit DNBR of 1.30 vs.1.28 2.
Grid Spacing (K Themal Diffusi6n) of 0.046 vs. 0.059 3.
Coefficient of 0.038 vs. 0.C59 4.
DNBR Multiplier of 0.865 vs. 0.88 5.
Pitch reduction The radial peaking factor F,y (Z) is measured periodically to provide assur -
ance that the hot channel factor Fg (Z), remains within its limit. The F,y limit for Rated Thermal Power (F P) as provided in the Radial Peaking Factor Limit Report per specification 6.9.1.14 was detemined from expected power control maneuvers over the full range of burnup conditions in the core.
3/4.2.4 QUADRANT POWER TILT RADIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during startup testing and period-ically during power operation.
The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts.
The two-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod.
In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the maximum g
allowed power by 3 percent for each percent of tilt in excess of 1.0.
i BEAVER VALLEY - UNIT 1 B 3/4 2-5 Amendment No. 97
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