ML19250C187

Amend 20 to License DPR-66,providing for Changes in Nuclear Enthalpy Hot Channel Factor,Core Radial Peaking Factor & Rod Bow Penalty.Deletes Licensing Condition 2.C

ML19250C187
Person / Time
Site:	Beaver Valley
Issue date:	11/03/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19250C188	List: ML19250C187 ML19250C196
References
NUDOCS 7911210264
Download: ML19250C187 (11)

Text

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'o UNITED STATES g

E NUCLEAR REGULATORY COMMISSION g

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DUQUESNE LIGHT COMPANY OHI0 EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 20 License No. DPR-66 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated September 22, 1978, as supplemented by letter dated February 8, 1979 and portions of letters dated October 27, 1978 and December 14, 1978, 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 Commissior.;

C.

There is reasonable assurance (i) 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 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 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 20, are hereby incorporated in the license. The licensee shall operate the facility in 6ccordance with the Technical Spec ific ations.

3.

The license is also amended by deletion of the license condition 2.C on " Rod Bow Penalty on Total Peaking Factor."

4.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION (dW A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Attac hment:

Changes to the Technical Spec ific ations Date of Issuance:

November 3, 1979

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ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET N0. 50-334 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4 2-6a 3/4 2-8 B 3/4 2-4 B 3/4 2-5 g

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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b)

At least once per 31 EFPD, whichever occurs first.

P 2.

When the F is less than or equal to the F limit for the appropriate measured core plane, additional power C

distribution maps shall be taken and F compared to RTP F

and F at least once per 31 EFPD x

e.

The F limits for RATED THERMAL POWER within specific core planes shall be:

RTP 1.71 for all core planes containing bank "D" l.

F 1

x control rods, and 2.

For unrodded core planes:

F 1 1.68 up to 2.4 ft. elevation, xy 1.75 from 2.4 ft. elevation up to 7.8 ft. elevation, F

1 xy F

1 1.63 above 7.8 ft. elevation xy f.

The F limits of e, above, are not applicable in the fol-lowing core plane regions as measured in percent of core height from the bottom of the fuel-1.

Lower core region from 0 to 15%, inclusive.

2.

Upper core region from 85 to 100% inclusive.

3.

Grid plane regions at 17.8 + 2%, 32.1 + 2%,

46.4 + 2%, 60.6 + 2% and 74.9 + 2%, inclusive.

4.

Core plane regions within + 2% of core height (+ 2.88 inches) about the bank demand position of the bank "0" control rods.

Q (Z) shall be g.

With F exceeding F

, the effects of F "I

xy evaluated to determine if Fg (Z) is within its limit.

4.2.2.3 When F (Z) is measured pursuant to Specification 4.10.2.2, an q

overall measured F (Z) shall be obtained from a power distribution map g

and increased by 3% to account for manufacturing tolerances and'further increased by 5% to account for measurement uncertainty.

IlBEAVER VALLEY - UNIT 1 3/4 2-6a Amendment No. 2, 9, J7 20

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CO FIGURE 3.2-2 K(Z)- NORMALIZED F (Z) o AS A FUNCTION OF CORE HEIGHT

i POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F6g LIMITING CONDITION FOR J?ERATION N

3.2.3 F shall be limited by the following relationship:

aH H 1 1.5355 [1.0 + 0.2 (1-P)]

F where P = THERMAL POWER RATED THERMAL POWER APPLICABILITY: MODE 1 ACTION:

With F exceeding iM, limit:

AH a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 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 tt 1 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 />, b.

Demonstrate thru in-core mapping that F is within its limit H

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 reduce 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 c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; sitbsequent POWER OPERATION N

is demonstrated through in-core may proceed provided that FaH mapping to be within its limit 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 THERPAL POWER.

BEAVER VALLEY - UNIT 1 3/4 2-8 Amendment 70, 20 1

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INO!CATED axial FLUX DIFFERENCC Fipero B 3/4 21 TYPICAL INDICATED AXI AL FLUX DIFFEdENCE VERSUS THERM AL POWER AT 80L FIGURE B 3/4. 2-1 D FD NTN A

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p BEAVER VALLEY - UNIT 1 B 3/4 2-3 3 7o' 1t0

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS-F (Z) and F n

H The limits on heat flux and nuclear enthalpy hot channel factors ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the ECCS acceptance criteria limit of 2200*F.

Each of these hot channel factors are measurable but will nonnally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:

a.

Control rod in a single group move together with no individual rod insertion differing by more than + 12 steps from the group demand position.

b.

Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.

c.

The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.

d.

The axial power distribution, expressed in tenns of AXIAL FLUX DIFFERENCE is maintained within the limits.

The relaxation in F as a function of THERMAL POWER allows chEnges ig the radial power shaphHfor all pennissible rod insertion limits.

ab$ve,llbemaintainedwithinitslimitsprovidedconditionsathrud F

wi are maintained.

When an F measurement is taken, both experimental error and man-n ufacturing tolerance must be allowed for.

5% is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% is the appropriate allowance for manufacturing tolerance.

The specified limit of F"0 which means that nonnal, ful1 hower,ains an 8% allowance for uncertain cont three loop operation will result in FaH < l.55/1.08.

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} Ip j BEAVER VALLEY - UNIT 1 B 3/4 2-4 Amendment No. 70, J7, :

POWER DISTRIBUTION LIMITS BASES An evaluation of DNB and test data from experiments of fuel rod bowing in subchannels containing thimble cells has identified that it is appropriate to impose a penalty factor to the accident analyses DNBR results. Accordingly, a thimble cell rod bow penalty as a function of fuel burnup, is applied to the measured values of the enthalpy rise hot channel factor, F This penalty at the end of bundle life, 33000 MWD /yTUisoffset$y. margins available in DNBR analysis and a 1% reduction 0

in FAH*

3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distributica satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testing and periodically 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 n

by reducing the maximum allowed power by 3 percent for eacn percent of tilt in excess of 1.0.

4 704 j47 BEAVER VALLEY - UNIT 1 B 3/4 2-5 Amendment No. J0,20

POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of The limits are operation assumed in the transient & accident analyses.

consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected The 18 month periodic measurement of the RCS total transient operation.

flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.

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)l\\b BEAVER VALLEY - UNIT 1 B 3/4 2-6 Amendment No. 9