ML20081E086
| ML20081E086 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/13/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081E091 | List: |
| References | |
| NUDOCS 8311010457 | |
| Download: ML20081E086 (8) | |
Text
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[ ].- [ %j NUCLEAR REGULATORY COMMISSION UNITCD s7ATEs
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,5 WASHINGTON. O. C. 20555 s, %.
m.... J;j OUOUESNE LIGHT CCMPANY OHIO EDISON COMPANY PENNSY1VANTA POWER COMPANY 00rVET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amencment No. 73 License No. OPR-66 1.
The Nuclear Regulatory Ccmission (the Cecraission) has found that:
A.
The, application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Pcwer Company (the licensees) dated December 16, 1982, supplemented by letters dated January 4 and Februa ry 24, 1983, 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 Comission; C.
There is reasonable assurance (i) that the activities autharizea by this amendment can be concucted without endangering the health and safety of the publi,c, and (ii) that such activities will De concucted in comoliance with the Comission's regulations; D.
The issuance of this amencment will not ce inimical to the comon cefense and security or to the healtn and safety of the puolic; and E.
The issuance of this amencment is in accorcance with lu CFR Part 51 of the Ccmission's regulations anc all applicaole requirecents have been satisfied.
1 8311010457 831013 PDR ADOCK 05000334 P
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2.
Accordingly, the license is amenced by changes to the Technical Specifications as indicated in the attachment to this license amenament, and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to reaa as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 73
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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e la ei-Operating Reactor. anch el Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 17, 1903 l
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ATTACHMENT TO LICENSE AMENDMENT
' AMENDMENT HO 73 TO FACILITY OPERATING LICENSE NO 'OPR-66 OOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4'2-6 3/4 2-6 3/4 2-6a 3/4 2-6a 3/4 2-9 3/4 2-9 3/4 3-37 3/4 3-37 B 3/4 2-4 8 3/4 2-4 9
6
F0WEk O!STRIBUT10f; LIMITS
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SURVEILLAflCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 F
shalI be evaluated to ceterrine if F (Z) is within its xy g
limit by:
i Using the covable incore detectors to obtain a power distribu-.. -. -
a.
tion map at any THE&iAL POWER greater than 5'. of RATED ThERiiAL PCWCR.
L.
Incrossing the measured F,y component of the power distribution cap by 31 to account for manufacturing tolerances and further increasing the value by 5! to account for measurement uncer-tanties.
C c.
Comparing the F computed (Fxy ) obtained in b, above to:
xy 1.
The F limits for RATED THERMAL POWER (F ) for the xy x
appropriate measured core planes given in e and f below, and 2.
The relationship:
RTP F
=F
[l*0. 2 (1,5)]
x
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l'is the limit for fractional THERMAL POWER where F operatio expressed as a function of FR and P is the fraction of RATED THERMAL POWER at which F was measured.
- Y d.
Remeasuring F according to the following schedule:
xy is greater than the F,R limit for the -appropriate 1.
When F measured core plane but less than the F
- ela tionship, xy additional power distribution maps shall be taken and F
compared to F and F a)
Either within 24 hour: after exceeding by 20% of
-RATED THERMAL POWER or greater, the THERiiAL POWER at which F was last determined, or b)
At least once per 31 EFPD, whichever occurs first.
4
. Beaver Valley - Unit 1 3/4 2-6 Amendment No. 73 i
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'POWEF. DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued) 2.
When the F
.is itss than or ecual to the FRTP limit for tne xy appropriate measured core plane, additional power distribution C
RTP L
caps shall be taken and F Compared to F and F at least once per 31 EFPD.
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The F limit for Rated' Thermal Power (FRTP) shall be provided for xy x
all core planes containing bank "0" control rods and all unrodoed core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.14.
f.
The F limits of e, above, are not applicable in the following core xy 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 Grid plane regions at 17.8go 100% inclusive.
i 3.
2%, 32.1 - 2%,
46.4 1 2%, 60.6 1 2% and 74.9 1 2%, inclusive 4.
Core plane regions within 1 2% of core height (1.88 inches) 2 about the bank demand position of the bank 0" control
- rods, g.
With F exceeding F
, the effects of F on Fq (Z) shall be xy evaluated to detennine if Fq (Z) is within its. limit'.
4.2.2.3 overal9 m(ea)sured F When F Z is measured pursuant to Specification 4.10.2.2, an n (Z) shall be obtained from a power distribution map and increased Dy 3% to account for manufacturing tolerances and further increased by 5% to accourit for measurement uncertainty.
l BEAVER VALLEY - UNIT 1 3/4 2-6a Amendment No.
73
POWER GISTRIBUTI0r. LIMITS SURVEILLANCE RECUIREMENTS v
F"Uure detectors to-obtain-.a, power distribution map:shall be 4.2.3.1 ik Prior to operation above 75% of RATED THERMAL POWER after each a.
fuel loading, and b.
At least unca per 01 Cffectivt."ull Power Days.
I 4.2.2.2 The measured F g of 4.2.3.1 above, shall be increased by 4% for measurement uncertainty.
BEAVER VALLEY - UNIT 1 3/4 2-9 Amendment No. 73
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JNSTRUf'ENTATION MOVABLE INCORE DETECTORS LIMITIfiG CONDITION FOR OPERATION 3.3.2.2 The movable incore detection system shall be OPERABLE with:
At least 75% of the detector thimbles, a.
L.
A inir.imusa of D detectci thimbles per core yuadr ant, and Sufficient movable detectors, drive, and readout equipment to c.
map these thimbles.
APPLICABILITY: When the movable incore detection system is used for:
A.
Recalibration of the axial flux offset detection system, B.
Monitoring the QUADRANT POWER TILT RATIO, or C.
Measurement of F and F9 (Z).
ACTION:
With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore movable detection system shall be demonstrated OPERABLE by nomalizing each detector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to 'its use when required for:
Recalibration of the excore axial flux offset detection system, a.
or b.
Monitoring the QUADRANT POWER TILT RATIO, or c.
Measurement of F and Fq (Z).
Beaver Valley-Unit 1 3/4 3-37 Amendment No. 73
1 F0WER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX ANC NUCLEAR Ef1THALPY HOT CHAttriEL FACTORS-I F(Z)andF[g 0
The limits on heat flux and nuclear enthalpy hot channel factors ensure tnat 1)' tne cesign limii.s un peak local power der.;ity arid minim = 0.90.'l cr:
not exceeded and 2) in the event of a LOCA the peak fuel c will not exceed the ECCS acceptance criteria limit of 2200[ad temperature F.
Each of these hot channel factors are measurable but will nomally only be detemined 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 differ.ing.by more than + 12 steps fecm the group denand 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 tems of AXIAL FLUX
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DIFFEREt1CE is maintained within the limits.
The relaxation in F as a function of THERMAL POWER allows changes H
in the radial power shape for all permissible rod insertion limits.
F g
will be maintained within its limits provided conditions a thru d above,
-are maintained.
When an F measurement is taken, both experimental error and manufacturing g
tolerance must be allowed for. 5% is the appropriate experimental error allowance for a full core map taken with the incore detector flux mapping system and 3% is the appropriate allowance for manufacturing tolerance.
N I
The specifiel limit of F con which means that nomal, full p$wer,tains an 8% allowance for uncertainties three loop operation will result in F"g g S1.55/1.06.
I B: aver Valley-Unit 1 B 3/4 2-4 Amendment No.
73
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