ML19332C761
| ML19332C761 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/17/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332C743 | List: |
| References | |
| TAC-49436, NUDOCS 8911280518 | |
| Download: ML19332C761 (8) | |
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- UNITED STATES
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i NUCLEAR REGULATORY COMMISSION r
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. WASMNGTON, D. C,20555 A
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g-y DUQUESNE LIGHT COMPANY 0HIO EDISON COMPANY PFWNSY1VANTA POWFR COMPANY 00cv.FT NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE y
Amenament No.-73 License No. DPR-66 1.
'The Nuclear Regulatory Comission.(the Comission) has founc that:
A.
The, application for emc.ndment by Duquesne Light Company, Ohio ' Edison
' Company, and Pennsylvania Power Company (the licensees) dated
. December 16, 1982, supplemented by letters dated January 4 and February 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, &nd the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorizec by this amendment can be conductea without endangering the health ano safety of the publip, and (ii) that such activities will be conoucted in compliance with the Comission's regulations;
.D.-
The issuance of this amencment will not be inimical to the common defense and security or to the health and safety of the public; ana' E.
The issuance of this amenament is in accoraance with 10 CFR Part 51 of the Commission's regulations ano all applicaole requirements have been satisfied.
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8911280518'831017 DR p
ADOCK 03000334 PDR
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2.
Accordingly, the license is amended 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. DPR-66 is hereby amendea to read as follows:
(2)
Technical ' Specifications The Technical Specifications contained in pendices A and B, as revised through Amendment No.
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0&tISSION I
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Opcrating Reactor anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 17, 1983 l
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ATTACHMENT-TO LICENSE AMENDMENT-g
. AMENDMENT HO. 73 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise' Appendix A' as follows:
Remove Pages MsertPages y
3/4'2-6 3/4 2-6 sv
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3/4 2-6a 3/4 2-6a 3/4 2-9 3/4 2-9 i-3/4 3-37 3/4 3-37 B'3/4~2-4 B 3/4 2-4 i
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m TOWER DISTRXBUTION LIMITS 7,,,
b' 3
~ SURVEILLANCE' REQUIREMENTS t,
L4. 2. 2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2
.F shall be evaluated to determine if F (Z) is within its xy g
limit by:
J a.
Using the movable incore detectors to obtain a power distribu-
. tion nap at any THERMAL POWER greater than 5% of RATED THERMAL POWER.-
Incrc: sing the measured F component of the power distribution-
'v.
xy
' map by 31 to account for manufacturing tolerances and further L
increasing the value by 5% to account for measurement uncer-
- tanties, c.
Comparing the F computed (Fxy ) obtained in b, above to:
xy 1.
The F limits for RATED THERMAL POWER (FRTP ) 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-P)]
i x
l
.where F is the limit for fractional THERMAL POWER RTP opera tio expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F
.was XJ measured.
d.
Remeasuring F according to the following schedule:
xy RTP 1.
When F is greater than the F limit for the appropriate x
x measured core plane but less than the F relationship, xy additional power distribution' maps shall be taken and RTP F
compared to F and F x
x x
a)
Either within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; after exceeding by 20% of 4
RATED THERMAL POWER or greater, the THERf1AL POWER i
at which F was last determined, or b)
At least once per 31 EFPD, whichever occurs first.
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l Beaver Valley - Unit 1 3/4 2-6 l
Amendment No. 73
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a, Y.
' POWEF. DISTFaiiUT10ff LIMITS SURVElLLANCE RE0VIREMENTS-(Continued)
- 2.,
When the F is less than or equal to the F limit for the x
appropriate measured core plane, additional power distribution C
RTP L
. map:' per 31 EFPD.shall be taken and F*7 Compared to F and F*7 at least
- J once e.
The F limit for Rated Themal Power (F P) shall be provided for xy all core planes containing bank'"D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.14.
1 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 PS $o 100% inc Grid plane regions at 17.F 2%, 32.1 -}usive.
3.
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 2.88 inches) about the bank demand position of the bank "D" cantrol rods.
g.
With F exceeding F
, the effects of F nFq (Z) shall be x
xy evaluated to detemine if Fq (2) is within its limit'.
j 4.2.2.3 When Fn (Z) is measured pursuant to Specification 4.10.2.2, an overalT measured Fn (Z) shall be obtained from a power distribution map and increased Dy 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
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l BEAVER VALLEY - UNIT 1 3/4 2-6a Amendment No.
73
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. POWER DISTRIBUTION LIMITS-6 e
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SURVEILLANCE' REQUIREMENTS N
h 4. 2. 3.1 -
F shall be determined to be within its limit by using moveable.
.i$$ ore detectors to obtain-a power distribution map:
a.
-Prior to operation above 75% of RATED THERMAL POWER a'fter each fuel loading, and c'
b.
AL'least'w.ce per 01EEffective Full Power Days, o
D.
I 4.2.2.2 Thefmeasured'F of 4.2.3 lf above, shall be increased by 4% for H
measu rement. uncertainty.
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BEAVER VALLEY - UNIT 1 3/42-9 Amendment No. 73 a
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'.INhTROi1ENTATION-I[ _
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- .j w :MOVABLC INCORE~ DETECTORS
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l LIMITING CONDITION FOR OPERATION
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-3.3.6.2
- The movable incore detection system shall be OPERABLE with:
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At least-75% of the detector thimbles, a.
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B b.-
A min imuns of. E' detectoi thidoles per core quads on t, and c..
Sufficient movable detectors, drive, and readout equipment to map these : thimbles.
l 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 Fq (2).
3 ACTION:
With the movable incore detection system inoperable, do not use the system for-the -above applicable monitoring or calibration functions.
The
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Lprovisions of ~ Specifications. 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS h
4.3.3.2 The incore movable detection system shall be demonstrated OPERABLE by normalizing 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:
'a.
Pecalibration of the excore axial flux offset detection system, or b.
Monitoring the QUADRANT POWER TILT RATIO, or
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c.
Measurement of F and Fq (Z).
A I:
Beaver Valley-Unit 1 3/4 3-37 Amendment No. 73
go; p J F0WER D1sTRIBUT10N LIMITS' RkSESI 13/4.2.2 and' 3/4.2;3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS-
-F(Z)andF{H-0 The limits on heat flux and nuclear enthalpy hot channel factors ensure
-that 1): tne design limii.s on peak local power der,:,ity arid minim = DMBR cre
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not-exceeded and 2) in the event of a LOCA the peak fuel c{ad temperature-
- will' not exceed the ECCS acceptance criteria limit _ of '2200 F.
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~ Each of these hot' channel factors are measurable but will normally only
'be detennined 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-denand position.
b.
Control rod groups are sequenced.with overlapping groups as' described in Specification 3.1.3.5.
d c.
The control rod insertion limits of Specifications.3.1.3.4 and 3.1.3.5 are maintained.
d.
Th6 axial power distribution, expressed in tenns of AX1AL FLUX DIFFERENCE is maintained within the limits.
N The relaxation in-F as a function of THERMAL POWER allows changes 6H N
~ in the radial _ power shape for all pennissible rod insertion limits.
F AH will be maintained within its limits provided conditions a thru d above, are maintained.
1 When an F measurement is taken, both experimental error and manufacturing j
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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.
' The specified limit of F" which means that normal, full p$wer,tains an 8% allowance for uncertainties con three loop operation will result in F g. 51. 55/1. 08.
l Beaver Valley-Unit 1 B 3/4 2-4 Amendment No.
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