ML20028F036
| ML20028F036 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/19/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028F037 | List: |
| References | |
| NUDOCS 8301280497 | |
| Download: ML20028F036 (8) | |
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. pn Uzuq4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION e E WASHINGTON, D. C. 20585 o
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 61 License No. UPR-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 December 16, 1982, 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 Commission; C.
There is reasonable assurance (i) that th2 activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Commission's regulations; i
l D.
The issuance of this amendment will not be inimical to the comon defense rnd 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.
r 8301280497 830119 PDR ADOCK 05000334 p
ATTACHMENT TO LICENSE AMEN 0 MENT AMENDMENT NO. 61 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Fages 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 B3/4 2-4 B3/4 2-4 I
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- o POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRDfENTS 4.2.2.1 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 q
limit by:
a.
Using the movable incore detectors to obtain a power distribu-tion map at any THERMAL POWER greater than:5%,of RATED THERMAL POWER.
b.
Increasing the measured F, component of the power distrib'stion map by 3% to account for manufacturing tolerances and further increasing the valce by 5% to account for esasurement uncer-tanties. When the number of available moveable detector thimbles is less than 75%*of the total, the 5% asasurement uncertainty shall be increased to [5% + (3-T/12.5)(2%)] where T is the number of available thimbles.
c.
Comparing the F computed (F,
) obtained in b, above to:
1.
The F limits for RATED THERMAL POWER (F
) for the xy xy appropriate measured core planes given in e and f below, and 2.
The relationship:
F, (1+0.2(1-P)]'
=
L where F is the limit for fractional THERMAL' POWER operati n expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F was measured.
- 7 d.
Remeasuring F according to the following schedule:
0 g
1.
When F is greater than the limit for the appropriate measured core plane but less than the F, relationship, i
additional power distribution maps'shall be taken and F,y compared to F and F a)
Either within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20% of RATED THERMAL POWER or greater, 'the THERMAL POWER at which F was last determined, or.
b)
At least once per 31 EFPD, whichever occurs first.
- See footnote on page 3/4 3-37 for limitation l
Beaver Valley - Unit 1 3/4 2-6 Amendment No, 61 O
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POWER' DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
When the F,7 islessthanorequaltotheFf'limitforthe 2.
appropriate measured core plane, additional power distribution maps shall be taken and F Compared to F and F at least
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- I once per 31 EFPD.
a.
The F limit for Rated Thermal Power (
) shall be provided for g
all core planes containing bank "D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.10.
f.
The F, limits of e, above, are not applicable in the following 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 go 100% inc}usive.
3.
Grid plane regions at 17. &- 2%, 3 2.1 -- 2%,
46.4 + 2%, 60.6 + 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" control rods.
q (Z) shall be g.
With F exceeding F
, the effects of F on F g
evaluated to determine if Fq (Z) is within its limit.
4.2.2.3 When Fg (Z) is measured pursuant to Specification 4.10.2.2, an overall measured F (Z) shall be obtained from a power distribution map and increased 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
When the number of available moveable detector thimbles is less than 75%*of the total, the 5% measurement uncertainty shall be increased to [5% + (3-T/12.5)(2%)] where T is the number of available thimbles.
.)
- See footnote on page 3/4 3-37 for limitation Beaver Valley-Unit 1 3/4 2-6a Amendment No. 61
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POWER DISTRIBUTION LIMITS SIIRVEILLANCE REQUIRMENTS (continued) 4.2.3.1 F
shall be determined to be within its limit by using moveable g
incore detectors to obtain a power distribution map:
a.
Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.
At least once per 31 Ef fective Full Power Days.
4.2.3.2 The measured F f 4.2.3.1 above, shall be increased by 4% for AH measurement uncertainty. When the number of available moveable detector thimbles is less then 75%*of the total the 4% measurement uncertainty shall be increased to [4% + (3-T/12.5)(1%)] where T is the number of available thimbles.
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- See foo*, note on page 3/4 3-37 for limitation
, Beaver Valley-Unit 1 3/42-9 Amendment No. 61 I
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INSTRbMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:
a.
At least 50% of the detector thimbles, b.
A minimum of 2 detector thimbles per core quadrant, and c.
Sufficient movable detectors, drive, and readout equipment to map these thimbles.
APPLICABILITY: When the movable incore detection system is used for:
A.
Recalibration of the axial flux offset detection system, B.
Monitoring t'he QUADRANT POWER TILT RATIO, or
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C.
Measurement of F and Fq (Z).
AH ACTION:
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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.
I SURVEILLANCE REQUIREMENTS 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.
Recalibration of the excore axial flux offset detection system, or b.
Monitoring the QUADRANT POWER TILT RATIO, or q (Z).
c.
Measurement of F and F A
- This percentage (changed from 75%) is only applic^able during the present fuel cycle, Cycle 3, which is expected to end about June 1983. This specification needs,to be revised prior to startup of the next cycle.
Beaver Valley-Unit 1 3/4 3-37 Anendment No. 61 1
9 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 9
H The lini'ts on heat flux and nuclear enthalpy at 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 normally 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:
I 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.
i c.
The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.
j d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE is maintained within the limits.
The relaxation in F as a functi n f THERMAL POWER allows changes 4H in the radial power shape for all permissible rod insertion limits. F 4H will be maintained within its limits provided conditions a thru d above, are maintained.
Wher an F measurement is taken, both experimental error and manufacturing q
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.
When the number of available moveable detector thimbles is less than 75%
- of the total, the 5% measurement uncertainty shall be increased to
[5% + (3-T/12.5)(2%)] where T is the number of available thimbles.
W The specified limit of F c ntains an 8% allowance for uncertainties 4H which means that normal, full power, three loop operation will result in F
1.55/1.08.
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- see footnote on page 3/4 3-37 for limitation Beaver Valley-Unit 1 B 3/4 2-4 Amendment No. 61 G
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