ML19340B941

Proposed Revision to Tech Specs Re Power Distribution Limits & Surveillance Requirements & Administrative Control Concerning Radial Peaking Factor Limit Repts

ML19340B941
Person / Time
Site:	Farley
Issue date:	11/03/1980
From:	ALABAMA POWER CO.
To:
Shared Package
ML19340B939	List: ML19340B938 ML19340B941
References
NUDOCS 8011120614
Download: ML19340B941 (4)

Text

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POWER DISTRIBUTION LD!ITS SURVEILLANCE RE0VIREMENTS (Continued)

C RTP

2. When the F xy is less than or equal to the F xy limit for the appropriate measured core plane, additional power distribution

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RTP maps shall be taken and FxyC compared to Fxy and F xy' at least once per 31 EFPD.

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f. The F limits of e, above, are not apolicable in the following core planeEYregions as measured in percent of core height frc:r the bottom of the fuel:

P 1. Lower core region frca 0 to 15%, inclusive.

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2. Upper core region frca 85 to 100%, inclusive.

. 3. Grid plane regions at 17.8 2%, 32.1 2%, 46.4 2%, 60.6 2%

2%, inclusive.

and 74.9

4. Core plane regions within 2% of core height ( 2.38 inches) "

about the bank demand position of the bank "D" control rods.

C exceeding F xyl the effects of F

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g. With F xy on Fq (Z) shall be evaluated to detcrmine if F q (Z) is within its limits.

4.2.2.3 When F (Z) is measured for other than F determinc.t'ons, an everall g as measured F (Z) khall be obtained from & power diIEribution mac and increased  %

by 3% to a9 count for manufacturing tolerances and further increase by 5% to ,

account for measurement uncertainty.

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POWER OISTRIBUTION LIMITS BASES r~ - -

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3/4.2.4 OUADRANT p0WER TILT RATIO The quadrant power tilt ratio limit assures that the radial cower distribution satisfies the design values used in the power ca: ability analysis.

Radial power distribution measurements are mace during startup testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNS and linear heat generation rate protection with x y plane power tilts.

The two hour time allcwance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and

- gy correction of a dropped or misaligned control red. In the event such action

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does not correct the tilt, the margin for uncertainty on Fq is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of'1.0.

3/4.2.5 DN3 PARAMETERS The limits on the DNS related parameters assure that each of the parameters are maintained within the normal steacy state envelope of coeration assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumstions and have been analytically cemenstrated idequate to maintain a minimum DNBR of 1.30 thr:ugneut eacn analy:ed 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 carameters threugh instrument readout is sufficient to ensure tlat the parameters are restored within their limits following load changes and otner expected transient o=eration. The i

18 month periodic measurement of the RCS total flow rate is adequate to detect i flow degradation and ensure correlation of the ficw indication channels with measured flow such that the indicated percent ficw 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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ADMINISTRATIVE CONTR0'.S

f. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 3.12-2 when average over any calendar quarter sampling period.

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SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time pericd specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections,

_ e'. repair and replacement of principal items of equipment ralated to nuclear safety.

c. All REPORTABLE 0CCURRENCES submitted to the Cce.aission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1.

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, f. Records of radioactive shipments. -

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g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source caterial of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report. -

'b. Records of new and irradiated fuel inventory, fuel transfers and i

', assembly burnup histories. l s , j i

FARLEY-UNIT 2 6-22

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PROPOSED Fyy TECHNICAL SPECIFICATI0tl CHAT;GE Insert To Page 3/4 2-6

_. e. The F limit for Rated Themal Power (FRTP) shall be provided for aN 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.

Insert To Page B 3/4 2-5 The radial peaking factor Fxy(Z) is measured periodically to provide assurance that the hot channel factor, F0 (Z), remains within its limit. The F x limit for Cated Thermal Power (FRTP) as provided in the Radial feaking Factor Limit Report per spedification 6.9.1.14 was determined from expected power control maneuvers over the full range of burnup conditions in the core.

Insert To Page 6-22 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The Fx limit for Rated Themal Power (FRTP shall be provided to the director of the Regional Offi:e of*Tns)pection and Enforcement, with a copy to the Director, Nuclear Reactor Regulations, Attention Chief of the Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit would be submitted at some other time during core life, it will be submitted 60 days prior to the date the limit would become effective unless otheraise exempted by the Comission.

Any infomation needed to support FRTP will be by request from the NRCandneednotbeincludedinthisYreport.

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