ML19339C995
| ML19339C995 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/02/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339C992 | List: |
| References | |
| NUDOCS 8102130066 | |
| Download: ML19339C995 (6) | |
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UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION 7 E WASHINGTON. D. C. 20555
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OMAHA PLTLIC POWER DISTRICT l,
DOCKET N0. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.55 License No. DPR-40 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated January 14, 1981, complies Act of 1954, as amended (quirements of the Atomic Energy with the standards and re the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the appli-cation, the provisions of the Act, and the rules and regulations of the Comission; t
C.
There is reasonable assurance (1) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to i
read as follows:
B.
Technical Specifications i
The Technical Specifications contained in Appendices l
A and B, as revised through Amendment No. 55, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION MiE k Robert A. Clark, Chief 3
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 2, 1981 b
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ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. OPR-40 l
DOCKET NO. 50-285 i'
l 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.
i Pages iii 6-4 (added) 6-5 (added) 6-6(added) i i
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TABLE OF CONTENTS (Continued)
Page 5.9 Reporting Requirements...................................... 5-10 5.9.1 Routine Reports..................................... 5-10 5.9.2 Reportable Occurrences.............................. 5-12 5.9.3 Special Reports..................................... 5 *5 5.9.4 Unique Reporting Requirements........................ 5-15 5.10 Records Retention.......................................... 5-18 5.11 Radiation Protection Program............................... 5-19 5.12 Environmental Qualifications............................... 5-20 6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS......................... 6-1 6.1 Limits on Reactor Coolant Pump Operation.................... 6-1 6.2 Use of a Spent Fuel Shipping Cask........................... 6-2 6.3 Auxiliary Feedvater Automatic Initiation Setpoint...........
6-3 6.4 Operation with Less Than 75% of Incore Detector Strings 0perable.......................................... 6-4 Arend:ent No. 32, 34, #3, 34, 55 iii
6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.4 Operation With Less Than 75% of Incore Detector Strings Operable Applicability Applies to power operation during Cycle 6 and can be used in lieu of Specification 2.10.3(2).
Objective To monitor kw/ft and power distribution with less than 75% of the in-core detector strings operable.
Specification (1) Theincoredetectors{stemshallbeoperabletomonitorpeak' T
linear heat rate, F
,FR, and the radial power distribution withlessthan75%bbtmorethan20%ofallincoredetector x
strings and one incore detector string per full length quadrant, where an operable string ccasists of three or more operable rhodium detectors, provided:
(a) The planar radial peaking factor uncertainty, Uxy, the integrated radial peaking factor uncertainty, U, and R
the total peaking factor uncertainty, U, are determined q
every 31 EFPD, in accordance with the reference.
to be used in evaluating the (b)
If UR > 6% the value of FR approach to the limits of Specification 2.10.4(2) is F
=F M (1 + UR - 0.06)
R R
M where F is datermined from a power distribution map R
with no part length CEA's inserted and all full length CEA's at or above the Long Term Steady State Insertion limit for the existing Reactor Coolant Pump combination, and the integrated radial peaking factor uncertainty, U
is the latest determined value of UR at the time Rg F
is determined.
R (c)
If U
> 7% the calculated value of.F to be used in.
xy evalstingtheapproachtothelimitsofSpecification 2.10.4(3) is F
=F M (1 + U
- 0.07) xy xy M
where F is determined z.at a power distribution map xy vith no part length CF.'J s, tset'ted and all full length CEA's c
- above rk i cv '"erra Steady State Insertion limit fuc the exis.its bi.or Coolant Pump' combination and the planar radigt peakte factor uncertainty, xy, is at the time F is the latest determined value of IJ,9 xy
-determined.
Amendment No. 55 6-4
6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.'
Ooeration With Less Than 75% of Incore Detector Strings Operable (Continued) as (q > 7% the total peaking uncertainty factor defined (d)
If U I + U ) shall be used in place of the measurement-q calculation factor of 1.07 in Specification 2.10.4(1).
(e) The maximum local peak linear heat rate in the core, Cmax, shall be determined and the incore detector alarms shall be adjusted to no greater than the following:
Alarm Setting = C *
- allowed-imax where C = The detector signal converted to flux units when the reactor is operating at steady-state.
Callowed = Linear Heat Rate (kw/ft) allowed by Specifi-cation 2.10.4(1) and adjusted as required by Specification 6.3(1)(d).
Cmax = The maximum local peak linear heat rate (kw/ft) measured at the same reactor conditions as C above.
(2)
If the incore detector system is not operable within the interval specified, the peak linear heat rate shall be monitored by ex-core, detectors per Specification 2.10.4(1)(c) and the surveillance requirements of Specification 3.10(5) are deleted.
Basis Operation of the incore detector system for peak linear heat rate I and F T with less than 75% of monitoring and surveillance of FR xy the strings operable requires additional measures to compensate i
for degradation of the incore instrument system. Periodic com-i parisons between calculated and reas red power distributions'are made to confirm the core is depleting as designed.
The measure-ment uncertainties are computed to assure the assumptions made in the setpoint analysis are valid.
The uncertainties are computed using the methods given in the reference.
If the determined uncertainties exceed the uncertainties used in the setpoint and safety analysis, the measured values of FR and F
are augmented by the appropriate uncertainty. These new values xy of' FR and F are then used to verify compliance with Specifications 2.10.4(2)and2.10.4(3). -This assures that the product of the x
radial peaking factors and their appropriate uncertainties are less than the values used in determining the setpoints.
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6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.4 Operation With Less Than 75% of Incore Detector Strings Operable (Continued)
.The minimum margin to the kw/ft limit is used to set alarms on all detectors.
This imposes restraint on the power distribution as well as the peak linear heat rate and precludes the occurrence of undetected peaks larger than the limit. When incore detectors alarms are set using this method, several alarms would be re-l ceived in the event of a shift in the power distribution even though the maximum local peak linear heat rate may not be exceeded.
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Reference l
INCA /CECOR Power Peaking Uncertainty - CENPD-153-P, Revision 1-P-A, May 1980.
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