ML20082H652
| ML20082H652 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/15/1991 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20082H645 | List: |
| References | |
| NUDOCS 9108260205 | |
| Download: ML20082H652 (2) | |
Text
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ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Document Coni 91 Desk, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with
'opy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle and any remaining part of a reload cycle for the following:
3.1.1.3.c Negative Moderator Temperature Coefficient limit 3.1.3.6 Regulating Rod Insertion Limits 3.1.3.7 Rod Program 3.1.3.9 Axial Power Shaping Rod Insertion Limits 3.2.1 AXIAL POWER IMBALANCE 3.2.4 QUADRANT POWER TILT The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC, specifically:
1)
BAW-10122A Rev. 1, " Normal Operating Controls", May 1984 2)
BAW-10ll6A, " Assembly Calculations and Fitted Nuclear Data",
May 1977 3)
BAW-10ll7P-A, " Babcock & Wilcox Version of PDQ User's Manual",
January 1977 4)
BAW-10ll8A, " Core Calculational Techniques and Procedures",
December 1979 5)
BAW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions", August 1976 6)
BAW-10125A, " Verification of Three-Dimer,sional FLAME Code",
a August 1976 7)
BAW-10152A, " NOODLE - A Multi-Dimensional Two-Group Reactor og Simulator", June 1985 oso 8)
BAW-10119, " Power Peaking Nuclear Reliability Factors", June 1977 m
ou
$8 9)
The methodology for Rod Program received NRC approval in the Safety 7
Evaluation Report dated January 31, 1990.
m 35 The core operating limits shall be determined so that all r.
ble limits
- (e g.,
fuel thermal-mechanical limits, core thermal-hydraui,-
m.
, ECCS ll CRYSTAL RIVER - UNIT 3 6-15 Amendment No.
. t.
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REACTIVITY CONTROL SYSTENS N0DERATOR TENPERATURE COEFFICIENT LINITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
a.
Less positive than 0.9 x 10 Ak/k/*F whenever THERMAL POWER is < 95%
of RATED. THERMAL POWER, b.
Less positive than 0.0 x IF' Ak/k/*F whenever THERMAL POWER is 195% -
of RATED THERMAL POWER, and c.
Equal-to or less negative than the limit provided in the CORE
-OPERATING LIMITS REPORT at RATED THERMAL POWER.
APPLICABILITY: MODES 1 and 2*#,
ACTION:
With the moderator temperature coefficient outside any of the above limits, be-in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIRENENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. Mic measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.3.2.The MTC shall be determined at the _following frequencies and THERMAL POWER Conditions during each fuel cycle, a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading, b.
At any THERMAL POWER, within 7 days after reaching a RATED THERMAL l
POWER equilbrium boron concentration of 300 ppm.
~
'*With K,,, 1 1.0.
- See Special Test Exception 3.10.2.
CRYSTAL RIVER - UNIT 3 3/4 1-4 AMENDMENT N0.
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