ML20196E544
| ML20196E544 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/17/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20196E548 | List: |
| References | |
| NUDOCS 9906280305 | |
| Download: ML20196E544 (3) | |
Text
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POWER DISTRIBUTION LINITS i
- *LINITING CONDITION FOR OPERATION (Continued)
(2) Reduce THERMAL POWER at least 1% for each 1% Fa(Z) exceeds the limit within 15-minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% Fo(Z) exceeds its limit shall be calculated as the maximum percent over the core height (Z), consistent with Specification 4.2.2.1.4.f, by the following expression:
'* (
-1 x 100 for P :n APL" x K(Z)
SURVEILLANCE REQUIRENENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.1.2 For RAOC operation, Fa(Z) shall be evaluated to determine if Fa(Z) is within its limit by:
Using the movable incore detectors to obtain a power distribution map a.
at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
b.
Evaluate the computed heat flux hot channel factor by performing both of the following:
(1) Determine the computed heat flux hot channel Factor, Fa"(Z) by increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increase the value by 5%
to account for measurement uncertainties, and (2) Verify that Fa"(Z) satisfies the requirements of Specification 3.2.2.1 for all core plane regions, i.e. 0-100% inclusive.
NILLSTONE - UNIT 3 3/4 2-7 Amendment No. pp, pp 77,170 6307 9906290305 990617 i
PDR ADOCK 05000423 P
7 l
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ADNINISTRATIVE CONTROLS CORE OPERATING LINITS REPORT (Cont.)
7.
WCAP-Il946, " Safety Evaluation Supporting a More Negative EOL l
Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," September 1988 (W Proprie-i tary).
8.
WCAP-10054-P-A, " WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL.17 l
USING THE NOTRUNP CODE," August 1985 (W Proprietary).
(Methodology i
for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
9.
WCAP-10079-P-A, "NOTRUMP - A N0DAL TRANSIENT SMALL BREAK AND GENERAL l
NETWORK CODE," August 1985 (W Proprietary).
(Methodelogy for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- 10. WCAP-12610, " VANTAGE + Fuel Assembly Report," June 1990 (W l
Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- 11. Letter from V. L. Rooney (USNRC) to J. F. Opeka, " Safety Evaluation for Topical Report, NUSCO-152. Addendum 4, ' Physics Methodology for PWR
' Reload Design,' TAC No. M91815," July 18, 1995.
- 12. Letter from E. J. Mroczka to the USNRC, " Proposed Changes to Technical Specifications, Cycle 4 Reload Submittal - Boron Dilution Analysis,"
B13678, December 4, 1990.
- 13. Letter from D. H. Jaffe (USNRC) to E. J. Mroc:ka, " Issuance of Amendment (TAC No. 77924)," March 11, 1991.
- 14. Letter from M. H. Brothers to the USNRC, " Proposed Revision to Technical Specification, Shutdown Margin Requirements and Shutdown Margin Monitor Operability for Modes 3, 4, and 5 (PTSCR 3-16-97),
B16447, May 9, 1997.
- 15. Letter from J. W. Anderson (USNRC) t'o M. L. Bowling (NNECO), " Issuance of Amendment - Millstone Nuclear Power Station, Unit No. 3 (TAC No.
M98699)," October 21, 1998.
MILLSTONE - UNIT 3 6-20a Amcndment No. 71,170 oeos.
R. Necci A second editorial error was identified to the staff on the retyped page 6-20a. Specifically, reference 11, should be a letter from V. L. Rooney (USNRC) dated July 18,1995, instead of a letter from V. L. Rooney dated July 8,1995.
The enclosed replacement pages are to be used to replace the incorrect pages provided ir the May 10,1999, letter transmitting Amendment No.170 to Operating License NPF-49 for the Millstone Nuclear Power Station, Unit No. 3. If you have questions or comments regarding the errors and omission in the retyped TS pages, please contact me at 301-415-1278.
Sincerely, ORIGINAL SIGNED BY:
{
John A. Nakoski, Sr. Project Mai ager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Pages 3/4 2-7 and 6-20a I
cc w/ encl: See next page DISTRIBUTION:
Docket PUBLIC EAdensam (EGA1) TClark JLinville, RI JClifford JNakoski WBeckner OGC ACRS GHill (2)
PDI-2 Reading D_ocument Name: A4574COR.WPD OFFICE PDl-2:PM PDI-2:LA 6 SRXp,,f 6 OGC Meh PDI-2:QC NAME JNakosl%b TCla3%
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JClitkrd DATE 19/'i/9%
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