ML20211P132

From kanterella
Jump to navigation Jump to search
Amend 89 to License DPR-6,revising Tech Spec Section 5.2.1.b to Add Table of Uncertainty Factors Re Analysis of Core Thermal Hydraulic Parameters for Reload I-2 Fuel & to Provide Footnotes Delineating Use of Values
ML20211P132
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 02/19/1987
From: Rajender Auluck
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211P120 List:
References
NUDOCS 8703020300
Download: ML20211P132 (9)
v • d • e


Text

'

. o nto

,,o,, UNITED STATES

. . <> NUCLEAR REGULATORY COMMISSION wash:NGTON, D. C. 20G55 3 3 ,E

%,...../

i b

CONSUMEPS POWER COPPANY DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 89 License No. DPR-6

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Consumers Power Company (the licensee) dated February 4,1987 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 (1) that the activities authorized by this amendment can be conducted without endancering the health and safety of the public; and (111 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 Commission's regulations and all applicable requirements have been satisfied.

7. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operatina License No. DPR-6 is hereby

( amended to read as follows:

l 8703020300 070219 P

I,DR ADDCK 05000155 PDR l

-2 -

E (2) Technical Specifications t-The Technical Specifications contained in Appendix A as revised through Amendment No. 89, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATOPY COMMISSION Ra.iender Auluck, Actino Director BWR Proiect Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: February 19, 1987 i

l l

ATTACHMENT T0 l! CENSE AMENDPENT NO. 89 ,

FACILITY OPERATING LICENSE NO. DPR-6

- DOCKET NO. 50-155 l-Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 5-9a 5-9a 5-9b 5-9b 5-9c 5-10 5-10 5-11 5-11 5-12 5-12 I

. TABI.E 1

. Reload G Reload Reloads Including Reload G3/G4/H1/ Reload F & Modified F C13/G14 CIU B2/H3/H4 II/I2 Minfaus Critical Power i i RatioatNormagOperation 1.59 1.59 1.59 1.59 1.61 Conditions * (IN-Miniava Bundle Dryout Time ** Figure 1 - - - -

MaximusHeatFluxaj(1) overpower Btu /h-Ft 500,000 395,000 407,000 392,900 392,900 l

Maximum Steady) State Heat Flux, Btu /h-ft (1) 410,000 324,000 333,600 322,100 322,100 l Maximus Average Planar Linear Heat Generation Rate.

Steady State, kW/Fe*** (1) Table 2 Table 2 Table 2 Table 2 Table 2 l Maximus Bundle Power, MWg (1) Fig. 2 x 0.95 Fig. 2 Fig. 2 Fig. 2 Fig. 2 l

Stability Criterion: Max.

i Measured Zero-to-Peak Flux Amplitude. Percent of Average Operating Flux 20 20 20 20 20 Maximus Steady-State Power Level. MW t Maximua Value of Average Core Power Density 46 46 46 46 46 6 240 MW , kW/L t

Nominal Reactor Pressure During Steady-State Power 1,335 1,335 1,335 1,335 1,335 Operation, Psig Minimum Recirculation Flev Rate Lb/h 6 x 10 6 6 x 10 6 6 x '10 6

6 x 10 6 6 x 10 6 l Rate of Change of Reactor i Power During Power Operation:

Control rod withdrawal during power operation shall be such that the average rate of change of reactor power is less than 50 MW per minute when power is less than 120 MWg, less than 20 MW per minute when power is Ietween 120 MW, and 200 MW,, and 10 MW, per minutewhenpowIrisbetween200MW and t 240 MWg.

  • The bundle Minimus Critical Power Ratio (MCPR), based on the Exxon Nuclear Corporation XN-2 Critical Power Correlation, must be above this value.
    • The actual dry out time for GE 9x9 fuel (based on the General Electric Dryout Correlation for Nonjet Pump Boiling Water Reactors. NEDE-20566) should be above the dryout time shown in Figure 1.
      • For operation with only one recirculation loop in service these limits shall be reduced by 5 percent for Reload F and Modified F and reduced by 20 percent for other fuel types.

5-9a Amendment No. $J, 69, $1,89

TABLE 1 (Cont'd)

Note 1: Actual Calculated Critical Power Patio, Heat Flux, Average Planar '

LinharHeatGenerationRate,andBundlePowervaluesusedtomonitor conformance to the associated thermal-hydraulic limits shall include the uncertainties listed in Table 3 and be bounded by the Technical Specification limits found in Table 1.

Note 2: Maximum Steady-State Power level shall not exceed a power such that any thermal-hydraulic limit listed in Table 1, Table 2, Figure 1, or Figure 2 is exceeded.

l l

l l

l l

5-9b Amendment No. 89

TABLE 2 MAPLHGR (KW/FT) LIMITS

  • il Planar Average Reload Reload Recon-Exposure Modi- Reload Reload Reload G3/G4/ Reload Reload stituted Reload MWD /STM) fied F F G G1U H1 H2 H3/H4 G13/G14 II/I2 0 - - - - 7.21 7.0 6.77 - 6.92 200 9.5 9.4 - - - - - - 7.28 360 - - - -

7.62 - - - -

1,000 - - - - 7.95 7.8 7.56 1 7.65 1,630 - - -

7.56 7.81 - - - -

3,810 - - -

7.57 - - - - -

3.900 - - - -

7.65 - - -

7.95 5,000 9.9 9.7 - - - - - - -

6.440 - -

7.28 - - - - - -

6,620 - - -

7.50 7.48 7.48 7.48 - 7.89 10.000 9.9 9.7 - - - - - - -

12,880 - - 7.17 - - - - - -

13.520 - - - -

7.49 - - -

8.00 13,610 - - -

7.56 - - - - -

15,000 9.8 9.6 - - - - - -- -

19,050 - - 7.11 - - - - -

7.89 8.6 - -

20,000 8.7 - - -

20.320 - - - -

7.56 7.56 7.56 - -

20,870 - - -

7.78 - - - -

7.76 24.580 - - 6.84 - - - - - -

25,000 8.4 8.3 - - - - - - -

26,400 - - - - 7.32 7.32 7.32 -

7.19 26,760 - - - 7.64 - - - - -

28,210 - - 6.08 - - - - -

l i 30,000 7.4 7.3 - - - - - 6.0 6.97 31,210 - - - - 6.73 6.73 6.73 - -

32,000 7.0 6.9 - - - - - 6.0 -

33,020 - - - 7.12 - - - - 6.81 33,380 - - - - 6.69 6.69 6.69 - -

34,000 6.5 6.5 - - - - - 6.0 -

34,470 - - 5.73 - - - - -

6.73 36,000 6.2 6.1 - - - - - 6.0 -

36,290 - -

5.73 - - - - -

38,000 - - - - - - - 6.0 -

40,000 - - - - - - - 6.0 -

41,400 - - - - - - - 6.0 -

CHAPLHGR ratios shall include the uncertainty listed on Table 3. l 5-9c Isme mtnt No. EJ, 62, EJ, 89

(- - _

l t O l

1 TABLE 3 i kHCERTAINTY FACTORS APPLIED TO THERMAL-HYDRAULIC PARAMETERS Parameter Uncertainty Factor l

MCPR .1531 Heat Flux 9.4017%

MAPLHGR Ratio .0784 Actual Bundle Power / Max Allowed Bundle Power 3.7661%

5-10 Amendment No. ,.- 26, fA, 89

1 2.5

- t l-l l

2.0 E

E -

S

? -

G g -

nl -

G g 1.5 o

E -

a y -

Q= WAPLHGR LIMIT X NUMBER OF ACTIVE FUEL RODS l

1.0

/

N 600 700 800 TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE Q(KW/FT)

FIGURE 1 FUNCTION T(Q) FOR GE 9 X 9 FUEL POWER VOID RELATION

  • l
  • The maximum bundle peak linear heat generation rates shall include uncertainties listed for MAPLHGR in Table 3.

5-11 Amendment No. JE, 76, $f, 89

L NORTH 2.30 3.22 3.22 3.22 3.22 2.30 3.69 L.00 h.00 h.00 h.00 3.69 2.30 3.69 L.00 h.00 3.9h k.00 h.00 h.00 3.63 2.30 3.22 h.00 h.00 h.00 k.00 h.00 h.00 h.00 h.00 3.22 3.22 L.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 3.22 L.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 i

2.30 3.69 h.00 h.00 h.00 h.00 h.00 h.00 3.69 2.30 l

3.69 h.00 h.00 h.00 h.00 3.69 l

2.30 3.22 3.22 3.22 3 22 2.30 I

l Figure 2 Maximus Bundle Power, NWg

  • l l
  • Maximum bundle power ratios shall include the uncertainty listed in Table 3.

5-12 Amendment No. 26, ff, 89

- . . . . - - . . _ . _ - - . . . . _ _ ___ .. .-- - _ - - _ -_ _ .

Retrieved from "https://kanterella.com/w/index.php?title=ML20211P132&oldid=3247643"