ML20113H186
| ML20113H186 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/16/1985 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20113H173 | List: |
| References | |
| JPTS-85-002, JPTS-85-2, NUDOCS 8501250025 | |
| Download: ML20113H186 (10) | |
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ATTACHMENT I TO JPN-85-03 Proposed Technical Specification Chances Related to Reload 6/ Cycle 7 (JPTS-85-002)
New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 8501250025 850116-DR ADOCK 050003gg
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LIST OF FIGURES FIGURE TITLE PAGE 3.1-1 Manual Flow Control 47a 3.1-2 Operating Limit MCPR versus 77 47b 4.1-1 Graphical Aid in the Selection of an 48 Adequate Interval Between Tests
-4.2-1 Test Interval vs. Probability of System 87 Unavailability 3.4-1 Sodium Pentaborate Solution Volume-110 Concentration Requirements 3.4-2 Saturation Temperature of Sodium 111 Pentaborate Solution 3.5 (Deleted) 135d 3. 5.7 (Deleted) 135e.
3.5-8 (Deleted) 135f 3.5-9 MAPLHGR Versus Planar Average Exposure 135g Reload 4, P8DRB284L 3.5-10 MAPLHGR Versus, Planar Average Exposure 135h Reloads 4, and 5 P8DRB299-3.5-11 MAPLHGR Versus Planar Average Exposure 135i l Reload 6, BP8DRB299 1
3.6-1 Reactor Vessel Thermal Pressurization 163 Limitations 4.6-1
. Chloride Stress Corrosion Test Results 164 at 500*F 6.1-1 Management Organization Chart 259 6.' 2-l '
_ Plant Staff Organization 260 Amendment No. We yfr g, frdo ff, }d vil
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JAFNPP 3.1 - (CONTINUED)
MCPR Operating Limit for Incremental
' Cycle Core Average Exposure C. MCPR shall be' determined daily during reactor power operation at 2, 25% of rated thermal power and following any At RBM Hi-trip BOC to EOC-2GWD/t to EOC-lGWD/t change in power level or distribution level setting LEOC-2GWD/t EOC-lGWD/t to EOC control rod pattern as described in the 1 S=
.66W + 39%
1.24 1.29 1.31 bases for Specification.3.3.B.S.
S =.66W + 40%
1.27 1,29 1.31 When it is determined that a channel has D.
failed in the unsafe condition, the S=
.66W + 41%
1.27 1.29 1.31 ther RPS channels that monitor the-same variable shall be functionally S=
.66W + 42%
1.29 1.29 1.31 tested immediately before the trip system containing the failure is tripped.
S=.66W + 43%
1.30 1.30 1.31 The trip system containing the unsafe failure may be placed in the untripped S=.66W + 44%
1.34 1.34 1.34 ndition during the period in which surveillance testing is being performed on the other RPS channels.
E. Verification of the limits set forth in specification 3.1.B shall be per-formed as follows:
1.
The average scram time to notch position 38 shall be: TAVEb UB 2.
The average scram time to notch position 38 is determined as follows:
n n
TAVE" i=1 i=1 Amendment No. f4I, }A',)MI where:n = number of surveillance tests 31 performed to date in the cycle, N1
=
number of active rods measured in
Figure 3.1-2 Operating Limit MCPR Versust (Defined in Section 3.1.B.2)
FOR ALL FUEL TYPES 1
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-1.41 l
1.40 -
_1,40
-1.38 (0.87,1.351)
C 1.35 (0.40,1.338) go
- 1.35 a:
SO "1 C
x vg
- 1. 31 -
3 1.30-
- 1.30 m 1.29 -
goc 2 (0.71,1.290) 0e o
1.25 -
-1 25 2i.24 1.20 -
- 1.20 l
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0.0 0.5 1.0 I
Amendment No.
47b
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3.5;, cont'd)l 4.5 (cont'd)
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condition,.that pump shall'be considered 2.
Following(any period where the'LPCI inoperable for purposes satisfying Speci-subsystems:or core spray subsystems fications 3.5,A, 3.5.C, and 3.5.E.
have not been required to be operable, the discharge piping of the inoperable system shall be vented.from the high H.
Av,erage Planar. Linear Heat Generation Rate point prior to the return of_the system (APLHGR) to service.
The.APLHGR for each type-of fuel as-a 3.
Whenever the HPCI, RCIC, or Core function of average planar exposure shall.
Spray. System is lined up to take not exceed the limiting value shown in suction from the condensate storage l
Figures 3.5-9 through 3.5-11.
If anytime tank, the discharge piping of the during reactor power operation greater HPCI, RCIC, and Core Spray shall than 25% of rated power.it is determined be vented.from the high point of that the limiting value for APLHGR is the system, and water flow observed being exc'eded, action.shall then be on a monthly basis.
e initiated within-15 minutes ~to restore operation to within the. prescribed limits.
4.
The level switches located on the If the:APLHGR 'is'not returned to.within Core Spray and RHR System discharge the. prescribed limi~ s; within two? (2) hours, piping high points which monitor c
an orderly reactor power reduction shall be
'these. lines to insure they are full commenced immediately.. The reactor. power shall be functionally tested each shall be reduced to less thanJ25% of rated
- month, power within the next four hours, or until the APLHGR is returned to within the' pre-H. Average Planar Linear Heat-Generation Rate scribed limits.
(APLHGR)
The APLHGR for each type of fuel as a function of average planar exposure shall be determined daily during reactor operation at 1 25% rated thermal power.
AmendmentNo.pI,p[,
123 6
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'JAFNPP:
3.5 BASESf(cont'd)-
requirements:for-the' emergency diesel assembly at any' axial' location =and.is onl'y
' generators.
dependent. secondarily on the rodito rod power distribution within.an assembly.
G.-
Maintenance of Filled' Discharge Pipe
.Since expected' local-variation.in power dis-s tribution within'a. fuel assembly affect the HIf the discharge piping of the' core ~ spay,-
calculated peak clad temperature by less
'LPCI,1RCIC, and HPCI are not filled, a than.1 20*F relative to t peak tempera-water hammer can develop in this piping ture for a typical-fuel design, the limit when the pump (s) are started. -To mini-on the average linear heat generation mi'ze damage to'the' discharge piping and rate is sufficient to assure that calculated to ensure added margin in the operation temperatures are within the 10 CFR 50 of'thesessystems, this technical speci-Appendix K limit.
The limiting value for fication' requires'the discharge lines APLHGR is shown in Figure 3.'5-6 through 3.5-11.l to be filled whenever the system is required to be operable.
If a discharge I.
Linear Heat Generation Rate (LHGR) pipe is not filled, the pumps that supply ~that'line~muso be. assumed to be This specification assures that the linear inoperable for technical specification heat generation-rate in any rod is less than
. purposes...However, if a water hammer the design linear heat generation.
w'ere to occur, the system would'still perform its design function.
The LHGR shall be checked daily during reactor operation at -]L 25% rated thermal power to H.
Average Planar Linear Heat Generation Rate determine if fuel burnu, or control rod move-(APLHGR) ment, has caused changes in' power distribution.
For LHGR to be a limiting value below 25%
This specification assures that.the peak rated thermal power, the ratio of local LHGR cladding temperature following the post-to average LHGR would have to greater than 10 ulated design basis loss-of-cololant acci-which is precluded by a considerable margin dent will not exceed the limit specified ehen employing any permissible control rod in 10 CFR 50 Appendix K.
pattern.
l The peak' cladding temperature.following a postulated loss-of-coolant accident is j
primarily a function of the average heat generation rate of all the rods of a fuel I
l Amendment No.-
130
JAFNPP Figure 3.5-6 i
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135d
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Amendment No. 37, M 135f i
JAFNPP Figure 3.5-11 13 _
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5 10 15 20 25 30 35 40 Planar Average Exposure (GWD/t)
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Planar Average Exposure
Reference:
NEDO-21662-2 (As Ammended December 1984)
Amendment No.
1351