ML20127D784
| ML20127D784 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/02/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20127D790 | List: |
| References | |
| DPR-59-A-088 NUDOCS 8505170022 | |
| Download: ML20127D784 (12) | |
Text
'. p erf UNITED STATES
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g NUCLEAR REGULATORY COMMIS510N l
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. POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated January 16, 1985, as supplemented April 8,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (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 application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 t.
comon 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.
2.
Accordingly, the license is amended by changes to the Tectinical
[
Specifications as indicated in the attachment to this license l
amendment and paragraph 2.C(2) of Facility Operating License No.
l DPR-59 is hereby amended to read as follows:
I 8505170022 850502 PDR ADOCK 05000333 P
. l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, 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 REGULATORY COMMISSION
~
lomenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 2, 1985 i
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 i
Revise the Appendix "A" Technical Specifications as follows:
-Remove Insert vii vii 31 31
-47b 47b 123 123 130 130 135d
-135d 135e 135e 135f 135f 1351 s
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I i
l LIST OF FIGURES FIGURE TITLE PAGE 3.1-1 Manual Flow Control 47a
'3.1-2 Operating Limit MCPR versus TI 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 3.5-6 (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-III MAPLHGR Versus Planar Average Exposure 135i l Reload 6, BP8DRB299 I
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 6.2-1 Plant Staff Organization 260 Amendment No. M, )8f, g, fr(, g, )( 88 vil
JAFNPP 3.1 (CONTINUED)
MCPR Operating Limit for Incremental Cycle Core Average Exposure C. MCPR shall be determined daily during reactor power operation at 1 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 EOC-2GWD/t EOC-lGWD/t to EOC that would cause operation with a limiting control rod pattern as described in the 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 1s34 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: TAVEI UB 2.
The average scram time to notch position 38 is determined as follows:
n n
AVE" l
i=1 i=1 Amendment No. f4', JAf,;Hf 88 where*n = number of surveillance tests 31 performed to date in the cycle, Ni =
number of active rods measured in e
l Figure 3.1-2 l
Operating Limit MCPR Versus T (Defined in Section 3.1.B.2)
FOR ALL FUEL TYPES
(
- 1 41 1.40 -
-1.40
-1.38 (0.87,1.351) 1.35 -
a:
toc 1
%y ay
- 1. 31.
3 1.30-
- 1.30 E
- 1. 29 -
goc"7.
(0.71,1.290) w O
1.25 -
- 1.25
.i.24 1.20 -
- 1.20 I
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t AmendmentNo.g, 88 47b
s JAFNPP 3.5 (cont'd) 4.5 (cont'd) condition, that pump shall be considered 2.
Following any period wh*ere the LPCI inoperable for purposes satisfying Speci-subsystems or core spray subsystems
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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.
Average 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'eeded, action shall then be on a monthly basis.
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 limits within two (2) hours, piping high points which monitor 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 than 25% 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 l 25% rated _ thermal power.
Amendment No. pd, p[, )I 88 123 2s
1 i
JAFNPP 3.5 BASES (cont'd)
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requirements for the emergency diesel assembly at any axial location and is only 1
generators.
dependent secondarily on the rod to rod power distribution within an assembly.
I G.
Maintenance of Filled Discharge Pipe Since expected local variati n in power dis-9 i
tribution within a fuel assembly affect the If the discharge piping of the core spay, calculated peak clad temperature by less i
LPCI, RCIC, and HPCI.are not filled, a than i 20*F relative to the 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 mize 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 these systems, 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 must 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.
were to occur, the system would still perform its design function.
The LHGR shall be checked daily during reactor operation at 1,25% rated thermal power to H.
Average Planar Linear Heat Generation Rate determine if fuel burnup, or control rod move-i (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.
The peak cladding temperature following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel e
Amendment No. 88 130 l
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JAFNPP Figure 3.5-6 i
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t Amendment No.
[ 88 135d
JAFNPP Figure 3.5-7 0
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(This page intentionally blank.)
J Amendment No. Jif, f( 88 135e
JAFNPP Figure 3.5-8 1
1 (This page intentionally blank.)
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Amendment No. fr, g 88 135f
JAFNPP t
i Figure 3.5-11 13 -
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Planar Average Exposure (GWD/t) i Maximum Averaqa Planar Linear Heat Generation Rate (MAPLIIGR)
Versus Planar Average Exposure i
Reference:
NEDO-21662-2 (As Ammended December 1984)
Amendment No. 88 1351
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