ML20209D890
| ML20209D890 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/02/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20209D896 | List: |
| References | |
| DPR-50-A-120 NUDOCS 8609090510 | |
| Download: ML20209D890 (15) | |
Text
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UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION 5
l WASHINGTON, D. C. 20555
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METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No.120 License No. DP.R-50 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al. (the licensees) dated July 16, 1986, 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; 3
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 endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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.
l MS' in!A ME$$9 P
. 2.
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 Operating License No. DPR-50 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.120, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR PEGULATORY COMMISSION oh b @F. Stolz, Direc PW$ProjectDirector e #6 D nision of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: September 2, 1986
ATTACHMENT TO LICENSE AMENDMENT N0.120 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert vii vii 2-3 2-3 3-34a 3-34a 3-35 3-35 3-35a 3-35a
-- 35b Figure 2.1-2 Figure 2.1-2 I
Figure 2.3-2 Figure 2.3-2 Figure 3.5-2E Figure 3.5-2E Figure 3.5-2F Figure 3.5-2F Figure 3.5-2H Figure 3.5-2H Figure 3.5-21 E
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[3 L!$T OF FIGURES Ffoure 71t]1,e,e t.1-1 TMI-1 Core Protection Safety Limit 2.1-2 TMI-1 Core Protection Safety Limits 2.1-3 TMI-1 Core Protection Safety Bases 2.3-1 TMI-1 Protection System Maximum Allowable set Points i
2.3-2 Protection System Maximum Allowable Set Points for Reactor Power i
Imbalance, TMI-1 1
3.1-1 Reactor Coolant System Heatup/Cooldown Limitations (Applicable to 5 EFPY)
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3.1-2 Reactor Coolant System, Inservice Leak and Hydrostatic Test
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Limitations (Applicable to 5 EFPY) 3.1-3 Limiting Pressure vs. Temperature Curve for 100 STL cc/ Liter HO' 2
3.5-2A Rod Position Limits for 4 Pump Operation from 0 to 125 2 5 EFPD, THI-1
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3.5-28 Rod Position Limits for 4 Pump Operation from 125 2 5 EFPD, TMI-I
- 3. 5-2D Rod Position Limits for 2 and Y Pimp Operation from 1252 5 EFPD to E0C, TMI-1 3.5-2E Power Imbalance Envelope for Operation from 0 EFPD to 250 + 10 EFPD l
3.5-2F
.Pnwd Imbalance Envelope for Ooeration after 2501 10 EFPD i
i 3.5-26 LOCA Limited Maximum Allowable ' Linear Heat TMI-1 l
l 3.5-2H APSR Position Limits for Operation from 0 EFPD to 250 + 10 EFPD l
3.5-2I APSR Position Limits for Operation After 250+ 10 EFPD-t 3.5-1 Incore Instrumentation specification Axial Imbalance Indication.
TMI-1 3.5-2 Incore Instrumentation specificat'fon Radial Flux Tilt Indication, TMI-1 3.5-3 Incom Instrumentation Specification 3.11-1 Transfer Path to and from Cask Loading Pit 4.17-1 Snubber Functional Test - Sample Plan 2 5-1 Extended Plot Plan TMI Amenneents nos.11,11, n, n, N, n, n, v11 M FM, M9,120
-. J :L
The curve of Figure 2.1-1 is the most restrictive of all possible
'1 reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-2.
The curves of Figure 2.1-3 represent the conditions at which a minimum DNBR of 1.3 is predicted at the 4
thermal power for the number of reactor coolant maximum possible pumps in operation or the local quality at the point of minimum i
DNBR is equal to 22 percent, (3) whichever condition is more restrictive.
The maximum thermal power for three pump operation is 89.36 percent due to a power level trip produced by the flux-flow ratio r
(74.7 percent flow x r.08 = 40.67 percent power) plus the maximum calibration and instrumentation error.* The maximum thermal power i
for other reactor coolant pump conditions is produced in a similar manner.
Using a local quality limit of 22 percent at the point of minimum j
DNBR as a basis for curve 3 of Figure 2.1-3 is a conservative criterion even though the quality at the exit is higher than the i
quality at the point of minimum DNBR.
l f
The DNBR as calculated by the S&W-2 correlation continually increases from the point'of minimum DNBR, so that the exit DNBR j
is always higher and is a function of the pressure.
For each curve of Figure 2.1-3, a pressure-temperatura point above and to the left of the curve would result in a DNBR greater l
than 1.3 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation.
Curve 1 is more restrictive than any other reactor coolant pump situation because any pressure / temperature point above and to the left of this curve will be above and to the left l
of the other curves.
l REFERENCES (1)
FSAR, Section 3.2.3.1.1 (2)
FSAR, Section 3.2.3.1.1.c j
(3)
FSAR, Section 3.2.3.1.1.k l
l Amendment No. 17, 29, 39, p, 120 2-3
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2.
The control rod group withdrawal limits (Figures 3.5-2A, 3.5-2B, 3.5-20, 3.5-2D, 3.5-2H, and 3.5-2I) shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit.
3.
The operational imbalance limits (Figures 3.5-2E and 3.5-2F) shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit.
f.
Except for physics or diagnostic testing, if quadrant tilt is in excess of +16.80% determined using the full incore detector system (FIT), or +: 9 5Q% determined using the minimum incore detector system (MIT) if the FIT is not available, or +14.2($
determined using the out of core detector system (OCT) when neither the FIT nor MIT are available, the reactor vill be placed in the hot shutdown condition. Diagnostic testing dur-ing power operation with a quadrant tilt is permitted provided that the thermal power allovable is restricted as stated in
~
3.5.2.h.d above.
g.
Quadrant tilt shall be monitored on a minimum frequency of once every'two hours during power operation above 15 percent of rated power.
i e
Amendment No. 29, 38, 39 AD, AE, 3-34a 50, 120
-.,n.
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3.5.2.5 Control Rod Positions a.
Operating rod group overlap shall not exceed 25 percent 5 percent, between two sequential groups except for physics tests.
b.
Position limits are specified for regulating and l
axial power shaping control rods.
Except for l
physics tests or exercising control
- rods, the regulating control rod insertion / withdrawal limits are specified on Figures 3.5-2A and 3.5-28 for four pump operation and Figures 3.5-2C and 3.5-2D three or two pump operation.
Also excepting physics tests or exercising control rods, the axial power shaping control rod insertion / withdrawal limits are i
specified on Figures 3.5-2H and 3.5-2I.
If any of l
these control.-rod position limits are exceeded, l
corrective measures shall be taken immediately to achieve an acceptable control rod position.
Acceptable control rod positions shall be attained within four hours.
c.
Except for physics
- tests, power shall not be increased above the power level cutoff of 92 percent i
of rated thermal power unless one of the following conditions is satisfied:
1 5
l 1.
Xenon reactivity never deviated more than 10 l
percent from the equilibrium value for operation l
at 100 percent of rated thermal power.
l 2.
Xenon reactivity deviated more than 10 percent l
and is now within 10 percent of the equilibrium j
value for operation at 100 percent of rated j
thermal power and asymptotically approaching stability.
3.
Except for Xenon free startup (when 3.5.2.5.c.2 applies) the reactor has operated within a range of 87 to 92 percent of rated thermal power for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the soluble poison control mode.
d.
Core imbalance shall be monitored on a minimum frequency of once every two hours during power operation above 40 percent of rated power.
Except for physics tests, corrective measures (reduction of imbalance by APSR movements and/or reduction in j
i reactor power) shall be taken to maintain operation j
within the envelope defined by Figures 3.5-2E and l
3.5-2F.
If the imbalance is not within the envelope j
defined by Figures 3.5-2E and 3.5-2F, corrective measures shall be taken to achieve an acceptable imbalance.
If an acceptable imbalance is not
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Amendment No. JS, J7, 29, 35, 39, 50,120~'
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a achieved within four hours, reactor power shall be reduced until imbalance limits are met.
safety rod limits are given in 3.1.3.5.
e.
3.5.2.6 The. control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent.
i 3.5.2.7 A power map shall be taken at intervals not to exceed 30 effective full power days using the incore instrumentation detection system to verify the power distribution is within the limits shown in Figure 3.5-2G.
BREAR The power-imbalance enveiope defined in Figures 3.5-2E and 3.5-2F l
is based on IDCA analyses which have defined the maximum linear heat rate (see Figure 3.5-2G) such that the maximum clad temperature will not exceed the Final Acceptance Criteria (2200F).
Operation outside of the power imbalance envelope alone does not constitute a situation that would cause the Final Acceptance Criteria to be exceeded should a IDCA occur.
The power imbalance envelope represents the boundary of operation limited by the Final Acceptance Criteria only if the control rods are at the withdrawal / insertion limits as defined by Figures 3.5-2A, 3.5-28, 3.5-2C, 3.5-2D, 3.5-2H, 3.5-2I, and if quadrant l
l tilt is at the limit.
Additional conservatism is introduced by l
application of:
I a.
Nuclear uncertainty factors i
b.
Thermal calibraticn uncertainty c.
Fuel densification effects d.
Hot rod manufacturing tolerance factors a.
Postulated fuel rod bow effects The Rod Index versus Allowable Power curves of Figures 3.5-2A, 3.5-25, b 5-20, 3.5-2D, 3.5-2H, and 3.5-2I describe three regions.
9Ir.se three regions are:
1.
Permissible operating Region 2.
Restricted Regions 3.
Prohibited Region (Operation in this region is not allowed)
NOTE:
Inadvertent operation within the Restricted Region for a period of four hours is not considered a violation of a Amendment Ho 'J7, gs, 38, 39, 50,120 3-35a
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limiting condition for operation.
The limiting criteria within the Restricted. Region are potential ejected rod the$ and ECCS power peaking and since the probability of wo se accidents is very low especially in a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time frames, inadvertant operation within the Restricted Region for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed.
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3-35b l
Amendment No.120
Thermal Power Level, %
-120
(-34.81,112)
(112) 1 (38.52,112)
Acceptable
(-77.53,99.2) 4 pimp
-100 (50.9?.2)
Operation
(-34.81,89.36)
(89.36) 2 (38.52,89.36)
Acceptable
(-77.53,76.56) 344 Pump 80 (50,76.56)
Operation'
(-34.81.61.99)
(61.99) 3 (38.52,61.99)
" 60 Acceptable
(-77.53,49.19) 2,344' Pump (50,49.19)
Operation
- 40 1
- 20 l
l l
t t
t 1
i I
i 8
-80
-60
-40
-20 0
20 40 60 80 Reactor Power Imbalance, %
Curve Reactor Coolant Flow (Ib/hr) 6 1
139.8 x 10 6
2 104.5 x 10 6
3 68.8 x 10 TMI-1 Core Protection Safety Limits, Cycle 5 Figure 2.1-2 Amendment No. J7, 7), 33,. D, S, 120
- i...
Themal Power Level,1 "120
(-28.5.108)
. (108)
(27,108)
Mg =.5806 Acceptable M2 = -2.000 100 4 Pump (36,90)
(-59.5,90)
(80.67)
'peceptable 1344 Pump (M,62.67 )
(-59.5,62.67)
. 60 l
(53.13) ceptable 344 Pump
. 40 Operation (36,35.13)
(-59.5,35.13) gl "I
m 20 3
Nl 7
n n
n u
l r>
e
.~l i
-60
-40
-20 0
20 40 60 Reactor Power Imbalance, %
l l
TMI-1 Protection System Maximum Allowable l
l Setpoints for Reactor Power Imbalance, Cycle 5 l i
Figure 2.3-2 Amendment No.77, 79, 39, M, #, ES,120
Power,1 of 2535 MWt RESTRICTED REGION
- 110
-15,102 10.0,102 i
- 100 10.0,92 ai
-15,92
- 90
. 80,,10.0,80
~
-20,80 <
PERMISSIBLE OPERATING
- 70 REGION
- 60 I
- 50 i
" 40
- 30
- 20
- 10 t
i i
1 I
1 i
i
-50
-40
-30
-20
-10 0
10 20 30 40 50 Ax1al Power lealance, 5 Power 12 alance Envelope for Operation i
From 0 EFPD to 250 t10 EFPD, Cycle 5 Figure 3.5-2E Amendment No. //, 29, 39, fD, 50, 120
=
Power, 1 of 2535 m t
- 110
-25.102 10,102
-28,92 10,92 80 10,80
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-32,80 i
- 70 PERMISSIBLE RESTRICTED OPERATING
" 60 REGION l
REGION
- 50
- 40
- 30
- 20
- - 10 I
I i
1 t
n i
i t
-50
-40
-30
-20
-10 0
10 20 30 40 50 Axial Power 12 alance, 1 Power 12alance Envelope for Operation After 250 t 10 EFPD, Cycle 5 Figure 3.5-2F Amendment No. 17, 29, 39, 6, ED,120
4 45.0.102
,,6.1,102 RESTRICTED REGION
,6,1,92
< 45.0,92 90 57.9,80 80 4
0,80 100,70 70 a
E
)4 60 2
PERMISSIBLE OPERATING y
REGION 50 i.
' 40
[
30 l
20 10 1
I I
I I
I f
f f
0-10 20 30 40 50 60 70 80 90 to APSR, 5 Withdrawn APSR Position Limits for Operation From 0 EFPD to 250110 EFPD, Cycle 5,
Figure 3.5-2H l
l l
Amendment No. 27,39,40,#E,50,120
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100 90 m
70 E
W 60 M
APSR INSERTION NOT ALLOWED IN THIS TIME INTERVAL
==
50 i
40 30 20 10 I
a a
i i
i i
I I
0 10 20 30 40 60 60 70 80 90 100 APSR, 1 Withdrawn APSR Position Limits for Operation After 250 t 10 EFPD, Cycle 5 Figure 3.5-21 l
Amendment No. 120
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