ML20100Q498
| ML20100Q498 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/09/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100Q502 | List: |
| References | |
| NUDOCS 9203170195 | |
| Download: ML20100Q498 (13) | |
Text
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S, UN11 ED STATES
/ j NUCLE AR REGULATORY COMMISSION j
nsmuoros o c mss
.....f EQ Fp AUTHORITY OF THE STATE OF NEW YORK W
QQCKET NO. 50-333 JAMES A. FITZPATRICK NUfLEAR POWER PLANT AMENDMfNT TO FA 1LITLQPERATING LICENSE Amendment No.179 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated January 9,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the-Act) and the Commissica'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 (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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common Jcn <se and security or to the health and safety of the public; and he,ssuance of this amendment is in accordance with 10 CFR Part
. the Commission's regulations and all applicable requirements O
! w. been satisfied.
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-59 is hereby amended to read as follows:
4 9203170195 920307 PDR ADOCK 05000333 P
p 1
(2) Technical SE.C.ifications Tha Technical Specifications contained in Appendices A and B, as revised through Amendment No.179, are hereby inccrporated 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
fy]
Robert A. Capra, Director Project Directorate I.1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 1992
s.
ATTACHMENT TQ_ LICENSE AMENDMENT NO.179 FACILITY OPERAT![lG LICENSE NO. DPR-59 00CKET NO, 50-333 Revise Appendix A as follows:
Remove Paoes Insert Paaes
!}3 118 i
120 120 121 121 137 137 138 130 139 133 143 143 148 148 149 149 150 150 1
b
't E
?
L:
JAFNPP 3.5 (cont'd) 4.5 (cont'd) a.
From and after the date that the HPCI System is a.
When it is deterraned that the liPCI subsystem is made or found to be inoperable for any reason, anoperable the FCIC, ite LPCI sutnystem, both core continued reactor operation is perrnssible only spray subsystems, and the ADS subsystem during the succeedwig 7 days utdess such system is actuation logic shall be venhed to be operabe
_ anediately. The RCIC system and ADS subsystem sooner made operable, provided that during such 7 w
days all actrve wnsponents of the - Automatic logic Aall be verited to be operable dasiy thereaP.er.
Depressurization System, the Core Spray System, LPCI System, and Reactor Core isolation Coolwig System are operable.
b.
If the requirements of 3.5.C.1 cannot be met, the reactor shall be placed in the cold conddKrs and pressure less than 150 psig within 24 hrs.
2.
Low power physics testing and reactor operator trainirg shall be perrntted with reactor coolarf. temperature
<2127 with an inoperable component (s) as specified in 3.5.C.1 above.
3.
The HPCI system is not required to be operable during hydrostatic pressure and leakage testing with reactor coolant temperatures between 2127 and 3007 and irradiated fuel in the roactor vessel pronded all control rods areinsertod.
Ame wjment No.
,1 7,14,'I8, 179 j4
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-7
+-e*
JAFNPP 3.5 (cont'd) 4 S (cont'd) duiing such time. the HPCI System is operable.
2.
If the requirements of 3.5.D.t canno: be rnet, the reactor 2.-
Alogic systemitaxiional test.
shall be placed in the cold condition and pressure less than 100 psig, within 24 hr.
- a.
When it is determiswd that one valve of the ADS is inoperable, the ADS subsystem actuation logc fcx the operable ADS valves and ite HPCI subsystem shall be venfied to be operable immediately and at least weekly thereafter.
b.
When it is delem*wd that more than one relief / safety valve of the ADS is inoperable, the HPCI System shall be venfied to be operable immediately.
3.
Low power physics testing and reactor operator training shall be. permitted with enoperable components as specified in 3.5.1.a and 3.5.1.b above, provided that reactor coolant tempeeature is <212"F. and the reactor vessel is vented or reactor vessel head is removed.
4.
The ADS is not required to be operable during hydrostatic pressure and leakage testing with reactor coolant temperatures between 212"F and 30(TF and irradiated fuel in the reactor vessel provided all control rods are inserted.
Amendment f40.
,'1 8,179 r
120 m
..i AFN PP 3.5 (Cont'd) 4.5 (Cont'd)
E.
Reactor Core isolation Cooling (RCIC) System E.
Reactor Coro isolation Coohng (RCIC) System 1.
The RCIC System shal1 be operable wtenever there is 1.
RCIC System testing shall be performed as follows irradiated fuel in the reactor vessel and the reactor provided a reactor steam supply is avaitable. If steam is pressure is greater than 150 psig and reactor coolant not availabio at the time the survesitance test is scheduled temperaturo is greator than 2tTF except fiam the time to be performed, the test shall be performed within ten e
that the RCtC System is made or found to bo inoperabio days of continuous operation from the time st:,am for any reason, continued reactor power operation is becomes available.
permissible during the succeeding 7 days ur%ss the llem Frequency system is made operabio oartier provided tha' during these 7 days the HPCI Systomis operab;o.
a.
Simulated Automatic,
Once/ operating 2.
ll the requirements of 3.5.E cannot be met, the reacto-Actuation (and Restart )
cycle shall be placed in the cold condition and pressure less Test than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b.
Pump OperabiMy Once/ month 3.
Low power physics testing and reactor operator training c.
Wim Opmated he/ month LI all be permitted with inoperablo components as valvo Operability specified in 3.5.E.2 abeve, provided that reactor coolant tanpmatwo is 12E d.
Flow Rate Once/3 months 4.
The RCIC system is not required to be operablo during e.
Testable Check Tested for operabihty hydrostatic pressure and leakage testing with reactor V
sem h coolant temocratures between 21TF ard 300*F and irradiated fuel in the reactor vessel provided all controf exceeding 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />, if rods at0 insetod.
operability tests have not been performed during the preceding 31 days.
f.
Logic Sysicm Once/ operating Fonctional Test cycle Automatic rutart on a low water Icvel signal wtsch is Amendment No.
,t
,1
), 179 subsequent to a tigh water level tiip.
4 e
JAFNPP 3.6 (cont'd) 4.6 (cont'd) a.
<2GF when to the left of curve C.
b.
< 100T when on or to the right of curve C.
4 Spx:ifications 3.5.C 3.5.D. 3.5.E and 3.6.E which would become effective because of an increase in reactor coolant temperature above 2127 or pressures above 100 and 150 psig are not required while conducting the RCS hydrostatic pressure and leakage tests between 2127 and 307F provided all control rods are fully inserted.
3.
Non-Nuclear Heatup and Cooldown 3.
Non-Nuclear Heatup and Cooldown During heatop by non-nuclear means (mechanica!),
Ouring heatup by Non-Nuc: ear means, cooldown following cooldown following nuclear shutdown and low power nuclear shutdown and low power physics tests, the reactor physics tests the Reactor Coolant System pressure and coolant system pressure and temperature stut! be temperature shall be on or to the right of the curve B recorded overy 30 nunutes until two consecutive shown in Figure 3.6-1 Part 1,2, or 3 and the maximum temperature readings are wittun ST of each other.
temperature change during any one hour shall be < 1007.
4.
Core Critical Operation 4.
Core Critical Operation During all modes of operation with a critical core (except Dunng all rnodes of operation with a critical core (except for low power physics tests) the reactor Coolant System for low power physics tests) the reactor Coolant System pressure and temperature shall be at or to the right of the pressure and temperature shall be recorded within 30 curve C shown in Figure 3.6-1 Part 1, 2 or 3 and the minutes prior to withdrawal of control rods to bring the maximum temperature change during any one hour shall reactor critical and every 30 minutes during heatup untd be < 100T.
two consecutive temperature readings are within 57 of each other.
i l
1,13,If,179 l
Amendment No. " J, r
137
.J
JAFNPP 3 G (cont'd) 4.G (cont'd) l S.
With any of the limits of 3.GA1 through 3.6A4 above 5.
Not Used I
exceeded, cia.'r r
l a.
restore the temperature and/or pressure to within
~
g the limits within 30 minutes, perform an engineering r
evaluation to determine the effects of the out-of limit condition on the structural integrity of the reactor coolant system, and determine that the reactor coolant system remains acceptable for continued operations; or b.
be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.
idle Recirculation Loop Startup 6.
Idle Recirculation Loop Startup When Reactor Coolant System temperature is > 1407 an Within 30 miretes prior to startup of an idle locp:
idic recirculation loop shall not be started unless:
a.
The temperature differential between the reactor a.
The differential temperature between the reactor coolant system and the reactor vessel bottom head coolant system and the reactor vessel txyttom head drain line is 51457, and drain line shall be recorded, and b.
When both foops are idle, the temperature difference b.
When both loops are idle, the differential between the reactor coolant system and the idle temperature between the reactor coolant system loop to be started is1507, or and the idio loop to be started shall be recorded, or c.
When only one loop is idle, the temperature c.
When only one loop is idle, the temperature difference between the idle loop and the operating differential between the idle loop and the operating loop is $ 50T.
loop shall be recorded.
Amendment No.
3, 179 138
JAFNPP 4.6 (cont'd) 3 6 (cont'd) 7.
Reactor Vessel Flux Monitoring l
The reactor vessel Flux Mordtoring Surveillance Program complies with the intent of the May,1983 r6 vision to 10 l
I CFR 50, Appendices G and H. The next flux monitonng surveittance capsule shall be removed after 15 effective full power years (EFPYs) and the test procedures and
/
reporting requirements sha!! meet the requirements of l
ASTM E 185-82.
l I B.
Ocleted B.
Deleted l
C.
Coolant Chemistry C.
Coolant Chemistry A samp!e of reactor coolant shat! be taken at least f
l 1.
The reactor coolant system radioactivity concentration in 1.
a.
l water shall not exceed the equi!!brium value of 3.1 pCi/gm every 96 hr and analyzed for gross gamma activity.
of dose equivalent 1-131 This limit may be exceeded, b.
Isotopic analysis of a sample of reactor coolant sha!!
fotrowing a power transient, f.v a maximum of 48 hr.
be made at least once/ month.
During this rodine activity transient the sodine A sample of reactor coolant shall be taken prior to concentrations shall not exceed the equilibrium limits by c.
more than a factor of 10 whenever the main steamline startup and at 4 hr interva!s during startup and l
l isofation valves are open. The reactor shall not be analyzed for gross gamma activity.
l operated more than 5 percent o' its annual power d.
During plant steady state operation and following an operation under this exception to the equilibrium limits. If offgas activity increase (at the Steam Jet Air the sodine concentration exceeds the equilibrium limit by Ejectors) of 10,000 pCl/sec within a 48 hr. period or more than a factor of 10, the reactor shall be placed en a a p level % of 120 ment of fd rated cold condition within 24 hr.
m WW aQs sM M t&en and analyzed for gross gamma ac'ivity. At least three sampics wi!I be taken at 4 hr intervals. These sampling reqtirements may be omitted whenever the equilibrium I-131 concentration in the reactor coolant is less than 0.007 pCi/ml.
Amendment rJo. 179 139
- F
- s n
w
~
JAFNPP L
I
. 3.6 '(cont'd) 4.6 (cord'd)
~
1 2.
- 2. '
. At least one salety/ relief valve shall be disassembled and -
mspected once/ operating cycle.
a.
From and after the date that the safety valve function
{
of one sdety/ relief valve is made or found to be >
n j:
inoperable.- continued operation is perrrassable only.
- dusing the succi-ding 30 days unless such valve is <
p made operable sooner.
b.
From and after the time that the safety valve function
]'
on two safety / relief valves is made or found to be moperable, ' continued. reactor operation is t
perrrussible only dunng ' the. mermeding 7 days unless such valves are sooner made operable.
I
[:
The integrity of the rutrogen system and components j;
3.
If Specification 3.6.E.1 and 3.6.E2 are not met, the reactor 3.
shall be placed in a cold condition withm 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
wnich provido manual and ADS actuahon. of the f
safety /relef valves shall be demonstrated at Icast once
[
every 3 months.
t i
4.
Low power physics testing and reactor operator trammg 4
Art annual report of safety /refel vave failures and shall be permitted -with inoperable components as ctsallenges will be sent to the,NRC in accordance with speedied in item 82 above, provided that reactor coolant Section 6.9.A2.b.
l temperature is <212*F and the reactor vessel is vented or I
the reactor vessel head is removed.
i 5.
The Safety and Safety / Relief Valves are not required to be
[
r;perable during hydrostatic pressure and leakage testing with reactor coolant temperatures between' 212*F and 3007 and inadiated fuel in the reactor vessel provkkd all '
.j control rods are inserted.
j i
Amendment No.
,t
,1
,179 143
[
l I
a
[
s
, ~ _..
+
3.6 and 4.6 BASES (cont'd)
Fig. 3.G-1, curve B, provides limitations for plant heatup and operable when reactor pressure c>cceds 150 psig and 212"F.
coo!down when the reactor is not critical or during low power HPCI and RCIC cannot t>e made operable during the test physics tests. The thermal limitation is based on maxhnum because piping normally fi2 fed with steam es felled with water heatup and cooldown rates of 100"F/hr in any one-hour pericd.
during the test.-
Fig. 3.G-1, curve C. estab;ishes operating limits when core is Hydrostatic and leakage tests sfdl be terminated before the critical. These finn:s include a margin of 40"F as required by 10 reactor coolant temperature exceeds 300"F. This temperature CFR 50 Appendix G.
limit is based on providing a 50"F band for operating f!cxibility between the 300"F limit and the highest estimated minimum The requirements for cold boltup of the reactor vessel closure testing temperature at 32 EFPY (approximately 250"F) are based on NDT temperature plus a 60"F factor of safety. This factor is based on the requirements of the ASME Code to which The protection provided by LCOs applicablo during cold the vessel was built. For Fig. 3.6-1, curves A, B and C, margiris shutdown plus the requirement that all control rods be fully are only a& led to the low temperature portion of the curve wheru inserted are adequate to ensuro protection of public health and non-ductilo failure is a concem. The c!osure flanges have an safety. The hydrostatic test is performed once every to years NDT temperaturo not greater than 30"F ard are not subject to while the leakage test is performed after each refueling wten any appreciable neutton radiation: exposure. Therefore, the conditions are similar to cold shutdown (i e, after the reactor has minimum temperature of the flanges when the s!uds are in been shutdown and decay heat and the energy stored in the tension is 30"F plus 60"F, or 90"F.
core is very low). The consequences of accidents (small and large break LOCAs, MSLB, etc_) are bounded by ardyses that Specification 3.6.A2 identifies four LCOs that beccmo effectivo assume fo; power operation. Specification 3.5_A requires the with increased reactor coolant temperature or pressure but are low pressure ECCS systems to be operable. Specifications not in effect during the hydrostatic and leakage tests. This is 3.7.A. 3.7.8 and 31.C reauire the containment SGTS and necessary because, as reactor fluence increases, the minimum secondary contaenment to be operable. Spocifications 32.A.
test temperature and pressuro rises into ranges nomWly 3.2.B and Appendix B, Specification 3.8 require instrumentat%
associated with startup or hot shutdown. RCS pressure and that initiate containmant, low pressure ECCS, SBGT and temperature are used throughout the Technical Specifications as secondary containment be operabic. Emergency power is a basis for establishing plant morto and system operability required by Specification 3.9.B.
requirements. Some LCOs and restrictions cannot be satisfied during the test at elevated temperatures. For exampio, Specifications 3.5.C.1 and 3.5 E.1 require that HPCI and RCIC be Amendment No. ' 3. 1 3. I 79 148
JAFNPP 3 6 and 4 G BASES (cont'd) annunciating at appropriate concentration levcis such that D.
Octeted sampling for isotopic analysis can be initiattd. The design details of such a system must be submitted for evaluation and C.
Coolant Chemistry accepted by the Commission prior to its impfentntation and incorporation in these Technical Specifications.
A radioactivity concentration limit of 20 Ci/mi total iodine can be reached if the gaseous cifluents are near the limit as set Since the concentration of radioactivity in the reactor coolant is forth in Radiological Effluent Technical Specification Section not continuously measured, coolant sampling would be 3.2.a if there is a failure or a prolonged shutdown of the ineffective as a means to rapidly detect gross fuel element cleanup demineraiiter.
failures. However, some capability to detect gross fuel element failures is inherent in the radiation monitors in the offgas In the event of a steam line rupture outside the drywell, with this system and on the main steam !ines.
coolant activity level, the resultant radiological dose at the site boundary would be 33 rem to the thyroid, under adverse Materials in the Reactor Coolant System are primarily 304 meteorological conditions assuming no more than 3.1 pCi/gm stainless steel and Zircatoy fuel cladding. The reactor water of dose equivalent I-131. The reactor water sample will be used chemistry limits are established to prevent damage to these to assure that the limit of Specification 3.6.C is not exceeded.
materials. Limits are placed on chievide concentration and The total radioactive iodine activity would not be expected to conductivity. The most important limit is that placed on change rapidly over a period of 96 hr. In add: tion, the trend of chloride concentration to prevent stress corrosion cracking of the stack offgas release rate, which is continuously monitored, the stainless steel. The attached graph, Fig. 4.6-1, illustrates is a good indicator of the trend of the iodine activity in thn the results of tests on stressed 304 stainless steel specimens.
reactor coolant. Also during reactor startups and large power Failures occuned at concentrations above the curve; no changes which could affect iod:ne levels, samples of reactor failures occurred at concentrations below the curve According coolant shall be analyzed to insure iodine concentrations are to the data, a!!cwable chloride concentrations could be set j
below allowable levels. Analysis is required whenever the I-13t several orders of magnitude above the established limit, at the concentration is within a factor of 100 of its allowable oxygen concentration (0.2-0.3 ppm) experienced during power equilibrium value. The necessity 'or continued sampling operation. Zircaloy does not exhibit similar stress corrosion i
following power and offgas transients will be reviewed within 2 failures.
years of initial plant startup.
However, there are various conditions under which the The surveillance requirements 4.6.C.1 may be satisfied by a dissolved oxygen content of the reactor coolant water could be continuous monitonng system capabfe of determining the total higher than 0.2-0.3 ppm, such as eefueling, reactor startup, and
{
iodine concentration in the coolant on a rea! time basis, and hot standby. During these periods with steaming rates less Amendment No.
179 149 3..
JAFNPP 3 G and 4.6 BASES (cont'd) than 100,000 lb/hr, a more restrictive limit of 9.1 ppm has been startup periods, which are in the category of less than 100,000 established to assure the chloride-oxygen combinations of Fig.
Ib/hr, conductivity may exceed 2 pmho/cm because of the initial 4.61 are not exceeded. At steaming rates of at least 100,000 evolution of gases and the initial evolution of gases.and the initial Ib/hr, boihng occurs causing deacration of the reactor water, addition of dissolved metals. During this period of time, when thus maintaining oxygen concentration at low levels.
the conductivity exceeds 2 pmho/cm (other than short. term spikes), samples will be taken to assure the chloride When conductivity is in its proper normal range, pH and chloride concentration h less than 0.1 ppm.
and other impurities affecting conductivity must also be within their normal ranges. When and if conductivity becomes The conductivity of the reactor coolant is continuously abnormal, then chloride measurements are made to determine monitored. The samples of the coolant which are taken every 96 whether or not they are also out of their normal operating values.
hr will serve as a reference for calibration of these monitors and This is not necessarily the case. Conductivity could be high due is considered adequate to assure accurate readings of the to the presence of a neuiral salt; e.g., Na SO, which would not monitors. If conductivity is within its normal range, chlorides and 2
4 have an eftect on pH or chloride. In such a case, high other impurities will also be within their normal ranges. The conductivity alone is not a cause for shutdown. In some types of reacic coolant samples will also be used to deterntne the water-cooled reactors, conductivities are, in fact, high due to chlorides. Therefore, the sampling frequency is considered purposeful addition of additives. In the case of BWR's, however, adequate to detect long-term changes in the chloride ion where no additives are used and where neutral pH is maintained, content. Isotopic analyses of the reactor coolant required by condunivity provides a very good measure of the quality of the Specificction 4.6.C.1 may be performed by a gamma scan.
reac'sr water. Significant changas therein provide the operator with a waming mechanism so he can investigate and remedy the condition causing the change before limiting conditions, with D.
Coolant Leakage respect to variabits affecting the boundaries of the reactor coolant, are exceeded. Methods availabic to the operator for Allowable leakage rates of coolant from the Reactor Coolant correcting the condition include operation cf the Reactor System have been based on the predicted and experimentalFf Cleanup System, reducing the input of impurities and placing the observed behavior of cracks in pipes and on the ability to make reactor in the cold shutdown condition. The major benefit of up Reactor Coolant System leakage in the event of loss of off-cold shutdown is to reduce the temperature dependent site a-c power. The normally expected background leakage due corrosion ratos and provide time for the Reacter Water Cleanup to equipment dcsign and the detection capability for determining System to reestabbsh the purity of the reactor coolant. During system Amendment No. 179 150 e
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