ML20037B432
| ML20037B432 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-02-A-026, DPR-2-A-26) |
| Issue date: | 07/10/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037B431 | List: |
| References | |
| NUDOCS 8009260715 | |
| Download: ML20037B432 (9) | |
Text
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'o UNITED STATES 7, [,g E
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NUCLEAR REGULATORY COMMisslON g
E WASHING TON. D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-10 DRESDEN NUCLEAR POWER STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. DPR-2 1.
The Nuclear Regulatory Commission ~(the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated November 25, 1975, as supplemented April 15,1976, August 19, 1976, September 9,1977, and Octcber 18, 1977, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Conmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applichtion, the provisions of the Act, and the rules and regulations of the Conmission; 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 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 Connission's regulations and all applicable requirements have 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 License No. DPR-2 is hereby amended to read as follcws:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 26, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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. %v '~,.,.,c Dennis Ziemaq, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10,1978 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE N0. DPR-2
_ DOCKET NO. 50-10 Change the Technical Specifications contained in Appendix. A by removing the following pages and inserting the enclosed pages.
The revised page's are identified by the captioned amendment number and contain vertical lines indicating the area of change.
Remove Insert 65 65 66 66 71 i
.71 72 72 72A 73 73 l.
3.6 1.ltillIrlG COND1110t1 FOR OPERATION 4.6 ' SIIRVEll.l.ANCE. I!EQlllilDIENT 1.6 PI:ll!ARY 'SYSTI.f t I!OllNDARY 4.6 PRit!ARY SYSTE}! Il0UNDARY Appl I cab il i ty,:
Applicabillty:
Applies to the operating status of the reactor Applies to the periodic examination and testing coolant nystem.
requirements for the reactor coolant system.
j)hj cct ive:
Objective:
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10 assure the integrity and nafe operation of To determine the condition of'the reactor ti"t reactor coolant system.
coolant system and the operation of the safety devices related to it.
Specification:
Specification:
A'.
Thermal Limitations A.
Thermal I, imitations 1.
The average rate of reactor coolant temperature change during normal 1.
During heatups and cooldowns the heatup or cooldown shall not exceed following temperatures shall be 100*F/hr when averaged over a*one-permanently recorded at Icast every hour period.
15 minutes.
reactor v'essel shell 2.
The recirculation pump in an idle a.
recirculation 1;op shall not be b.
reactor vessel shell flange started unicas the coolant in that c.
temperatures of any two recirculation loop is within 50*F of the operating loops.
loop coolant temperature.
2.
The temperatures listed in 4.6.A.1
)
B.
Pressurization Ten.perature shall be permanently recorded sub-sequent to a heatup or cooldown at 1.
During heatup by non-nuclear means (except 15 minute intervals until three when the vessel is vented), cooldown follow-consecutive readinps are within 5 ing nucicar. shutdown, or low level physics degrees of each other.
tests, the reactor vessel metal should be at or above the temperatures shown on Fig.
B.
Pressurization Temperature
- 4. 6.1, curve 15.
1.
Reactor Vessel shell temperature 2.
During operation where the reactor core is and reactor coolant pressure sha?!
critical '(except for low level physics tests),
be permanently recorded at 15 vessel metal should be at or above the temp-minute intervals whenever the sheti craturen shown on Figure 4.6.1, curve C.
temperature is below RT NDT and the reactor vessel is not vented.
3.
During pressurization for system hydrostatic tests, vessel metal shonid he at or above 67 Amendment No. 26 the temperature shown.in Fig. 3.6.1, curve A.
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.'. 6 ' I.I!l..IlG COND1T10N FOR OPEltAT10!!
.6 SURVEILt.ANCE ItEqlilitEtIENT 2.
fleut ron I lux mon t I orn anil n.nnple., nhatI he inntalled Jn the reactos vennel 4.
Ihr reactor vennel head ho1 Ling ailjacent Io the ver.nel walI at I he c n e ntudn nhall not he under tennion midplane level. The monitor and nampic unicus the temperature of the program shall as a minimum conform to vennel shell immeillately below the ASTil E 185-66. The monitorn and namples vennel finnge in >l30*F.
nhall he removed and tested periodically to verify the calculated valuen of C.
Coolant Chemistry Integrated neutron flux that are used to determine the NDTT for Figure 4.6.1.
1.
The reactor coolant nyntem radioactivity concentration in water shall not 3.
When the reactor vennel head holting exceed 20 microcurlen of total studn are tightened or loonened the 1
lodine per ml. of water.
reactor vessel shell temperature immediate y below the head flange shall be permanently 2.
Tbc reactor coolant water shall recorded.
remain below the following limits uutti steam flow in entablinhed C.
Coolant Chemlntry l
except no npecified in 3.6.C.3.
A nample of reactor coolant shall 1.
a.
Conductivity 2pmho/cm be taken at Icast every 96 hourn Chloride ion 0.1 ppm and analyzed for radioactivity.
In addition, when off-gan monitors 3.
For reactor startups the maximum Indicate an Increase.In release value for conductivity shall not rate of 257. or 5000 pc/nec, which-exceed 10 Dmbo/cm and the maximum ever in greater, and which is not value for chloride ion concentration due to operations in progrens, a shall not exceed 0.1 ppm, for the reactor coolant sample shall he firnt 24 hourn after pincing the token and analyzed for radioacttvi reactor in the power operating b.
Inotopic analysis of a sample of condition.
e reactor coolant shall be made at least once per month during power E"'"
4.
Except as specified in 3.6.C.3 above, the reactor coolant water 2.
During.ntartups and before steam flow is shall remain below the following establinhed, a nnmple of reactor coolan-
' limits with nteam flow.
shall be taken every four hourn and analyzed for conductivity and chloride Conductivity Spmho/cm content.
Chloride ion 0.5 ppm 3.
n.
With entablinhed steam flow, a reactor coolnnt nample nhall be taken at leant every 96 hourn and Amendmen t flo. 26 b o.
NA
A - I(ydrontatic Prcncure Tcat Curvo D - IIcatup-Cooldown Curvo (Core Suberitical)
A 1200 -- C - Critical. Coro. Opefation p
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r i r.u re 4. 6. '1 Coolant Tenq5craturo (*F)
Drcr:C.cn Unit 1 IIcc. tup - Cooldown Curve at 100*F/Mr for an. accumulated Fluence of 1,4 x 1019 Amendment flo. 26 71
nnne..-
A.
Thermal I. imitations - The reactor vessel was a) The reference nil-ductility transition designed for a maximum hentup and cooldown temperature (RTNDT) for all vessel material.
rate of the contained fluid (water of 100*F) per hour averaged over a period of one hour.
b)
Integrated neutron flux at the vessel This rate has been chosen based on past ex-wall (fluence, at energies >lifeV).
per!ence with operaling power p.lants.
The associated time periods for heatup and cool-For radiation exposure to fast neutrons (>tteV) down cycles when the 100 F per hour rate is and fluence above 1 X 1037 nyt, the RTNDT m""L limiting, provides for efficient, but safe, be adjusted to account for the radiation effects plant operation.
on the vessel material.
F.xtensive tests have been made on the D-1 vessel material to characterize
?! ore severe thermal conditions than those the effects of irradiation. A summary of the which would be encountered during nermal results of the surveillance testing program are heating and cooling operations can he toler-given in letter dated October 18, 1977, from ated without damage to the reactor vessel.
Commonwealth Edison.
The three curves of 4.6.1 give the maximum allowabic gressure for three B.
Pressurization Temperature - The reactor different conditions.
Curve "A" is to be used coolant system is a primary barrier against for maximum hydrotest pressure. Curve "B" is the release of fission products to the to be used only for heating up or cooling the environs.
In order to provide assurance vessel when the core is subcritical.
Curve "C" that this barrier is maintained at a high is the curve that must be used when the core is degree of integrity, restrictions have been critical.
placed on the operating conditions to which it can he subjected.
These restrictions Figure 4.6.1 is acceptable for operation until shown in Figure 4.6.1 are established in the vessel wall at 1/4T location has seen a fluence conformance with 10 CFR 50 Appendix G.
of 1.4 x 1019 m/cm2 (2.4 X 106 Megawatt days). At 1 cast 90 days prior to this time new operating The reference nil-ductility transition limit curves will be submitted to NRC.
temperature RTNDT is defined as the temper-atore below which ductile failure cannot be Curve A is for hydrostatic pressurization tests.
guaranteed.
For irradiated material this This curve defines the maximum vessel pressure value, RTNDT, is known as the adjusted providing protection against non-ductile failure reference nil-ductility transition temper-of the vessel at any temperature.
It was cal-ature.
In evaluating the adequecy of ferritic culated using Figure G-2110.1 and the prescribed SA302 Grade B steel, it is necessary that procedures in ASME Section III Appendix G.
Curve the following be established:
A gives the maximum pressure the vessel can be pressurized to for a temperature below RTNDT pro-viding that during pressurization curve "B" is followed until this temperature is reached.
Amendment No.
26 72
Curve "B" Is the heat-up and cool-down curve when the core is subcritical. The reactor prer nure vessel inust never he pressurized to a prer.nure above that shown on this curve durinp, sub-critical react or heat.-up or cool-down.
Thun. Curbe B munt alwayn be followed j
dni I ny, the heating of the reactor pressure ver.ne l to the pressurization temperature for a hvdropressurization test.
Once the hydropressurization temperature is reached, Curve A can be followed to perform the hydro-pressurization test.
Curve B was plotted using the methods suggested in AS?!E Section III Appendix G.
Curve C gives the inaximum pressure the reactor pressure vessel can see during critical core operation. This curve is plotted using the safety margins specified for critical core operation in 10 CFR Appendix G Section IV.2.C.
4 1
1 Amendment No. 26 72A
F per ml.) of water in the primary reactor coolant system enn be reached if the grons radioactivity in the gaseous effluents are DELETED near the limit as set forth in Specification 3.8.C.1 or there is a failure or a prolonged ohutdown of the cleanup denincralizer.
The reactor water sample will be uned to assure that the limit of Specification 3.6.C 10 not excceded.
The total radioactive lodine activity would not be expected to change rapidly over a period of 96 hourn.
In additien, the trend of the stack off-gas release rate, which is continuously monitored, is a good indicator of the trend of the iodine activity in the reactor coolant. When a significant increase in off-gas in noted, as specified, an additional sample will be taken.
Since the concentration of radioactivity in the rehetor coolant is not continuously measured, coolant sampling would be ineffective as a meens to rapidly detect gross fuel element failuren.
Ilowever, some capability In addition, vennel material namplen will be to detect gross fuel element failures in located within th: vessel to monitor the inherent in the radiation monitors in the affect of neutron exposue on these materials.
off-gas system.
The samplen include specimens of base metal,
.el.1 zone netal, heat affected zone metal, liaterials in the primary system are primarily and standard opecimenn.
These snmples will 304 stainless steel and the 7.ircaloy fuel receive neutron e.xponure more rapidly than cladding.
The reactor water chemistry' limits the vessel wall raterial and theref ore will are established to prevent damage to these iced the vesse; n integrated neutron flux materials.
Limits are placed on chloride e::ro su r e.
These compler. vill provide further concentration and conductivity. The most
- s ;urance th at tbc shift in NETr used in the important limit is that pinced on chloride
- peci fication is conservative.
concentration to prevent stress corrosion cracking of the stainless stocl.
C.
Ceolant Chenistry - A steady state radiciod.ine co: :ent ration (20 nicrocurien of total iodine f
73 Amendment No. 26 3