ML20238D710
| ML20238D710 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/31/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20238D704 | List: |
| References | |
| NUDOCS 8709110348 | |
| Download: ML20238D710 (7) | |
Text
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!s**av UNITED STATES o,,
8-NUCLE AR REGULATORY COMMISSION c.
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,I wassmovos. o. c. 20sss NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.10.9 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated November 24, 1987 as modified by letter dated August 13,-1987, 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; 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; 0.
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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
8709110348 870908 PDR ADOCK 05000298 P
2-l (2) Technical Specification The Technical Specification's contained'in Appendix A, as revised through Amendment No.109, are hereby incorporated in the license.
'The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment'is effective as of its date of issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION
- j 4, & /i..>
f'JoseA.Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 31, 1987
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ATTACHMENT TO LICENSE. AMENDMENT'NO.IM FACILITY OPERATING LICENSE NO. OPR-46
}j DOCKET NO. 50-298 4
Replace the following pages of the Appendix A Te'chnical Specifications with The revised areas are indiciated by marginal. lines.
the enclosed pages.
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Pages 52a 134 134a 229 l
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SCrIES FOR TASLE 3.2. A (cont'd.)
Group 2 Isolation Signals:
1.
Reactor Low Vater-Level (+12.5 in.)~
2.
High Dry Well Pressure (< 2 pois)
Isolations:
1 1.
RER Shutdown Cooling System j
2.
Vessel head spray 3.
Dryvell floor and equipment drain sump discharge lines.
4 TIP ball valves 5.
Group 6 isolation relays l
l Group 3 Isolation Signals:
1.
Reactor Lov Water Level- (+12.5 in.)
'l 2.
Reactor Water Cleanup System High Flev (2001 of system flow) 1 3.
Reactor Water Cleanup System High Area Temperature (< 200'F) i l
Isolations:
1.
Reactor Water Cleanup System Greup 4 Isolation Signals:
Provided by instruments on Table 3.2.B (HPCI)
]
Isolations:
Isolates the EPCI steam line Group 5 Isolation Signals:
Provided by instruments on Table 3.2.B (RCIC)
Isolations:
Isolates the RCIC steam line.
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Group 6
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l Isolation Signals:
1.
Group 2 Isolation Signal 2.
Reactor Building H&V Exhaust Plenum High Radiation (<100 mr/hr)
- c+ndment No. 103, 109
-52a-g[p g g
L_______________________________________________________________
LIM!ilNC CONDITIONS FOR OPEPATION SURVEILLANCE REQUIREMENTS
~
4.6.B.1 (cont'd) 1 6.B.
(cont'd) l b.
If the gross activity counts of a
?
nen the reactor is pressurized (i.e.
sample indicate an activity
>212*F) and during operation up to 10%
- "**"I'**I " * **
8 I!I" of rated power, the following reactor dose equivalent 1-131. an isotopic coolant system chemistry limits shall analysis shall be performed and apply:
quantitative measurements niade to determine the dose equivalent a.
Normal limits.
1-131 concentration.
i Conductivity (umho/cm at 25'C)
<2.0 c.
An isotopic analysis of a reactor l'
coolant sample shall be made at
~
Chloride (ppm) 10.1 least once per month..
pH 5.61pH18.6 2.
Reactor coolant shall be continuously monitored for conductivity, or, when 1
Should these limits be exceeded the continuous conductivity monitor is for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one inoperable, the reactor coolant shall continuous time interval, be in at be analyzed:
least the HOT SHUTDOWN condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and (or a.
At least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for if already in the HOT SHUTDCMN conductivity, chloride fon content, condition) be in the COLD SHUTDOWN and pH, when the reactor is condition within the following 24 pressurized (i.e. >212*F), during hours.
the operation of the reactor, and during hot standby.
3.
During operation in excess of 10% of r a t ed power, the following reactor 3.
Vhen the reactor is pressurized (i.e.
1 coolant system chemistry limits shall
>212*F), and during the operation l
apply:
of the reactor, and during hot standby, a sample of the reactor coolant'shall a.
Normal limits.
be analyzed:
.J Conductivity a.
At least every 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> for
]
(umho/cm at 25'C) 11.0 conductivity and chloride ion l
content when the continuous Chloride (ppm) 10.2 conductivity monitor reading is
<0.7 vmho/cm at 25'C.
pH 5.6<pH18.6 j
b.
At least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for i
i b.
Time limit.
Should the conductivity and chloride ion conductivity or chloride limits in content when the continuous 3.6.B.3.a. be exceeded for more conductivity monitor reading is j
than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year or the
>0.7 but. <2.0 pmho/cm at 25'C.
conductivity, chloride or pH limits j
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for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one c.
At least every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for l
continuous time interval, be in at conductivity and chloride ion least the STARTUP/ HOT STANDBY mode content when the continuous within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
conductivity monitor reading is
>2but().5pmho/cmat25'C.
c.
Maximum limits.
j Conductivity (pmho/cm at 25'C) 110 l
1 Chloride (ppm) 10.5 Amendment flo. N. EB,109
LIMITISC CONDITIONS FOR OPERATION SURVEILLMlCE REQUIREMENTS Should these maxi =um limits be d.
At least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> f or exceeded, be in the COLD SHL'TDOWN conductivity, chloride ion contect, condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
and pH, when the continuous conductivity monitor reading is 4
At all other times, the following
>3.5 unho/cm at 25'C.
I reactor coolant system chemistry limits shall apply:
4 When the reactor is not pressurized, a sample of the reactor coolant shall be analy:ed at least every 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> for a.
Normal limits.
conductivity and chloride ion content Conductivity and pH.
l (umho/cm at 25'C) 110.0 Chlorides (ppm) 10.5 pH 5.31pH18.6 Should the conductivity o'r pH limits be exceeded for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval, or should the chloride limit be exceeded for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during one continuous time interval, perform an engineering evaluation to determine the effects of the out-of-limit condition on I
the structural integrity of the reactor coolant system.
The structural integrity of the reactor coolant system shall be determined to remain acceptable for continued operation (prior to operation in other than the COLD SHUTDOWN conditions).
5.
The provisions of Specification 1.0.J, are not applicable.
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1 Amendrent No. 109
- 3'a-SEP B 1907
6.4.2.G: (cont'd) usage evaluation per the pSKE Boiler and Pressure. Vessel Code Section III was performed for the conditiets defined in the design specification.
The locations to be monitored shall be:
.a.
Ths'feedvater nozzles b.
The shell at or near the waterline c.
The flange studs 2.
Monitoring, Recording, Evaluating, andL Reporting Operational transients that occur durits plant operations will, a.
least annually, be reviewed and compared to the transient atconditions-defined in the component stress report for. the locations listed in 1 above, and used as a basis for the existing f atigue analy sis,
b.
The number of transients which are comparable to or more severe than the transients evaluated in the stress report Code f atigue usage calculations will be recorded in an operating log book.
For those transients which are more severe, available data, such as the metal and fluid temperatures, pressures, flow rates, and other conditions vill be recorded in the log book, c.
The number of transient events that exceed the design specif1 cation quantity and the number of transient events with a severity greater than that included in.the existing Code f atigue usage calculations shall be added. When' this sum exceeds the predicated number of y
design condition events by twenty-five, a f atigue usage evaluation -
of such events _ vill be perf ormed for the af f ected portion of the RCPB.
H.
Records of current individual plant staf f members showing qualifications and the completion of training.
1.
Records for Environmental Qualification which are covered under the pro-l visions of Specification 6.3.
1 J.
Records of the service lives of all hydraulic and mechanical snubbers l
noted in 3.6.B.1, including the date at which the service life commences l
and associated installation and maintenance records.
l 6.4. 3 2 Year Retention Records and logs relating to the following items shall be kept for two years.
A.
The test results, in units of microcuries, for leak tests of sources performed pursuant to Specification 3.8. A.
B.
Records of annual physical inventories verifying ' accountability of the sources on record.
1.
See paragraph N-415.2, ASME Section III, 1965 Edition.
2.
The Code rules permit exclusion of eventy-five (25) stress cycles from secondary stress and f atigue usage evaluation.
(See paragraphs N-412(t)(3) and N-417.10(f) of the Summer 1968 Addenda to ASME Section III,1968 Edition.)
4.e ndment No. 74, 32, 97,.109
-229-SEP E 19 7
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