ML20238D681
| ML20238D681 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/31/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20238D683 | List: |
| References | |
| NUDOCS 8709110322 | |
| Download: ML20238D681 (7) | |
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NUCLEAR REGULATORY COMMISSION n
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. OPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) cated 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-
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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:
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i (2). Technical Specification The Technical Specifications contained in Appendix A, as revised' through Amendment Nc.108, are herely incorporated'in the license.
The licensee shall operate the facility in accordance with the j
Technical Specifications.
3.
This..licenseamendmentiseffectiveasofitsdateofissuance, FOR Tile NUCLEAR REGULATORY COMMISSION s
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y J)se A. Calvo, Director Project Directorate - IV
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IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August' 31, 1937 p
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l, ATTACHMENT TO LICENSE dMENDMENT NO.108-FACILITY OPERATING LICENSE NO. DPR-46.
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DOCKET NO. 50-298 l
Replace the following pages of the Appendix A Technical' Specifications with-the enclosed pages.
The revised areas are indiciated by marginal lines.
Pages 52a
'134 134a 229 4
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NOTES FOR TABLE 3.2. A (cont'd.)
Group 2 Isolation Signals:
1.
Reactor Lov Water Level (+12.5 in.)
2.
High Dry Well Pressure (< 2 peig)
Isolations:
1.
RER Shutdown Cooling System 2.
Vessel head spray 3.
Drywell floor and equipment drain sump discharge lines.
4 TIP ball valves 5.
Group 6 isolation relays Group 3 Isolation Signals:
1.
Reactor Lov Water Level (+12.5 in.)
2.
Reactor Water Cleanup System High Flow (200% cf system flow) 3.
Reactor Water Cleanup System High Area Temperature (< 200*F)
I Isolations:
1 1.
Reactor Water Cleanup System Group 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.
Group 6 1 solation Signals:
1.
Group 2 Isolation Signal 2.
Reactor Building H&V Exhaust Plenum High Radiation (<100 mr/hr)
Anendment No. Jp3,108
-52a-
LIMITING CONDITIONS FOR OPEPATION SURVEILLANCE REQUIREMENTS 4.6.B.1 (cont'd) 1.6.B. (cont'd) b.
If the gross activity counts of a 2.
Vben the reactor is pressurized (i.e.
sample indicate an activity..
>212*F) and during operation up to 10%
c neentration above 3.1 pCi/gm of of rated power, the following reactor dose equivalent 1-131, an isotopic coolant system chemistry limits shall analysis sna11 be performed and apply:
quantitative measurements made to determine the' dose equivalent a.
Normal limits.
I-131 concentration.
Conductivity (pmho/cm at 25*C) 12.0 c.
An isotopic analysis of a reactor coolant sample shall be made at Chloride (ppm) 10.1 least once per month.
pH 5.61pH18.6 2.
Reactor coo'lant shall be continuously monitored for conductivity, or, when 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 17. hours 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 SHUTDOWN conductivity, chloride ion content, condition) be in the COLD SEUTDOWN and pH, when the reactor is I
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 l
rated power, the fellowing reactor 3.
When the reactor is pressurized (i.e.
coolant system chemistry limits shall
>212*F), and during the operation apply:
of the reactor, and during hot standby, a sample of the reactor coolant shal) 4.
Norval limits.
be analyzed:
i 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 content when the continuous Chloride (ppm) 10.2 conductivity monitor reading is
<0.7 umho/cm at 25'C.
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pH 5.61pH18.6 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 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 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 Iimits
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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 continuous time interval, be in at conductivity and chloride ion least the STARTUP/ HOT STANDBY mode content when the continuous i
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
>2 but <3.5 pmho/cm at 25'C.
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c.
Maximum limits.
Conductivity (umho/cm at 25"C) 110 Chloride (ppm) 10.5 Amendment No. EP, R$,108 l
LIMITING CONDITIONS FOR OPERATION SURVEILLM:CE REOUIRDiENTS Should these maximum 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 /> fer exceeded, be in the COLD SHUTDOWN conductivity, chloride ion content, 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, vhan the continuous-
.' conductivity monitor reading is 4.
At all other times, the following
>3.5 umho/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 a.
Normal limits, analyzed at. least ' every 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> for 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 or 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 the structural integrity of the reactor coolant system. The structural integrity of the reactor coolant system shall ba 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 l
are not applicable.
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Amendment No 108
-134a-
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l.& 2.0 (cont'd) usage evaluation per the pSME Boiler and Pressura Vessel Code Section III was performed for the conditions defined in the design specification. The locatione to be monitored shall be:
a.
The feedvater nozzles b.
The shell at or near the waterline c.
The flange stude 2.
Monitoring, Recording, Evaluating, and Reporting a.
Operational transients that occur during plant operations will, at least annually, be reviewed and compared to the transient conditions defined in the component Stress report for the locations listed in 1 above, and used as a basis for the existing fatigue analysis.
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 tempa'etures, pressures, flow rates, and other conditions will be recorded in the log book.
c.
The number of transient events that exceed the design specification quantity and the '. umber of transient events with a severity greater than that incluved in.the existing Code f atigue usage calculations shall be added.
When this sum exceeds the predicated number of 2
design condition events by eventy-five, a fatigue usage evaluation of such events will be performed for the affected portion of the RCPB.
H.
Records of current individual plant staff members showing qualifications and the coupletion of training.
I.
Records for Environmental Qualification which are covered under the pro-visions of Specification 6.3.
3 J.
Records of the service lives of all hydraulic and mechanical snubbers noted in 3.6.H.1, including the date at which the service lif e commences and associated installatica and maintenance records.
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.
3.
Records of annual physical inventories verifying accountability of the sources on record.
4 1.
See paragraph N-415.2, ASME section III, 1965 Edition.
)
2.
The Code rules permit exclusion of twenty-five (25) stress cycles from secondary stress and fatigue usage evaluation.
(See paragraphs N-412(t)(3) and N-417.10(f) of the Summer 1968 Addenda to ASME Section III, 1968 Edition.)
Amendment No. 74, $2, 92,108
-2'9-
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