ML19341D305
| ML19341D305 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/17/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341D306 | List: |
| References | |
| NUDOCS 8103050314 | |
| Download: ML19341D305 (18) | |
Text
{{#Wiki_filter:-- .. ~ pn ne: UNITED STATES g NUCLEAR REGULATOFlY COMMISSION t
- j WASHINGTON, D. C. 20556 IOWA ELECTRIC LIGHT AND POWER COMPANY _
CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. DPR-49 1. The Nuclear Regulatory Commission (the Comission) has found that: A. The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power Cooperative (the licensees) dated September 10, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-49 is-hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. l B108050hk _,j
, -.. =....-.... . i 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY C0leISSION ~ .Q Thomas . Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 17, 1981 4 i i.---. - -. 7- .y a-p_
. _._..a ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Remove Replace 3.2-5 3.2-5 3.2-Sa 3.2 -Sa
- 3. 2-6
- 3. 2 -6 3.2-7 3.2-7 3.2-19 3.2-19 3.2-23a 3.2-24 3.2-24 3.2-33 3.2-33 3.2-34a 3.6-6 3.5-6 6.2-3 6.2-3 6.3-1 6.3-1 6.8-1 6.8-1 6.8-2 6.8-2 6.8-2a e
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.._. m. _ __ DAEC-1 NOTES FOR TABLE 3.2-A 1.. Whenever Primary Containment integrity is required by Subsection 3.7, there shall be two operable or tripped trip systems for each functlen. 2. If the first column cannot be met for one of the trip systems, that trip system shall be tripced er the acpropriate acticn listed belcw shall be taken. ACT!CN A - Se in a least HOT SHUTCCWN within 5 hours an: in COLD SHUTCCSN within the next 30 hours. ACTION 3 - 3e in at least STARTUP witn the associated isolation valves closed within 5 hcurs or be ir at least HOT SHUTCOWN wi:nin 5 hours and in COLD SHUTDCWN within the nex: 30 hours. i ACT!CN C - : lose the affected system isolatien valves within One hcur and declare One affected system incoerable. f ACT:CN O - 5e in at leas: STARTUP wi nin 5 hours. ACTION E - Isolate secondary c:ntainmen: and start tne standby gas treatment system. 3. Instrument set:cint corres:cncs c 170" accve t:c of active fuel.* 1 Instrum an set:oin; corresponds to 119.5" above :: of acti.- fuel.' ' Too of the active fuel :cne is defined to te 342.5 inches accve vessel :ere (see 3ases 3.2). 3.2-5 Amendment No.'59, 64 4 =
If DAEC-1 5. Two required for each steam line. 6. These signals also start 55GTS and initiate secondary containment isolation. 7. Only required in Run Mcde (intericcked with Mode Suitch). s l 3.2-7 Amendment No. 33, 64 ~
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ACC1DLtil MotliIORIflG 1flSIRiltitil Al10N 5a g l us trimien t total No. of Channels Minimum Cha:mels Operable Safety /Rellet Valve Position 1/ Valve (1) 1/ Valve (2) Indicator (l*risitary Detector) Safety Relief Valve position 1/ Valve 0 Indica tor (IbcLup-lhenm> couple) Salety Valve position Indicator 1/ Valve (1) 1/ Valve (2) (Primary Detector) Sately Vulve position Indicator 1/ Valve O P2 (llackup-lheimocouple) g Y R n! w fl0lLS l~01 l AllLE 3.?-11 1. Each channel is comprised of three instruments (pressure switt.hes) which are arranged iri a "two out of three" logic connected to a relay, i 2. From and after the date that a channel is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which might be indicative of an open SRV; continued reactor operation is permissible only during the succeeding 30 days, unless such channel is sooner made operable. i f I e 4
TABIE 4.2-A 4 a MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Ins t rtunent Calibration Instrument Instrument channel (5) Functional Test (9) Fr equency (9) Check
- 1) Reactor Low Pressure (Shutdwn (1)
Once/3 months None Cooling Permissive) g
- 2) Reactor Low-Low Water Level (1)
Once/3 monitlis Once/ shift cn
- 3) Main Steam liigh Temp.
(1) Once/ operating Once/ day cycle
- 4) Reactor Low Water Level (1)
Once/ operating cycle once/ shift
- 5) Main Steam liigh Flow (1)
Once/3 months once/ shift
- 6) Main Steam Low Pressure (1)
Once/3 months None N
- 7) Reactor Water Cleanup liigh Flow (7)
(1) Once/3 months once/ day E u N /3
- 8) liigh Drywell Pressure (1)
Once/3 months ae s~
- 9) Reactor Cleanup Area Iligh Temp. (8)
(1) Once/ operating None cycle
- 10) liigh Radiation Main Steam Line Tunnel (1)
Once/ operating cycle Once/ shift
- 11) Loss of Main Condenser Vacuum (1)
Once/ operating None cycle Logic System Functional Test (4) (6)
- 1) Main Steam Line Isolation valves once/6 montha Main Steam Line Drain Valves Reactor Water Sample Valves
- 2) RilR - Isolation Valve Control Once/6 montha Shutdown Cooling Valves llead Spray
- 3) Reactor Water Cleenup Isolation Once/6 months J
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( DAEC-1 Th me i n. t.rumen t channe t:; will bc calibrated using simulated electrical signaln. 4. Simul.ated automatic act.uat. ion shall be performed once each operating cycle. Where possible, all logic syste.m functional t est.a will be performed using the test jacks. rteactor low wat.cr '.evel, high drywell pressure and high racitat. ion main steam line tunnel are also included on Tahla.1.1 2. 6. The logic system functional tests shall in.:Lude a cali-bration of time delay relays and timers necessary for proper ( functioning of the trip systems. 7. These signals are not PCIS trip signals but isolate the Peactor Water Cicanup system only. 8. This instrumentation is excepted from the functional test definition. The functional tsst will ;sasist of comparing the anslug signal of the active thermocouple element feeding the isolation logic to a redundant thermoccuple el..ue.. 9. Functional tests and calibrations are not required on the part of the system that is not required to be operable or is tripped. Functional tests shall be perfonned prior to returning the system to an operable status with a frequency not less than once per month. Calibrations shall be performed prior to returning the system to an operable status with a frequency not less than those defined in the applicable table. However, if maintenance has been performed on those components, functional tests and calibration shall be performed prior to returning to service. i l 3.2-33 ? l ~ 1 Amendment No. 29, 64
1 1 Alli E 4. 2 -11 i g ACCIDENT MONITORING INS 1RilMENTATION SURVLILL ANCE ItEQlllREMf filS E Instrument Check ( } Instrument CalibraLion fre<[uency, no E. p Safety / Relief Valve Position (!)(E) Once/ Operating Cycle Once/ month Indicator (Priniary) Safety / Relief Valve Postilon Once/ Operating Cycle Once/ month Indicator (Hackup-Thermocouple) Safety Valve Position Indicator (1)(2) Once/ Operating Cycle Once/ month (Primary) Safety Valve Position Once/ Operating Cycle Once/ month g w 7 Indicator (Hackup-Ihermocouple) g ?! L w NOIES IOR TAHLE _4.2-11 1. Functional test of the relay is done once/3 months. 2. Instrument check shall consist of the qualitative assessment of channel behavior during operation by observation. This detennination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels (e.g. backup thermocouple) measuring the sane paraneter. O e i
LI.9IT!NG CON 0fTf0NS FOR OpERATTON SURVEfLLANCE REOUTREVENTS 2. 2. At least one of ohe relief valves shall be disassembled a. From and after the date tnat the and inspected each refueling safety valve
- nction of cne outage.
relief valve is made or found to be inoperable, continued l reactor operation is per-missible only during the succeeding thirty days un-less suen valve function is sooner made coerable. b. From and after :ne date tna: the safety valve function of two relief valves is made or found c be incperacle, c:ntinued reactor oceration is per-missible only during the succeeding seven days unless such valve function is secner made Operable. ~ 3. If Specification 3.5.0.1 is no: 3. With the reactor pressure ;g 100 me:, an orderly shu-dcwn snail psig and turbine bypass flow to be initiated and the reactor the main condenser, each relief coolant pressure snall be valve snall be manually c:ened recuced :: atmospheric and verified Ocen by turbine by-within 24 hcurs. pass valve positicn decrease and pressure switches and l tnermaccuole readings dcwnstream of :he relief valve to indicate steam ficw from tne valve once per ocerating cycle., E. Jet puros ,vet umes r 1. Whenever One reactor is in tne 1. Whenever there is recircu-startup cr run medes, all jet lation ficw with the reactor pumps snall be Oceracie.
- f it in the startue or run mcdes, is determined that a jet purc jet cump Operabili y snali is inocerable, an crder!y shut-be checked daily by verify-down shall be ini:iated and ing that the following con-the reactor shall be in a ditions ce not occur simul-Cold Shutdown Condition within tanecusly:
i ?! neurs, a. The two recircul ation leccs have a ficw imcaiance of 15% or mere wnen the pum:s are Operated 3 the same s;eed. 3.5-6 Amendment No. 34, 64 e -WWTQj
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8-d CAEC-1 5.3 PLANI STAFF QUALIFICATIONS 6.3.1 The qualifications of individual members on the plant staff l will meet or exceed qualifications referenced for comparable positions ir. ANSI N18.1-1971. i 5.3.2 The Radiation Protection Engineer shall meet or exceed tne I qualifications of Regulatory Guide 1.3, September 1975. ) 5.3.3 The Shift Technical Advisor shall have a Bachelor's :egree or i equivalent in a scientific or engineering discipline with specific training in piant design, and response and analysis of the plant for transients and 5 accidents (effective 1/1/31). i J 4 I i Amendment No. 35, 64 5.3-1 %4
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~. e OAEC-1 - 6.3 PLANT OPERATING PROCEDURES 1 6.8.1 Cetailed written precedures involving nuclear safety, including acplicable check-off lists and instructions, covsring areas listed belcw shall be prepared, and approved as specified in Subsection 5.3.2. All crocedures i shall be adhered to: 1 r Normal star:ue, operation, and shutdown of systems anc 1. f_ ccmcenents of the f5cility. 1 i 2. Rafueling Ocerations. } 3. Actions be taken to c:rrect s:ecific anc foreseen pctantial malfunctions o' systems or ccmcenents, including respenses to alarms, sus-
- ected primary leaks, and abnormal reactivity enanges.
4 Emergency and off-normal ::nciti:n :rocedures. 5. Preventive and corrective maintenance Operations whicn could nave an effect on the nuclear safety of tne facili:y. 5. Surveillance an: testing recuirements. 5.3-1 Amendment No. 64 l G -+ ~' m*u w c -q -pg m,,,w---,-. y mycp,q..e q p. 9-t- -'f"" - --- " - * -*m*"" ..m.vm -w w 7-
DAEC-1 -7. Procedures ' required by the Preparedness Plan. l 3. Procedures required by the plant Security ?!an. 9. Operation of radicactive waste systems. 10. Fire Protection Program imolementation. 11. A preventive maintenance and periodic visual examination program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient to as low as practical levels. This program shall also include provisions for performance of periodic systems leak tests of each system no less frequently than at refueling cycle intervals. 12. Program to ensure the capability to accurately determine the airoorne iodine ::ncentration in vital areas under acciden: conditions, including training of perscnnel, procecures for monit: ring and provisions f:r maintenance of samoling and analysis ecufpment. 5.3.2 Procedures described in 5.3.1 a:cve, and changes thereto, snail be reviewet :y One Ccerations ^:mmittee and sporoved :y the Chief Engineer price :: imciementatien, except as provided in 5.3.3 :eicw. 6.3.3 Tem:orary minor :hanges :o procedures describec in 5.3.1 above which do not :nange :he inten: Of the original precedure may be made with the concurrence of two emebers of the plan management staf#, a: leas: One of wncm shall hcid a senior Opera:Or license. Such changes snail be documented anc Or:mptly reivewed by :ne Operations Cctmittee and by the Chief Engineer. Sucsequent incor;cration, if necessary, as a permanent change, snall :e in ac: orc with 5.3.2 above. Amendment No.,43, 64 5.3-2 =%.m A m---
CAEC-1 6.3.4 Selected drills of emergency procedures shall be conducted quarterly in accordance with the provisiens of the Preparedness Plan. 6.3.5 The preventive and correctP/e maintenance program 6.S.1.11 above shall be implemented as follows: 1. Once per year er no less frequently than once per refueling cycle, a detailed walkd:wn inspec:icn snall be performed and the results recorded. 2. Accitional walkdcwn ins:ections shall be perfcrmed cuarterly
- detect any visible leakage.
u I Amendment No. 64 1 6.3-21 . ~., 4}}