ML20098H188
| ML20098H188 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/27/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20098H189 | List: |
| References | |
| TAC 46677, NPF-03-A-075 NUDOCS 8409120105 | |
| Download: ML20098H188 (11) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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's THE TOLEDO EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated July 10, 1981, as revised May 2, 1983; February 23, 1983; and August 18, 1983, comply 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 applications, 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 Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
84091;M)105 84ce27 PDR ADOCK 05000346 p
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. 'l Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of-issuance'.
FOR THE NUCLEAR REGULATORY COMMISSION b
ohn
. Stolz, Chief j
Qgerating Reactors Brandh No. 4.
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1984 l
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ATTACHMENT TO LICENSE AMENDMENT N0.75 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET N0.-50-346 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 6-19 3/4 8-3 3/4 8-5 6-15 t
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TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME (seconds) 67 CV5090 Hydrogen Dilution System Supply 60 68A SS235A Pressurizer Quench Tank Sample 30 68A SS235B Pressurizer Quench Tank Sample 30 688 CV5010B Containment Air Sample 15 688 CV5011B Containment Air Sample 15 69 CV5065 Hydrogen Dilution System Supply 60 71B CV5010A Containment Air Sample 15 718 CV5011A Containment Air Sample 15 71C CV1544 Core Flood Tank N2 Fill 10 73B CV5010C Containment Air Sample 15 73B CV50 llc Containment Air Sample 15 74B CV50100 Containment Air Sample 15 74B CV5011D Containment Air Sample 15 B.
CONTAINMENT PURGE AND EXHAUST ISOLATION 33 ## CV5005 Containment Vessel Purge Inlet Line 10 33 #p CV5006 Containment Vessel Purge ' Inlet Line 10 34 ## CV5007 Containment Vessel Purge Outlet Line 10 34 ## CV5008 Containment Vessel Purge Outlet Line 10 C.
OTHER 5 # SW1366 Containment Air Cooling Units SW Inlet Line N/A 6
- SW1368 Containment Air Cooling Units SW Inlet Line N/A 7 # SW1367 Containment Air Cool:ng Units SW Inlet Line N/A 9 # SW1356 Containment Air Cooling Units SW Outlet Line N/A i
Amendment No. 8J,75 DAVIS-BESSE, UNIT 1 3/4 6-19
r TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME (seconas) 10 # SW1358 Containment Air Cooling Units SW N/A Inlet Line 11 # ~ SW1357 Containment Air Cooling Units SW Outlet Line N/A 17 CY343 Containment Yessel Leak Test Inlet Line 17 Flange Co'ntainment Vessel Leak Test Inlet Line (Inside Containment)
N/A 19 # HP57 High Pressure Injection Line N/A 20 # HP56 High Pressure Injection Line N/A 22 # HP49 High Pressure Injection Line N/A 23 # SF1 Fuel Transfer Tube N/A 23 Flange Fuel Transfar Tube N/A 24 # SF2 Fuel Transfer Tube N/A 24 Flange Fuel Transfer Tube N/A
- 25 CS23 Containment Spray Line N/A
- 25 CS17 Containment Spray Line N/A
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25 SA536 Containment Soray Line N/A l
25 SA532 Containment Spray Line N/A
- 26 CS36 Containment Spray Line N/A
- 26 CSIS Containment Spray Line N/A 26 SA535 Containment Spray Line N/A l
26 SA533 Containment Spray Line N/A 1
i 27 # DHIA Low Pressure. Injection Line N/A 27 # DH76 Low Pressure Injection Line N/A
i DHl3 Low Pressure Injection Line N/A 28 # DH77 Low Pressure trigection Line N/A DAVIS-BESSE, UNIT 1 3/4 6-20 Amendment No. 3
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tank, 2.
Verifying the fuel level in the fuel storage tank, i
3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.
Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in 1 10 seconds, i-5.
Verifying the generator is synchronized, loaded to 3,1000 kw, and operates for 3,60 minutes, and 6.
Verifying the diesel generator is aligned to provide standby power to the associated essential busses.
t 7.
Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within + 10" of 3
its requi.ed value.
b.
At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM 0975-68 when checked for viscosity, water and sediment.
c.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's i
recommendations for this class of standby service, Verifying the generator capability tc reject a load l
2.
the largest single emergency load supplied by the generator without tripping.
I 3
Simulating a loss of offsite power in conjunction with a safety injection actuation test signal, and:
(a)
Verifying de.energization of the essential busses and load shedding from the essential busses, DAVIS-BESSE, UNIT 1 3/4 8-3 Amendment No. 75 i
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b)
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the essential busses with permanently connected loads, energizes the auto-connected essential loads through the load sequencer and operates for 3,5 minutes while its generator is loaded with the essential loads.
c)
Verifying that all diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the essential bus and/or an SFAS test signal.
4.
Verifying the diesel generator operates for 1. 60 minutes while loaded to 3. 2000 kw.
i 5.
Verifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2838 kw.
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l DAVIS-BESSE, UNIT 1 3/4 8-4 i
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I ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and the onsite Class lE distribution system consisting of; 1.
One OPERABLE 345 KV transmission line, 2.
One OPERABLE 345 KV - 13.8 KV startup transformer, and 3.
One OPERABLE 13.8 KV bus, and b.
One diesel generatcr with:
1.
Day fuel tank containing a minimum volume of 4000 gallons of fuel, 2.
A fuel storage system containing a minimum volume of 32,000 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.5 and 4.8.1.1.2.a.7.
DAVIS-BESSE, UNIT 1 3/4 8-5 Amendment No. 75
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ELECTRICAL POWER SYSTEMS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE and energized with tie breakers open between redundant busses:
4160 volt Essential Bus # C1 4160 volt Essential Bus # D1 480 volt Essential Bus # El 480 volt Essential Bus # F1 120 volt A.C. Vital Bus # Y1 120 volt A.C. Vital Bus # Y2 120 volt A.C, Vital Bus # Y3 120 volt A.C. Vital Bus # Y4 i
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following
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30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS l
I 4.8.2.1 The specified A.C. busses shall be determined OPERABLE with tie breakers open between redundant husses at least once per 7 days by verifying correct breaker alignment and incicated power availability.
g DAVIS-BESSE, UNIT 1 3/4 8-6
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ADMINISTRATIVE CONTROLS' power operation), supplementary reports shall be submitted at le'st a
every three months until all three events have been completed.
ANNUAL OPERATING REPORTE 6.9.1.4 Annual reports covering the activities of the unit during the previous calendar year shall.be submitted prior to March 31 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
. A tabulation on an annual basis of the number of station, utility and other personnel (. including contractors) receiving exposures greater than 100 mrem /yr and their asso rem exposure according to work and job functions,gjated man e.g.,
reactor operations a~nd surveillance, inservice inspection, routine maintenance, special ma'intenance (describe maintenance),
i waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to spec,ific major work functions.
b.
The complete results of steam generator tube inservice inspections (Specification
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MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdewn experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washincton, D.C.
- 20555, with a. copy to the Regional Office, _to arrive no later than the 15th of each month following the calendar month covered by the report.
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A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all I
units at the station.
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This tabulation supplements the re.quirements' of.120.407 of l
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DAVIS-BESSE, UNIT 1.-
6-15 Amendment No..,%W,AQP3, 75
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ADMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9, including corrective actions and measures to prevent recurrence, shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP
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6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate e
no later than the first working day following the event, with a written followup report within two weeks.
The written followup report shall include, as a minimum, a completed copy.of a licensee event report form.
Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event, a.
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
b.
Operation of the unit or affected systams when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical s peci fications,
c.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure.bcundary, or primary containment.
d.
Reactivity ancmalies invo'1ving disagreement with the predicted value of reactivity balance under steady state conditions du' ring power operation greater than or equal to 1% ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifica-tions; short.-tera reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5% ak/k; or occurrence of any unplanned criticality.
CAVIS-IESSE, UNIT 1 6-16
/c.endmentNo.[12l