ML20079N006

Amend 52 to License NPF-3,permitting Defeat of Essential Bus Feeder Breaker Undervoltage Trips for Up to 1 Minute When Starting Reactor Coolant or Circulating Water Pump

ML20079N006
Person / Time
Site:	Davis Besse
Issue date:	02/17/1983
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20079G766	List: ML20079N006 ML20079N032 ML20079N164
References
NPF-03-A-052 NUDOCS 8303030409
Download: ML20079N006 (11)

Text

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'Io UNITED STATES g

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NUCLEAR REGULATORY COMMISSION

,,E WASHINGTON, D. C. 20555

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THE TOLED0 EDISON 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. 5 2

(

License No. NPF-3 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 23, 1979, as supplemented August 31, 1931, and March 19, 1982, 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 autSorized 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 'pplicable requirements a

have been satisfied.

8303030409 830217 PDR ADOCK 05000346 P

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4 2.

Accordingly, Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:

Revise paragraph 2.C.(2) to read as follows:

Technical Specifications The Technical Specifications contained in Appendices 1

A and B, as revised through Amendment No. 5 2, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Sp.*?.ifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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J6hn F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing Attachrent:

Changes to the Technical Specifications Date of IssuanceFEB 1 7 1983 i

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d ATTACHMENT TO LICENSE AMENDMENT NC 5 i FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment nunber and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4 3-11 3/4 3-12 3/4 3-12a (new page) 6-15 ll '

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i TABLE 3.3-3 E$

SAFETY FEATUR,ES ACTUATION SYSTEM INSTRUMENTATION Y'g MINIMtM TOTAL NO.

UNITS UNITS APPLICABLE

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FUNCTIONAL UNIT 0F UNITS

,TO TRIP

OPERARLE, MODES ACTION c5 3.

MANUAL ACTUATION

-4 a.

/ SFAS (except Containeent i Spray and Emergency Sump 2

2 2

1,2,3,4,6****

11 Recirculation) i b.

Containment Spray 2

2 2

1,2,3,4 11 A.

SEQUENCE LOGIC' CHANNELS' s-s, x Seque'ncer 4s 2***

4 1, '., 3,4 9#'

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a.

1

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b.., Essential Bus Feeder 2

14 2*****

1,2,3,4 14#'

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s f Breaker Trip (90%)

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Diesel Generator St3rt,

'2 1

2 1,2,3,4 14#

g Load Shed Bus' (59%) gn tssent N e--

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IllTERLOCK CilAllilELS '. 4

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Decay lleat Isolation Valv,e, 1

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.a TABLE 3.3-3 (Continued)

TABLE NOTATION i

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• Trip function may be bypassed in this MODE with RCS pressure below 1800-psige Bypass shall be automatically removed when RCS pressure

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exceeds l800 psig.

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Trfp function may be bypassed in this MODE with RCS pressure below 600; psig;600, psig. Bypass shall be automatically removed when RCS pressure exceeds?

One niu'st[be if SFAS Channels #1 or #3, the other must be in Channels

1. 2 orJ4?

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• • • • This ins inentation must be OPERABLE during core alterations or movo-ment of ifradiaced fuel within the containment to meet the require-

.ments of Tech. Spec 3.9.4.

All f n2tional units may be bypassed for up to one minute when starting,each Pcactor Coolant Pump or Circulating Water Pump.

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The proyisions of Spec'ification 3.0.4 are not applicable.

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.:f ACTION STATEMENTS 7

ACTION 9 -

With the nucher of OPERABLE functional units one less than th; Total Number of Units, startup and/or power operation map proceed provided both of the following conditions are s'atis fi ed:

a.s The inoperable functional unit is.placed in the tripped condition within one hour.

,c W b.

The Minimum Units OPERABLE requirement is met; how-ever, one additional functional unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 10 -

With any component in the Output Logic inoperable, trip th: associated components within one hour 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 l

SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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ACTION 11 -

With the number of OPERABLE Units one less than the Total l

Number of Units, restore the inoperable functional unit j

to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 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 with-t.

in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 12 -

a.

With less than the Mimimum Units OPERABLE.and reactor coolant pressure > 438 psig, both Decay Heat Isola-tion Valves (DHil~and DH12) shall be verified closed.

b.

With Less than the Minimum Units OPERABLE and reactor i

l coolant pressure < 438 psig operation may continue; however, the functional unit shall' be OPERABLE prior to increasing reactor coolant pressure above 438 psig.

ACTION 13 -

With less than the Minimum Units OPERABLE and reactor coolant pressure <438 psig, operation may continue; however, the func-tional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig, or the inoperable functional unit t

shall be placed in the tripped stata.

DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No. K37,5 2

TABLE 3.3-3 (continued)

ACTION STATEMENTS ACTION 14 With the number of OPERABLE functional units one less than the Total Number. of Units operation may proceed provided both of the following conditions are satisfied:

a.

The inoperable section of a functional unit is placed in the tripped condition within one hour, b.

The Minimum Units OPERABLE requirement is met; how-ever, the inoperable section of a functional unit may be-bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification-4.3.2.1.1.

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s DAVIS-BESSE, UNIT 1 3/4 3-12a Amendment No. 5 2

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b ADMINISTRATIVE CONTROLS i

power operation), supplementary reports shall be submitted at leitst every three months until all three events have been completed.

E ANNUAL OPERATING REPORT 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 i

following initial criticality.

l

6. 9.1. 5 Reports required on an annual basis shall include:

i 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 assopated man rem exposure according to work and job functions, e.g.,

reactor operations a~nd surveillance, inservice inspection, routine maintenance, special'ma~intenance'(describe maintenance),

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 e

totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the l

total whole body dose received from external sources shall l

be assigned to spec.ific major' work functions.

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b.

The complete results of steam generation tube inservice inspections (Specification ~~41475'~5.b).

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdcwn experience shall be submitted on' a monthly basis to the Director, Office of Management j

j and Program Analysis, U.S. Nuclear Regulatory Commission. Washington, 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 submittai should combine those sections that are common to all units at the station.

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This tabulation supplements the requirements' of.s20.407 of 10 CFR Part 20.

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DAVIS-BESSE, UNIT 1 6-15 Amendment No..RW,MI5 8 i

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ADMINISTRATIVE CONTROLS

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rep 0RTABLE 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.

PROMpf 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 designatt no later than the first working day following the event, with a written I

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.

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a.

Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the I

required protective function by the _ time a monitored para-l -

meter ra=ches the setpoint specified as the limiting safety system

- 7.ing in the technical specifications or failure to compl6ce the required protective function.

b.

Operation of the unit or affected systems when 'any parameter 7

cr 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 speci fications.

c.

Abnormal degradation discovered in fuel cladding, reactor

. coolant pressure. boundary, or primary containment.

d.

Reactivity anomalies invdiving 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-terra reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% ak/k; or occurrence of any unplanned criticality.

s MVIS-IESSE, UNIT 1 6-16 Amendment No. (12 l

o3

f 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 no later than the first working day following the event, with a written folloyup 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, at 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 1

to complete the required protective function.

b.

Operation of the unit or affected systems when any parameter or operation subject to a limiti.1g condition for operation' is less conservative than the least conservative aspect of the limiting condition for operation established in the technical speci fications.

c.

Abno'rmal degradation discovered in fuel cladding, reactor

. coolant pressure. boundary, or primary containment.

d.

Reactivity anomalies involving 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 te'chnical specifica-tions; short-teria 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.

n MVIS-dESSE, UNIT 1 6-16 Amendment No. 412 y

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