ML20033C656

Amend 41 to License NPF-3,changing Date for Submission of Annual Personnel Radiation Dose Monitoring Repts from March 1 to March 31 of Each Yr

ML20033C656
Person / Time
Site:	Davis Besse
Issue date:	11/09/1981
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Cleveland Electric Illuminating Co, Toledo Edison Co
Shared Package
ML20033C657	List: ML20033C656 ML20033C658
References
NPF-03-A-041 NUDOCS 8112030579
Download: ML20033C656 (6)

Text

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UNITED STATES

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' 'g NUCLEAR REGULATORY COMMISslON

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THE TOLEDO 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 Amendnent No.41 License No. NPF-3 1.

The Nuclear Regulatory Connission (the Comission) has found that:

A.

The application for amendment by the Toledo Edison Company)and The Cleveland Electric Illuminating Company (the licensees dated April 27, 1981, complies with the standards and require-ments 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 confomity with the application.

the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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 connon 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 Connission's regulations and all applicable requirements -

have been satisfied.

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Accordingly, the license is amended by changes to the Technichio

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Specifications as indicated in the attachment to this licerise!

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amendment, and paragraph 2.C.(2)' of Facility Operating Licerise r

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No. NPF-3 is hereby amended to read as follows:

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s (2) Technical Specifications i'

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=4 The Technical. Specifications contained in Appendices 5s c.c; A and B,,as revised through Amendment No. 41, are o

hereby incorporated in.the license.

The Toledo Edison s' '

Company shall operate the facility in accordance with G,'

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the Technical Specifications, w

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

FOR THE NUCLEAR REGULATORY COMMISSION' 1

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Jahk F. Stolz, Ch'ief s

Oferating Reactors Branch #4 d ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issua.nce: November 9,1981 A

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~ ATTACHMENT TO LICENSE AMENDMENT NO. 41 N

FACILITY OPERATING LICENSE NO. NPF-3 L

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.( f Replace.theffollowing pages of the Appendix "A" Technical Specifications W.gMA with the' enclosed pages as indicated. The revised pages are identified by Amendment' number and contain vertical lines indicating the area of M

T change. The..ccrresponding overleaf piges are also provided to maintain i

docuu.ent completeness.

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y REACTIVITY CONTROL SYSTEMS SAFETY R00 INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All safety rods shall be fully withdrawn.

APPLICABILITY:

1* and 2*#.

ACTION:

With a maximum of one safety rod not fully withdrawn, except for sur-veillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a.

Fully withdraw the rod or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

7 SURVEILLANCE REQUIREMENTS 4.1.3.5 Each' safety rod shall be detemined to be fully withdrawn:

a.

Within 15 minutas prior to withdrawal of any regulating rod during an approach to reactor criticality.

b.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

• See Special Test Exception 3.10.1 and 3.10.2.

1. With K,ff > 1.0.

DAVIS-BESSE, UNIT 1 3/4 1-25 4

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'lP.[ACTIVITYCONTROLSYSTEMS REGULATING R00 INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-2a and -2b and 3.1-3a and -3b, with a rod group overlap of 25 +;; 5% between sequential withdrawn groups 5. 6, and 7.

L APPLICABILITY: MODES 1* and 2*#.

ACTION:

With the regulating rod groups inserted beyond the above insertion limits.

(in a region other than acceptable operation), or with any group sequence or overlap outside the specified limits, except for surveillance testing ptrsuant. to Specification 4.1.3.1.2, either:

a.

Restore the regulating groups to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position using the above figures within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or c.

Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

NOTE:

If in unacceptable region, also see Section 3/4,1,1,1.

s "See Special Test Exceptions 3.10.1 and 3.10.2.

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DAVIS-SESSE, UNIT 1 3/4 1-26 Amendment No.yFf,73,41 4

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UNACCEPTABLE OPERATION 80 S (252,80) r 5

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SHUTDOWN LIMIT g

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shutdown margin) c$<7 g

(200,50)

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OPERATION g

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10 0 200 30 Rod Index (%4rithdrawn 3$

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CR 7 5 25 lb0 TECHNICAL SPECIFICATION FIGURE 3.1-2b Regulating Group Position Limits, After 150 +10 EFPD, Four RCPs - Davis Besse 1, a

Cycle 2

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Rod Index ( % withdrawn)

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.g TECHNICAL SPECIFICATION FIGURE 3.1-3a Regulating Group Position Lintt s4 0 to 150 +10 l

EFPD, Three RCPs - Davis Besse 1, Cycle 2

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ADMINISTRATIVE CONTROLS power operation), supplementary reports shall be submitted at lea'st every three-months until all three events have been completed.

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ANNUAL OPERATING REPORT I -

6.9.1.4 Annual reports covering the activit'es of the unit during the previous calendar year shall be submitted prior to F. arch 31 of each year.

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i The initial report shall be submitted prior to March 1 of the year following initial criticality.

9 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 i

exposures greater than 100 mrem /yr and their assog}ated inan F

rem exposure according to work and,iob functions r e.g.,

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reactor operations and surveillance, inservice inspection.

routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty funct1oc. may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20!, of tha individual total dose need e

n'>t be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

l' b.

The complete results of steam generation tube inservice inspections (Specification 4.5.5.b)..

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MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.

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with a copy to the Regional Office,.to arrive no later than the 15th of each l

Imonth following the calendar month covered by the repor.t.

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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 units at the-station.

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This tabulation supplements the requirements' of 520.407 of-

~10 CFR Part 20.

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DAVIS-BESSE,bNIT1.

6-15 Ainendment tio. ff(41

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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 p event recurrence, shall j'

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 6.9.1.8 The types of events listed below r. hall 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 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 systems 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 speci fications.

c.

Abnormal degradation discovered in fuel cladding, reactor l

coolant pressure boundary, or primary containment.

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betivity anomalies invdiving disagreement with the predicted l

value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOWN MAPGIN r

less conservative than'specified in the technical specifica-tions; short-term reactivity increases that correspond to a reactor period of.less than 5 seconds or, if suberitical, an unplan_ned reactivity insertion of more than 0.5% ak/k; or i

occurrence 'of any unplanned criticality.

DWIS-IIESSE, UNIT 1 6-1C AmendmentNo.k12l r

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