ML20082S638

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Amends 79 & 70 to Licenses DPR-19 & DPR-25,respectively, Specifying Reactor Pressure While Conducting Scram Testing Following Refueling
ML20082S638
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/12/1983
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082S640 List:
References
NUDOCS 8312140235
Download: ML20082S638 (8)


Text

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UNITED STATES g

NUCLEAR REGULATORY COMMISSION r

e WASHINGTON, D. C. 20555 5

%,.....,o COMMONWEALTH EDIS0N COMPANY Docket No.

50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 79 License No. DPR-19 1.

The Nuclear Regulatory Commission (the Co=ission) has found that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated May 2, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulaticns 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; 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.

8312140235 831212

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications ?.s indicated in the attachment to this license amendnent and paragraph 3.8 of Provisional Operating License No. DPR-19 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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D N.YuthNekch CN Operating Reactors B nch #5 Division of Licensing

Attachment:

1.

Changes to the Technical Specifications Date of Issuance: December 12, 1983 l

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ATTACHMENT TO LICENSE AMENDMENT fl0. 79

. PROVISIONAL OPERATING LICENSE NO. OPR-19 DOCKET NO. 50-237 Replace.the following page of the Appendix A Technical Specifications with the enclosed page.

This page contains the captioned amendment number and vertical lines indicating the changes.

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3.3 1.lMITING CONDITION Toll Ol't!!!ATIOtt 4.3 MJitVlill.l.ANCli Ill!QlllRiiHl:N13 8

C.

Scram Insertion Times C.

Scram Insertion Times 1.

The average scraim insertion time, based on the de-energ12ation of the scram pilot After each refueling outage, prior to operation 1.

valve solenoids as time zero, or all oper-greater than 30 percent of rated thermal power, all control rods shall be subject i

ablo control rods in the reactor power to scram-time oiscration condition shall be no greater than; tests from the fully withdrawn position with reactor pressure above 800 psig.

If the control rods are tesced individually, their hydraulic control

% Inserted From Avg. Scram Insertion units shall be isolated from the control rod drive e -

Fully Nithdrawn Times (sec) pumps.

5 2.

At 16 week intervals, at least 50% of the control l

0.375 0.900 rod drives shall be tested as in 4.3.C.1 so that 20 50 every 32 weeks all of the control rods shall have 2.00 been tested.

Whenever 50% or more of the control l

90 3.50 rod drives have been tested, an evaluation shall be made to provide reasonable assurance that proper The uverage of the scram insertion times control rod drive performance is being maintained.

for the three fastest control rods of all I

3.

Following completion of each set of scram testing groups of four control rods in a two by two as described above, the results will be compared array' shall be no greater tisan:

against the average scram speed distribution used in the transient analysis to verify the applica-

% Inserted From Avg. Scram insertion bility of the current MCPR Operating Limit.

to specification 3.5.x.

Refer Fully Withdrawn Times (sec) 5 0.398 20 0.954*

50 2.120 90 3.800 2.

The maximum scram insertion time for 90%

insertion of any operabic control rod shall not exceed 7.00 seconds.

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Amendoent No. ) I. /S 79 58

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UNITED STATES

'^Q NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C, 20555

'.....,o COMMONWEALTH EDIS0N COMPANY Docket No.

50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No. 70 License No. DPR-25 1.

The_ Nuclear Regulatory Commission (the Commission) has fcund that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated May 2, 1983 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

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in 10 CFR Chapter I:

B.

The facility will cperate 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; E.

The-issuance of this amendment is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-25 is hereby anended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

i FOR THE NUCLEAR REGULATORY COMMISSION W

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Dennis M. Crutc field, ief Operating Reactors Branch #5 Division of Licensing

Attachment:

1.

Changes to the Technical Specifications Date of Issuance: December 12, 1983 J

I e

l ATTACHMENT TO LICENSE AMENDMENT N0. 70 FACILITY OPERATING LICENSE NO. OPR-25 DOCKET NO. 50-2a5 Replace the following page of the Appendix A Technical Specifications

.with the enclosed'page. This page contains the ca'ptioned amendment number and vertical lines indicating the changes.

Replace Pace 58 4

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3. 3 1,lMITING CONDITION TOlt Ol'ailtATION E.3 SURVi!!I.I.ANCl! Ill:tjlllRl!Ml!N13 C.

Scram Insertion Times c.

Scram Insertion Times 1.

"Ihc average scram insertion time, based 1.

After each refueling outage, prior to operation on the de-energitation of tlic scram pilot greater than 36 percent of rated thermal power, valve solenoids as time zero, of all oper-all control rods shall be subject to scraw-time.

able control rods in the reactor power tests from the fully withdrawn position with reactor operation condition shall be no greater than:

pressure above 800 psig.

If the control rods are tested individually, their hydraulic control units shall be isolated from the control rod drive

% Insertad From Avg. Scram Insertion ptmps.

Fully Withdrawn Times (sec) 2.

At 16 week intervals, at least 50% of the control l~

5 0.375 rod drives shall be tested as in 4.3.C.1 so that 20 0.900 every 32 weeks all of the control rods shall have been tested.

Whenever 50% or more of the control l

50 2.00 r d drives have been tested, an evaluation shall 90 3.50 be made to provide reasonable assurance that proper control rod drive performance is being maintained.

"ihe average of the scram insertion times for the three fastest control rods of all 3

Following completion of each set of scram testing as described above, groups of four control rods in s two by two the results will be compared against the average scram speed distribution used array shall be no greater than:

in the transient analysis to verify the applica-bility of the current MCPR Operating Limit.

% Inserted From Avg. Scram Insertion Refer Fully Withdrawn Times (sec) 5 0.398 20 0.9r4 50 2.120 90 3.800

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2.

"Ihe maximum scram insertion time for 90%

insertion of any operable control rod shall not exceed 7.00 seconds,

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Amendment No.77, 63, 70 58