ML19345C656

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Amends 50,59 & 54 to Licenses DPR-19,DPR-29 & DPR-30, Respectively,Establishing Max Average Planar Linear Heat Generation Rate Limits for Std 8X8 Fuel Types for Exposure Valves
ML19345C656
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 11/12/1980
From: Ippolito T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19345C657 List:
References
NUDOCS 8012080095
Download: ML19345C656 (23)
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UNITED STATES 3

NUCLEAR REGULATORY COMMISSION wassmorow. o. c.20sss e

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C0.TiONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN STATION UNIT N0. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 50 License No DPR-19 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated March 19, 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 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 comon 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 Spec-ifications as indicated in the attachment to this license amendment, and paragraph 3.B 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. 50, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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- 3. :This license. amendment is effective ~ as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 4

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- Thomas

. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing i

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Attachment:

Changes to' the Technical Specifications Date of Issuance:-November 12, 1980 4

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ATTACINENT TO LICENSE AMENDMENT NO. 50 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237'

' Revise the Appendix "A" Technical: Specifications as follows:

. Remove Replace 818 818 818-1 81C 81C-81C-1 81C-1 81C-2 81C-2

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DPR-19 4.5 SURVEILLANCE REQUIREMENT 3.5 LIIIITING CONDITION FOR OPCRATION I.

Average Pinnne Lincar Itcat Generation I.- ' Averaqc Planar IJIGR During steady state power oporation, the -

average linear heat generation rato (LUGR)

The APIJIGR for cach type of fuel as a function of average planar exposure shall of.all the rods in any fuel assembly, as be determined daily during reactor opera-a function of. average pinnar exposure, at any a>:ial location, shall not c:-:cced the tion at 2, 257. rated therraal power.

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ras:cie.um average planar Ll! git shown l'ti.ure 3.5-1 dependent on fr.I-typt.,

If'at any time thering operation it is dete: mined by normal surveillance that th'c-limit ing value for API.llGit is being

,w triled, action shall be initiated within I!. ute.utes to restore operation to within

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the prc:>cribed limits. If the APillGit is not returnel to within the prescribed liriits with-in two (2) hours, the reactor shall be brcught to ti.e Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Surveillance and corresponding action shall u.ntinue initil reactor operation is within the prescriled limits.

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g, Local nygg Duris.g.steadf stat.s power operation,.the The IDC2 as a functio'n of core 11nce r heat generation rate (LHGR) of any height shall be checked daily dur-rod in any fuel assembly at any exial le.

ing reactor operatien at > 25t,

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cation shall not exceed th~e r.aximu a allev rated th:r:s1 po-cr.

able LI:OR as calculated by the following equation.

Lit 0n LHCR 1 - /4 Ph r,

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LIIGil Design IJiGR d

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g bo initiated within 15 cinutes to restore operation to within 6g the prescribed !!!::its.

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UlGR is r.ot returned to within the prescribed ti:Lts g

within two (2) hours, the b

reactor shall be brougist' to the Cold Shutdom condition within 36 hcurs. Sucwell-Isoce and corresponding action 813-1 l

shall continue until s c ac tor eperation is within the prescribed limits.

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Amendment No. 50

d g

UNITED STATES

[

_g NUCLEAR REGULATORY COMMISSION r,

a wasmworow, o.c.rosos x****)

C0tWONWEALTH EDISON COMPANY AND IOWA ILLINOIS GAS D ELECTRIC COMPANY 1

DOCKET NO. 50-254 QUAD CITIES STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-29

1.. The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the Comonwealth Edison Company (the licensee) dated March 19, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 4

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 Comission; 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 Comission's regulations; D.

The issuance of this-amendment will not be inimical to the comon 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-29 is hereby amended to read as follows:

8.

Technical Specifications

)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The -licensee shall operate the facility in accordance with the Technical Specifications.

L

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

FOR THE NUCLEAR REGULATORY COPMISSION Thomac A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changas to the Technical Specifications Date of Issuance: November 12, 1980 b

ATTACtNENT TO LICENSE AMENDMENT NO.- 59

[.

FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise.the Appendix "A" Technical Specifications as follows:

Remove Replace 3.5/4.5-9 3.5/4.5-9 Fig. 3.5-1 (Sheet 1 of 3 Figure 3.5-1 Sheet 1 of 4)

Fig. 3.5-1 (Sheet 2 of 3 Figure 3.5-1 Sheet 2 of 4)

Fig. 3.5-1 (Sheet 3 of 3 Figum 3.5-1 Sheet 3 of 4)

Figure 3.5-1 (Sheet 4 of 4)

_J

v QUAD.CITII/Si DPM-29 cycle by assuring that water can be run through the drain lines and actuating the air operated valves by operation of the following sensorr I) loss of air

2) equipment drain sump high level
3) vault high fevel
d. The condenser pit 5-foot trip cir-cuits for each channel shall 'e checked once a month. A Inc system functional test shall be per-formed during each refueling outage.

1.

Average Planar 1.inear Heat Generation Rate 1.

Average Planar f.inest Heat Generation P m (API.HGR)

( AP,f.fiGRI During steady state power operation, the aver.

The APLifGR for each type of fuel as.: fune-age linear heat generation rate i APLilGR) of tion of average planar exp>sure shall be de:ct-all the rods in any fuel.membly.. s a function mined daily during reactor operation at of average planar espwure as as., asial loca-2 25'I. rated thermal power.

tion. shall not esceed the maximum average l

planar LHGR shown in hgure 3.5-l.

If at any time during operation it is determined by normal surveillance that the limiting value for APLHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to w! hin the prescribed limits. If the APLHGR is not r. turned in within the prescribed limits withi',2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. the reactor shall be brought to it.e cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

J.

local I.HGR J.

local I.lfG't During steady-state piwer operation, the linear Daily during steady state power operat:on heat generation rate t tilGR1of any rod in any above 25% of rated thermal power, the !ccal fuel assembly at any asial location shall not LHGR shall be checked.

e exceed the maximum allowable LHGR as cal-culated by the following equation. If at any time during operation it is determined by not-mal surveillance that the limiting value tiir LHGR is being exceeded. action shall he initi-ated within 15 minutes to restore oper.ition to within the prewribed linists 11 the I.ll(iR is not returned to within the prewribed limits withio

.tsi.ts.9 Amendment No. 59

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% * * * * *,M COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-30 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated March 19, 1980, 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 fortr. in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the proj'sions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by'tnis amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in campliance 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 Commission'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 caragraph 3.B of Facility Operating License No. DPR-30 is hereby amended 10 read as follows:

l l

I B. ' Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, 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 A

4 Id 'b t

s Thomasi Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: - November 12, 1980 4

4 i.

_-,_2._

ATTACHMENT TO LICENSE AMENDMENT NO. 5_4 4

FACILITY OPERATING LICENSE NO. DIR-30 DOCKET NO. 50-265 Revise the Appendix-"A" Technical Specifications as follows:

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