ML20126D228

Amends 87 & 80 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs to Incorporate GE Std Limits on Dose Equivalent I-131 in Primary Coolant & Action Statements to Survey Limits Per SEP Topics VI-7.C.1 & XV-16

ML20126D228
Person / Time
Site:	Dresden
Issue date:	05/30/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126D231	List: ML20126D228 ML20126D238
References
TASK-06-07.C1, TASK-15-16, TASK-6-7.C1, TASK-RR NUDOCS 8506140683
Download: ML20126D228 (27)

Text

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UNITE 3 8TATES NUCLEAR REOULATORY COMMISSION n

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WASHINGTON, D. C. 20666

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COMMONWEALTH EDISON COMPANY

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DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 87 License No. DPR-19 1.

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

A.

The application for amendment by the Commonwealth Edison Company (t% licensee) dated February 10, 1984, le, er dated August 2, 1984, complies with the standardsas supplemented b 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 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 pubife, 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 i

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 of the Comission's regulations and all applicable requirements have t

been satisfied, i

i I

i 0506140603 850530 yDR ADOCK 05000237 PDR

' 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 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. 87, 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 W

f A John A. Zwolinski, Chief Operating Reactors Branch #5 Mvision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 30, 1985

1 1

f ATTACHMENT TO LICENSE AMENDMENT N0. 87 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 below and inserting the attached pages. Revise Appendix A T the captioned amendment number and contain marginal lines ind area of change.

REMOVE INSERT 3/4.6-3 3/4.6-3 3/4.6-4 3/4.6-4 3/4.6-5 3/4.6-5*

3/4.6-6 3/4.6-6*

3/4.6-7 3/4.6-7*

3/4.9-1 3/4.9-1 3/4.9-4 3/4.9-4 3/4.9-5 3/4.9-5*

3/4.9-6 3/4.9-6*

B 3/4.9-7 B 3/4.9-7

• Pagination change only

s DRESDEN II DPR-19 Amerdment No. )4, pt, 87 3.6 LIMITING CONDITION FOR OPERATION (Cont'd.)

4.6 SURVEIf1 AMCE REOUIREMENT (Cont'd.)

3.

Neutron flux monitors and samples shall be installed in the reactor vessel adjacent to the vessel wall at the core midplane level.

The monitor and sample program where possible conform to ASTM E 185.

The monitors and samples will be removed and tested as outlined in Table 4.6.2 to experimentally verify the calculated values of integrated neutron flux that are used to determine NDTT for Figure 4.6.1.

C.

Coolant Chemistry C.

Coolant Chemistry 1.

a.

The reactor coolant activity shall be main-1.

a.

A sample of reactor tained less than 0.2 coolant shall be microcuries per gram taken at least DOSE EQUIVALENT I-131 every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and during Reactor Power analyzed for DOSE operation, EQUIVALENT I-131 and total activity content.

b.

If the reactor coolant activity is greater b.

When an isotopic than 0.2 microcuries analysis shows per gram and less than reactor coolant or equal to 4.0 micro-activity to be in curies per gram DOSE excess of 0.2 EQUIVALENT I-131, for microcuries por more than 48 continuous gram and less than hours (one continuous 4.0 microcuries per time interval) an orderly gram DOSE EQUIVALENT shutdown shall be immedi-1-131, additional reactor coolant 3688a 3/4.6-3 3123A

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I DRESDEN II DPR-19 Amende.ent No. Jd, yt, gy 3.6 LIMITING CONDITION FOR OPERATION (Cont'd.)

4.6 SURVEILLANCE REQUIREMENT (Cont'd.)

~

ately initiated and the unit shall be in cold samples shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

taken and analyzed i

at least 3 times every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If a sample of reactor c.

coolant activity is greater When reactor coolant c.

than 4.0 microcuries per activity is greater gram DOSE EQUIVALENT I-131, than 4.0 microcuries a second sample shall be per gram DOSE EQUIV-taken and analyzed within ALENT 1-131, reactor 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

If the second coolant samples sample indicates a reactor shall be taken and coolant activity greater analyzed every 8 than 4.0 microcuries per hours until the gram DOSE EQUIVALENT I-131, reactor is in a cold an orderly shutdown shall shutdown condition.

be initiated and the unit shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Should the second sample indicate a reactor coolant activity less than or equal to 4.0 microcuries per gram DOSE EQUIVALENT I-131, state-ment 3.6.C.1b shall apply.

2.

The reactor coolant water shall not 2.

During startups and at exceed the following steaming rates below limits with steaming 100,000 pounds per rates less than hour, a sample of 1

100,000 pounds per reactor coolant shall hour except as be taken every four specified in 3.6.C.3:

hours and analyzed for Conductivity 2 micro-aho/cm conductivity and Chloride ion 0.1 ppm chloride content.

3.

For reactor startups the maximum value 3.

a.

With steaming rates

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for conductivity greater than or shall not exceed 10 equal to 100.000 micro-sho/cm and the pounds per hour, a maximum value for reactor coolant chloride ion sample shall be concentration shall taken at least not exceed 0.1 ppa, every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and for the first 24 when the continuous conductivity 3688a 3/4.6-4

DRESDEN 11 DPR-19 AmeIdment N3. f6, pt, 87 3.6 LIMITING CONDITION FOR OPERATION (Cont'd.)

4.6 SURVEILLANCE REOUIREMENT (Cont'd.)

hours after placing the reactor in the monitors indicate Power operating abnormal conductivi-condition.

(other than short-term spikes) and analyzed for conduc.

tivity and chloride ion content.

t b.

When the continuous i

conductivity monitor is inoperable, a reactor coolant samp should be taken at least daily and analyzed for conductivity and 4.

Except as specified in chloride ion content.

3.6.C 3 above, the reactor coolant water shall not exceed the following limits with steaming rates greater than or equal to 100,000 pounds per hourt conductivity 5 micro-sho/cm chloride ion 0.5 ppm 5.

If specification 3.6.C.1, 3.6.C.2, 3.6.C.3 or 3.6.C.4 is not met, an orderly shutdown shall be initiated.

D.

Coolant Leakage D.

Coolant Leakage

{

1.

Any time irradiated fuel is in the 1.

Reactor coolant system reactor vessel and leakaBe shall be reactor coolant checked by the sump temperature is above and air sampling 212*F, reactor system.

Sump flow coolant leakage into monitoring and the primary recording shall be containment from performed once per unidentified sources 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Air sampling shall not exceed 5 shall be performed once per day.

3688a 3/4.6-5 f

DRESDEN 11 DPR-19 Ame:dme:t N3. %, pt, 87 3.6 LIMITINC CONDITION FOR OPERATION 4.6 SURVIILLANCE REOUIREMENT (Cont'd.)

(Cont'd.)

spm.

In addition, the total reactor coolant system leakage into the primary containment shall not exceed 1

25 spm.

If these conditions cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

After complation of the 2.

The following additional investigation, or con-leakage limits shall be tainment inspection, met until the recircula-specified in 4.6.D.2.a tion piping indications or 4.6.D.2.b. if the have been resolved.

leakage is determined to be due to a thru wall Whenever the reactor is pipe crack on the reactor at operating pressure, coolant pressure boundary, the following will apply an nederly shutdown shall to unidentified leakage:

be initiated and the reactor shall be in a a.

If a 1 spa increase Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, over the previous 4 l

hours occurs or when leakage equals 3 spa total, an investigation of the cause of the leakage increase will be performed.

This in-vestigation should consist of taking drywell air and water samples, and a review of any previous plant evolutions to the estent,

necessary to determine the source of leakage.

b.

If leakage equals 4 spa, a containment inspection will be conducted to determine the source of leakage.

E.

Safety and Relief Valves E.

safety and gelief Valves 1.

During reactor power A minimum of 1/2 of all operating conditions and safety valves shall be whenever the reactor bench checked or replaced coolant pressure is greater with a bench checked valve than 90 psis and temperature each refueling outages.

3/4.6-6 3688a

DRESDEN II DPR-19 e

4 Ame:daent No. J, pt, 87 1

3.6 LIMITING CONDITION FOR' OPERATION 4.6

$URVEIf f "CE REQUInnurNT j

(Cont'd.)

(Cont'd.)

greater than 320'F, all nine of the safety valves shall The popping point of the safety valves shall be set be operable. The solenoid as follows:

activated pressure valves shall be operable as' required by specification 3.5.D.

M-He of Valves set Point i

(Psia) 1 11358 i

2 1240 2

1250 2

1260 2

1260 The allowable set point error for each valve is plus or i

minus it.

All relief valves shall be checked for set pressure each refueling outage. The set pressures shall be 2.

If Specification Valve Mo, Set Point (osis) 3.6.E.1 is not met, an orderly shutdown 203-3A 11248 shall be initiated i

203-38 1101 and the reactor 203-3C 1101 coolant pressure and 203-3D 1124 temperature shall be 203-3R 1124 less than or equal to 90 psis and less than a Target rock combination safety / relief valve.

or equal to 320' F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The allowable setpoint error for each valve is plus or minus it.

F.

Structural Integrity F.

Structural Integrity The structural integrity 1.

Beginning November 1, i

of the primary system 1970s and. updated every boundary shall be 40 months thereafter maintained at the level theComponentinserVkCe required by the ASME insptCtion program Boiler and pressure Shall be performed in Vessel Code, section XI, accordance with Section atulos for Inservie.

XI Of the ASME 80iler i

Inspection of Nuclear and Pressure Vessel Power plant components".

Code and Addenda as Components of the required by 10 CFR 50, primary system boundary Section 50.55a(g),

whose inservice except where specific examination reveals the written relief has been absence of flaw given by the NRC indications or flaw pursuant to 10 CFR 50 Section50.55a(g)(6)(i),

3/4.6-7 36aSa

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La th_J EU DPR-19 Amendment No. )d, Pf, 87 o

a 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT AUXILIARY ELECTRICAL SYSTEMS AUXILIARY ELECTRICAL SYSTEMS Apolleability:

Apolleability:

Applies to the auxiliary electrical power system.

Applies to the periodic testing requirements of the auxillary electrical system.

Obiective:

Ob3ectiver To assure an adequate supply of electrical power during Verify the operability of the plant operation.

aux 111ary electrical system.

Soeelfleation:

Soeelfleation:

A.

The reactor shall not be A.

Station Batteries made critical unless all the following requirements are satisfied:

1.

One 345 KV line, 1.

associated switchgear, Every week the specific and the reserve gray!Ly, voltage and auxiliary power temperature of the pilot cell and transformer capable of carrying power to overall battery t' nit 2.

voltage shall be measured.

2.

The Dresden 2 diesel 2.

Every three months the generator and the Unit 2/3 diesel measurements shall be generator shall be made of voltage of each

operable, cell to nearest 0.01 volt, speelfic gravity i

of each cell, and temperature of every fifth cell.

3.

An additional source 3.

of power consisting Every refueling outage, of one of the the unit's batterles following shall be subjected to a rated load discharge test.

Determine (a) One other 138 KV line, fully specific gravity and voltage of each cell operational and after the discharge.

3/4.9-1 3693a 3124A

DRESDEN II DPR-19 Ame:dme:t No. 92, 87 e

3.9 LIMITING CONDITION FOR OPERATION 4.9

$URVETLLANCE REQUIREMENT (cont'd.)

(Cont'd.)

operable, provided that during such anyon days the operable diesel generator shall be demonstrated to be operable at least once each day and two off-site lines are available.

3.

From and after the date that one of the two 125 or 250V battery systems is made or found to be inoperable, except as specified in 3.9.3.4a or b, Unit shutdown shall be initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the unit shall be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the failed battery can be sooner made operable.

4.

a.

Each 125 or 250 volt battery may be in-operable for a mant-num of 7 days per operating cycle for maintenance and

testing, b.

If it is determined that a battery need be replaced as a result of mainton-ance or testing, a specific battery may be inoperable for an additional 7 days per operating cycle.

3/4.9-4 3693a 3124A

DRESDEN II DPR-19 Amendment No pt, 37 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT l

(Cont'd.)

(Cont'd.)

C.

Diesel Fuel C.

Diesel Fuel l

There shall be a minimum Once a month the quantity i

of 10,000 gallons of of diesel fuel available diesel fuel supply on shall be logged.

i site for each diesel.

Once a month a sample of diesel fuel shall be checked for quality.

D.

Diesel Generator D.

Diesel Generator operability operability l

Whenever the reactor is 1.

Each diesel generator

}

in the Cold shutdown or shall be manually l

Refueling modes, a started and loaded once minimum of one diesel each month to generator (either the demonstrate operational I

Dresden 2 diesel generator readiness. The test I

or the Unit 2/3 diesel shall continue untti generator) shall be both the diesel engine

(

operable whenever any work and the generator are is being done which has at equilibrium the potential for conditions of draining the vessel, temperature while full l

secondary containment is load output is required, or a core or maintained.

containment cooling system la required.

2.

DJring the monthly l

generator test the diesel starting air compressor shall be checked for operation and its ability to recharge air receivers.

3.

During the monthly generator test the diesel fuel oil transfer pumps shall be operated.

4.

Additionally, during each refueling outage, a simulated loss of off-site power in 3/4.9-5 p

3693a 3124A 1

DRESDEN II DPR-19 Amendment No. %, 37 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVETLt.At?CE REQUI!fdHENT (Cont'd.)

(Cont'd.)

conjunction with a' ECCS Inttlatlon signal test shall be performed on tl 4160 volt emergeni bus by:

(a) Verifying de-energization o a

the emergency bus.

and load shedding l from the emergenc; buses.

(b) Verifying the diesel starts fro ambient condition on the auto-start signal, energizes the emergency buse with permanently connected loads, energizes the auto-connected emergency loads through the load seguencer, and operates for greater than or equal to 5 minute while its generate is loaded with th.

emergency loads.

3/4.9-6 3493a 3124A

DRESDEN II Dpt-19 4

AmeIdee2tNo.Pt,87 6

2 3.9 LIMITING CONDITION FOR OPERATION R&BES l

1 l

5 A.

The general objective of this Specification is to assure an l

adequate source of electrical power to operate the auxillaries i

during plant operation, to operate fac111tles to cool and lubricate the plant during shutdown, and to operate the engineered safeguards following an accident. There are three sources of electrical energy availables namely, the 133 KV l

l trans,alssion system, the diesel generators, and the 345 KV transmission system through the 4160 volt bus tie.

The d-c supply is required for control and motive power for switchgear and engineered safety features.

The electrical power required provides for the maximum availability of power; i

1.e., one active off-site source and two back-up sources of j

off-site power and the maximum amount of on-site sources, j

3.

Aus111ary power for Unit 2 is supplied from two sources, either the Unit 2 ausillary transformer or the Unit 2 reserve i

auslitary transformer. soth of these transformers are sized i

to carry 1001, of the ausillary load.

If the reserve auxillary transformer is lost, the unit can continue to run for 7 days since the unit aus111ery transformer is avs11able and both diesel generators are operational. A reduced period is pro-vided since if an accident occurs during this period, the unit i

i would trip and power to the unit auxillary transformer would l

be lost and the diesels would be t'se only source of power.

[

i In the normal mode of operation the 133 KV system is operating j

l and two diesel generators are operational. One diesel gener-t ator may be allowed out of service based on the availability l

of power to the 133 KV switchyard, a source of power available l

1 from the 345 KV system through a 4160 volt bus tie and the l

l fact that one diesel carries sufficient engineered safeguards j

equipment to cover all breaks.

Off-site power is gutte re-liable.

In the last 25 years there has only been one instance in which all off-site power was lost at a cosusonwealth Edison i

generating station.

i 4

Two battery chargers are supplied for each of the 125 volt batteries, while for the 250 volt system a battery charger is

[

supplied for each battery and a third battery charger acts as a shared unit. Thus, on loss of a battery charger, another i

battery charger is available.

Since an alternate sharger is avellable, one battery charger per unit for the 125 volt and one battery charger overall for the 250 volt battery system

[

een be out of service for thirty days. The system besemos j

i inoperable whenever there is a loss of the battery or loss of j

both chargers for that system and a battery voltage of 105 f

volts for the 125 or 210 volts for the 250 volt batteries.

B 3/4.9-7 l

l 1

I i

3693a I

3124A l

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[g UNITEJ STATES NUCLEAR MEGULATORY COMMISSION c

5 WASHlNGTON, D. C. 20066 j

l l

COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 80 l

License No. DPR-25 1.

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

l A.

The application for amendment by the Comonwealth Edison Company (the licensee) dated February 10, 1984, as supplemented by a letter dated August 2, 1984, complies with the standards and requirements of the Atomic Eeargy Act of 1954, as amended (the Act), and the Commission's vules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the Act ev1d 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 (11) that such act<vities 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 Comission's regulations and all applicable requirements have been satisfied.

2-2.

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. OPR-25 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, 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 NJCLEAR REGULATORY COMMISSION V

&$f

'f4 John A. Zwolinski, Chief Operating Reactors Branch f5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 30, 1985.

ATTACHMENT 70 LICENSE AMENOMENT N0. 80 FACILITY 0PERATING LICENSE DPR-25 D0CKET N0. 50-249 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4.6-3 3/4.6-3 3/4.6-4 3/4.6 4 3/4.6-5 3/4.6-5*

3/4.6 6 3/4.6 6*

3/4.6-7 3/4.6-7*

3/4.9-1 3/4.9-1 3/4.9-4 3/4.9 4 3/4.9-5 3/4.9-5*

3/4.9 6 3/4.9 6*

8 3/4.9-7 8 3/4.9-7

' Pagination change only

DRESDEN III DPR-25 Ame-dme~:t N3. f4. 7/. 80 3.6 LIMITINC CONDITION FOR OPenATION 4.6 3URVEILLANCE REQUIntMENT (Cont'd.)

(Cont'd.)

3.

Neutron flux monitors and samples shall be installed in the reactor vessel adjacent to the vessel wall at the core midplaae level.

The monitor and sample program where possible conform to ASTM E 185.

The monitors and samples will be removed and tested as outlined in Table 4.6.2 to experimentally verify the calculated values of integrated neutron flux that are used to determine NOTT for Figure 4.6.1.

C.

Coolant Chemistry C.

Coolant Chemistry 1.

a.

The reactor coolant 1.

a.

A essple of reactor activity shall be main-coolant shall be tained less than 0.2 taken at least microcuries per gram every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and Dost EQUIVALENT 1-131 analysed for Dott during teactor power EQUIVALENT I-131 operation.

and total activity content.

b.

If the reactor coolant b.

When an isotopic activity is greater analysis shows than 0.2 microcuries reactor coolant per gram and less than activity to be in or equal to 4.0 micro-escess of 0.2 suries per gram Dost microcuries per EQUIVALENT 1-131, for gram and less than more than 40 continuous 4.0 microcuries per hours (one continuous gram DOSE EQUIVALENT time laterval) en orderly 1-131, additional shutdown shall be immedi-reactor coolant 3/4.6-3 3891a 3123A

Dtt3 DEN III DPR-25 Ame;daent No. %, K 80 3.6 LIMITING CONDITION FOR OPttATION 4.6 $URVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

stely initiated and the samples shall be unit shall be in cold taken and analyzed shutdown within h4 hours.

at least 3 times every 2A hours.

c.

If a sample of reactor c.

When reactor coolant coolant activity is greater activity is greater than 4.0 microcuries per than 4.0 microcuries gram DOSE EQUIVALENT I-131, per gram DOSE EQUIV-a second sample shall be ALENT I-131, reactor taken and analyzed within coolant samples 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

If the second shall be taken and sample indicates a reactor analysed every 8 coolant activity greater hours untti the than 4.0 alcrocuries per reactor is in a gram DOSE EQUIVALENT I-131, cold shutdown cond!-

an orderly shutdown shall tion.

be initiated and the unit shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Should the second sample indicate a reactor coolant activity less than or equal to 4.0 alcrocuries per gram D088 IQUIVALENT I-131, state-ment 3.6.C.1b shall apply.

2.

The reactor coolant 2.

During startups and at water shall not steaming rates below exceed the following 100.000 pounds per limits with steaming hour, a sample of rates less than reactor coolant shall 100,000 pounds per be taken every four hour except as hour's and analysed for specified in 3.6.C.3:

conductivity and chloride content.

Conductivity 2 alcro-sho/cm Chloride ton 0.1 ppe 3.

For reactor startups 3.

a.

With steaming rates the maalaus value greater than or for conductivity equal to 100,000 shall not onceed 10 pounds per hour, a alero-sho/cm and the reactor coolant assimum value for sample shs11 be chloride ton taken at least concentration shall every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and not escoed 0.1 ppa, when the continuous for the first 24 conductivity 3/4.6-4 3897a 3123A

DRE3 DEN III

_DFR-25 Ame:dment No. K. 7,80 3.6 LIMITING CONDITION FOR OPERATION 4.6 $URVIILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

hours after placing monitors indicate the reactor in the abnormal power operating conductivity (other condition.

than short-term spikes) and analysed for conductivity and chloride ion content.

b.

When the continuous conductivity monitor is inoFerable, a reactor coolant sample should be taken at least daily and analyzed for conductivity and chloride ion content.

4 Escept as speelfled in 3.6.C.3 above, the reactor coolant water shall not onceed the following limits with steaming rates greater than or equal to 100,000 pounds per hour:

Conductivity 5 micro-sho/cm Chloride ton 0.5 ppm 5.

If specification 3.6.C.1, 3.6.C.2, 3.6.C.3 or 3.6.C.4 is not met, an orderly shutdown shall be initiated.

D.

Coolant Leakage D.

Coolant Leskage 1.

Any time irradiated 1.

Reactor coolant system fuel is in the leakage shall be resetor vessel and shocked by the sump reactor coolant and air sampling temperature is above system. Sump flow 212'F, reactor monitoring and toelant leakage into recording shall be the primary performed once per containment from shift. Air sampling unidentitled sources shall be performed shall not escoed S once per day.

3/4.6-5 l

3897a 31234

DRESDEN III DpR-25 Amendment No. % J'1, JV, 80 3.6 LIMITING CONDITION FOR OPERATION 4.6 8URVEILLANCE_ REQUIREMENT (Cont'd.)

(Cont'd.)

gPa.

In addition, the total reactor coolant system leakage into the primary containment shall not exceed 25 gPa.

If these conditions cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

The primary 2.

The primary containment sump containment sump sampling system and stapling and air an air sampling sempling system system shall be operability will be operable during observed as part power operation.

of 4.6.D.2.

If either a sump water semple or a containment air sample cannot be obtained for any reason, reactor operation is permis-sible ca.ly during the succeeding 33y.gg days unless the system is made operable during this period.

E.

Safety and Relief Valves E.

Safety and Relief Valves 1.

During reactor power A minimum of 1/2 of all operating conditions safety valves shall be and whenever the bench checked or replaced reactor coolant pressure with a bench shocked valve is greater than 90 each refueling eettges.

psig and temperature The popplag point of the greater than 320'F, safety watves shall be set all nine of the as follows:

safety valves shall be operable. The Mumher of Valves Ret point solenoid activated iggigl pressure valves shall be operable as 1

1135a required by 2

1240 speelfication 3.5.D.

2 1250 2

1240 2

1260 (See nest page) 3/4.6-4 3897a e

DRESDEN III DPR-25 Amendment No. p6. ft. fl. N 80 3.6 LIMITING CONDITION FOR OPERATION 4.6

$URVIILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

The allowable set potet error for each valve is plus or alnus 1%.

All relief valves shall be checked for set pressu e each refueling outase. The set pressures shall ber 2.

If Speelfication valve No.

Set Point (nsin) 3.6.E.1 is not met, an orderly shutdown 203-3A 1124*

shall be initiated 203-3B 1101 and the reactor 203-3C 1101 coolant pressure and 203-3D 1124 temperature shall be 203-3E 1124 less than or equal to 90 pels and less than

• Target Rock combination or equal to 320' F safety / relief valve within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The allowable setpoint error for each valve is plus or minus 1%.

F.

Structural Integrity F.

Structural Integrity The structural inteseity 1.

Beginning November I.

of the primary system 1g78, and. updated every boundary shall be 40 months thereafter maintained at the level the component interVIce required by the ASNE inspection program toller and pressure shall be perforised in Vessel Code. Jeetton II.

accordance with Section "tulos for Inservice XI of the ASM Boiler Inspection of Nuclear and Pressure Yellel power plant Components".

Code and Addenda as required by 10 CFR 50, Ceepenents of the Section50.55a(g),

primary system boundary except where specific whose inservlee esamination reveals the written relief has been absence of flew given by the NRC indleattens or flew pursuant to 10 CFR 50 indleattens not in eseess Section50.55a(g)(6)(I).

of the allowable indicatten standards of this Code are seseptable for sentinued servlee.

Plant operation with components whleh have inservlee esaminatten flew 3/4.6-7 P IYh

.. ~.

DRESDEN.III DPR-75 Amandmsnt No. $6, 74, 80 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REOUIREMENT AUKILIARY ELECTRICAL SYSTEMS AUXILIARY ELECTRICAL SYSTEMS Applicability:

Applicability:

Applies to the auxiliary Applies to the periodic testing electrical power system.

requirements of the auxiliary electrical system.

Ob3ective:

Objective:

To assure an adequate supply Verify the operability of the' of electrical power during auxiliary electrical system.

Plant operation.

Specification:

Specification:

A.

.The reactor shall not be A.

Station Batteries made critical unless all the following requirements 4

are satisfied:

1.

One 345 KV line, 1.

Every week the specific associated switchgear, gravity, voltage and and the reserve temperature of the auxiliary power pilot cell transformer capable and overall of carrying power to battery voltage shall Unit 3.

be measured.

2.

The Dresden 3 diesel 2.

Every three months the generator and the measurements shall be Unit 2/3 diesel made of voltage of each

(

generator shall be cell to nearest 0.01 operable.

volt, specific gravity of each cell, and temperature of every fifth cell.

3.

An additional source 3.

Every refueling outage, of power consisting the unit's batteries of one of the shall be subjected to a l

following:

rated load discharge j

test.

Determine (a) One other 345 KV specific gravity and line, fully voltage of each cell operational and after the discharge.

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3901a 3124A

DRESDEN III DPR-25 Am:ndm3nt No. }4, 80 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

operable, provided that during such seven days the operable diesel generator shall bc.

demonstrated to be operable at least once each day and two off-site lines are available.

3.

From and after the date that one of the two 125 or 250V battery systems is made or found to be inoperable, except as specified in 3.9.B.4a or b, Unit shutdown shall be initiated

~

within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the unit'shall be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i

unless the failed battery can be sooner made operable.

4.

a.

Each 125 or 250 volt battery may be inoperable for a maximum of 7 days per operating cycle for maintenance and testing.

l b.

If it is determined that a battery need l

be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional 7 days Per operating cycle.

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3901a 3124A

DRESDEN III DPR-25 Amenda:nt No. 7/, 80 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

C.

Diesel Fuel C.

Diesel Fuel There shall be a minimum once a month the quantity of 10,000 gallons of of diesel fuel available

• diesel fuel supply on shall be logged, site for each diesel.

Once a month a sample of diesel fuel shall be checked for quality.

D.

Diesel Generator D.

Diesel Generator Operability Operability Whenever the reactor is 1.

Each diesel generator in the Cold Shutdown or shall be manually Refueling modes, a started and loaded once minimum of one diesel each month to generator (either the demonstrate operational Dresden 3 diesel generator readiness. The test or the Unit 2/3 diesel shall continue until generator) shall be both the diesel engine operable whenever any work and the generator are is being done which has at equilibrium the potential for conditions of draining the vessel, temperature while full secondary containment is load output is required, or a core or maintained.

containment cooling system is required.

2.

During the m:)nthly generator test the diesel starting air compressor shall be checked for operation and its ability to i

recharge air receivers.

3.

During the monthly generator test the diesel fuel oil

[

transfer pumps shall be i

operated.

4.

Additionally, during f

each refueling outage, a simulated loss of off-site power in i

3/4.9-5 3901a 3124A

DRESDEN III DPR-25 Amsndment No. )d, 80 3.9 LIMITINC CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

conjunction with,an ECCS initiation signal test shall be performed on the 4160 volt emergency bus by:

(a) Verifying de-energization of the emergency buses and load shedding from the emergency buses.

(b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected emergency loads through the load sequencer, and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.

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l 3901a 3124A

DRESDEN III DPR-25 Amendment No. J4, 80

(*

3.9 LIMITING CONDITION FOR OPERATION BASES A.

The general objective of this Specification is to assure an adequate source of electrical power to operate the auxiliaries during plant operation, to operate facilities to cool and i

lubricate the plant during shutdown, and to operate the engineered safeguards following an accident. There are three sources of electrical energy available; namely, the 345 KV transmission system, the diesel generators, and the 138 KV transmission system through the 4160 volt bus tie.

The d-c supply is required for control and motive power for l

switchgear and engineered safety features. The electrical l

Power required provides for the maximum availability of power; i.e., one active off-site source and two back-up sources of off-site power and the maximum amount of on-site sources.

B.

Auxiliary power for Unit 3 is supplied from two sources, either the Unit 3 auxiliary transformer or the Unit 3 reserve auxiliary transformer. Both of these transformers are sized to carry 100% of the auxiliary load. If the reserve auxiliary transformer is lost, the unit can continue to run for 7 days 5

since the unit auxiliary transformer is available and both diesel generators are operational. A reduced period is pro-vided since if an accident occurs during this period, the unit would trip and power to the unit auxiliary transformer would be lost and the diesels would be the only source of power.

In the normal mode of operation the 345 KV system is operating and two diesel generators are operational. One diesel generator may be allowed out of service based on the availability of power to the 345 KV switchyard, a source of power available from the 138 KV system through a 4160 volt bus tie and the fact that one diesel carries sufficient engineered safeguards equipment to cover all breaks. Off-site power is quite reliable.

In the last 25 years there has only been one instance in which all off-site power was lost at a Commonwealth Edison generating station.

Two battery chargers are supplied for each of the 125 volt batteries, while for the 250 volt system a battery charger is supplied for each battery and a third battery charger acts as a shared unit. Thus, on loss of a battery charger, another battery charger is available.

Since an alternate charger is available, one battery charger per unit for the 125 volt and one battery charger overall for the 250 volt battery system can be out of service for thirty days.

The system becomes inoperable whenever there is a loss of the battery or loss of both chargers for that system and a battery voltage of 105 s

volts for the 125 or 210 volts for the 250 volt batteries.

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3901a 3124A

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