ML20116A879

Amends 119,115,138 & 134 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising Tech Specs Re Auxiliary Electrical Sys

ML20116A879
Person / Time
Site:	Dresden, Quad Cities
Issue date:	10/19/1992
From:	Siegel B Office of Nuclear Reactor Regulation
To:
Shared Package
ML20116A881	List: ML20116A879 ML20116A890
References
NUDOCS 9210300192
Download: ML20116A879 (62)

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UNITED STATES 8' -

I 4 NUCLEAR REGULATORY COMMISSION n

WASHINGTON. D. C. 20555

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CQ_MMQNWEALTH EDISON COMPANY ILOCKET NO. 50-231 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.119 License No. DPR-19 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated June 29, 1992, as supplemented August 28, 1992, 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 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 i

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.

l 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:

92103hh PDR P

. (2)

Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No.119, 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 to be implemented within 60 days.

FOR 1HE NUCLEAR REGULATOR' COMMISSION

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Ric a

. Barret, Director Proje'ct Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: October 19, 1992

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'e ATTACHMEN1--T0 L ICENSE AMENDMENT NO. - 119 4

FAClllTY OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Revise the Appendix A Technical Specifications by removing the pa9es-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 iv iv vi vi 3/4.9-1 3/4.9-1 3/4.9-la 3/4.9-2 3/4.9-2 3/4.9-3 3 /4. 9-3 3/4 9-3a 3/4.9-4 3/4.9-4 3/4.9-5 3/4.9-5 3/4.9-Sa 3/4.9-6 3/4.9-6 B 3/4.9-7 8-3/4.9-7 B 3/4.9-7a B 3/4.9-8 8 3/4 9 --

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DRE50EN Il DPR-191 Amencment ' No. 119 (Table of Contents, Cont'd.)

P39e 3.9.C Diesel fuel 3/4.9 - Sa

3. 9. D Diesel Generator Operability 3/4. 9 - S a Limiting Conditions for Operation Bases (3.9)

B 3/4. 9 - 7 Surveillance Requirement Bases (4.9)

B 3/4.9 - 8 3.10 Refueling 3/4.10- 1 3.10.A; Refueling Interlocks 3/4.10--1 3.10.B Core Monitoring 3/4.10- 1 3.10.C fuel Storage Pool Water Level 3/4.10- 2 3.10.D Control Rod and Control Rod Drive Maintenance 3/4.10- 3 3.10.E Extended Core Maintenance 3/4.10- 4 3.10.F 5 pent fuel Cask Handling-3/4.10- 5 Limiting Conditions for Operation Bases (3.10)

B 3/4.10- 9 Surveillance Requirement Bases (4.10)

B 3/4.10- 12 3.11 High Energy Piping Integrity (outside containment) 3/4.11-1 Limiting Conditions for Operation Bases (3.11)

B 3/4.11-4 Surveillance Requirement Bases (4.11)

B 3/4.11-4:

3.12 Fire Protection Systems - Sections 3.12.A through 3.12.H - Deleted per Generic Letters 86-10 and 85-12 (Amendment 106) 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Protection System 3/4.1 - 1

-4.2

- Protective Instrumentation 3/4.2 - 1 4.2.A Primary Containment Isolation Functions 3/4.2 4. 2. E Core and_ Containment Cooling Systems --

Initiation and Control

-3/4.2 - 1 4.2.C Control Rod Block Actuation 3/4.2 - 2 4.2.0

_ Refueling Floor Radiation Monitors 3/4.2 - 2 4.2.E Post Accident Instrumentation 3/4.2 :- 3

4. 2. F -

Radioactive Liquid Effluent-Instrumentation 3/4.2 4.2.G.

Radioactive Gaseous Effluent Instrumentation

-3/4.2 - 5 4.3 Reactivity Control.

3/4.3 - 1 4.3.A Reactivity Limitations 3/4.3 21 4.3.8 Cont-ol Rods 3/4.3 4.3.C' Scram Insertion Times 3/4.3 -10 iv

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DRESDEN 11 DPR-19 Amendment No.119 (Table of Contents, Cont'd.)

fag 4.9 Auxiliary Electrical Systems 3/4.9 - 1 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 4.9.C Diesel Fuel 3/4.9 - Sa 4.9.D Diesel Generator Operability 3/4.9 - Sa 4.10 Refuelin 3/4.10- 1 4.10.A Refuelin Interlocks 3/4.10- 1 4.10.B Core Men toring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Extended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.10.G Fuel Storage Reactivity Limit 3/4.10- 8 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems -

Sections 4.12. A through 4.12.H -

Deleted per Generic Letters 86-10 and 88-12 (Amendment 106) 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Procedures and Programs 6-13 6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation 6-15-6.4 Action to be taken in the Event a safety Limit is Exceeded 6-15 6.5 Plant Operating Records 6-15 6.6 Reporting Requirements 6-17 6.7 Environmental Qualification 6-22 6.8 Offsite Dose Calculation Manual (ODCH) 6-24 6.9 Process Control Program (PCP) 6-25 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-25 vi l

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m DRESDEN II-DPR-19" Amendment No. 119-

- 1

- 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT-AUXILIARY ELECTRICAL SYSTEMS AUXILIARY-ELECTRICAL SYSTEMSj Applicability:

Applicability:

l Applies to the auxiliary Applies te the periodic testing I

electrical power system.

requirements of the' auxiliary

)

electrical system.

Objective:

Objective:

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

plant operation.

i Specification:

Specification:

i A.

Tbo reactor shall not be A.

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

1.

One 138 KV line, 1.

Every week the specific -

associated switchgear, gravity, voltage'and and the reserve

- temperature of the auxiliary power pilot cell-and-transformer capable overall battery of carrying power to voltage shall Unit 2 shall be be measured.

available.

2..The Dresden 2 diesel 2.

Every three months the generator'and the1 measurements shall be----

Unit-2/3 diesel'

- made of voltage of-each generator shall be cell to nearest 0.01-operable.-

evolt, specific gravity of each cell, and -

temperature.of-every-fifth~ cell.

3.

One 345 KV.line from 3.

At least onceJeach oper-Unit 3 capable of ating cycle,fthe unit's'.

carrying auxiliary power batteries shallLbe tested to an essential electrical

-to verify-that1the battery bus-of Unit 2 through the capacity is adequate to-4160 volt bus tie shall be

' supply 1and maintain oper-:

available.

able the actual:or simu-lated emergency-loads for-3/4.9-1 r

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DRESDEN 11 DPR-19 Amendment No. 119 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

the design duty cycle when the battery is subjected to a battery service test.

Specific gravity and voltage of each cell shall be determined af ter each service test.

4.

At least once per 60 months, in lieu of the battery service test required by 4.9.A.3, the Unit's batteries shall be subjected to a performance discharge test to verify that the battery capacity is the greater of either 80% of the manufacturer's rating or the minimum acceptable battery capacity from the latest revision of the load profile when subjected to a performance discharge test.

5.

For any battery-that shows signs of degradation or has reached 85% of the_ service life for the expected application as determined under Section 4.9.A.4, a perform-ance discharge test af battery -

capacity shall be p>

formed at least once each operating cycle.

Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

6.

To assure operability prior to use, once the alternate 125 volt battery cell-to cell connections are completed and the maintenance charger placed into service, each such battery shall adhere to the surveillances specified in 4.9.A.

i 3/4.9-la

11 DRESDEn II DPR-19 Amendment No. 119 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

~~

4.

(a) 4160 volt buses 23-1 and 24-1 are energized.

(b) 480 volt buses 28 and 29 are energized.

5.

The unit 24/48_ volt batteries, the two station 125 volt batteries and the two station 250 volt batteries and a battery charger for each required battery are operable.

B.

Except when the reactor B.

N/A is in the Cold Shutdown or Refueling modes the avail-l ability of electric power shall be as specified in 3.9. A, except as speci fied in 3.9. B.1, 3. 9.B. 2, and 3.9.B.3.

1.

From and after the date that incoming power is available from only one of the lines specified in 3.9.A reactor operation is 3/4.9-2

l DRESDEN 11 DPR-19 Amendment 119 3.9 LIMITING CONDITION _.FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

permissible only during the succeeding seven days unless the second line is sooner placed in sertice providing both the Unit 2 and Unit 2/3 emergency diesel genera-tors are demonstrated oper-able per Specification 4.9.D.I.a.

}com and after the date that incoming power is not available from any line, reactor operation is permissible providing both the Unit 2 and Unit 2/3 emergency diesel generators are demonstrated operable per Specification 4.9.D.I.a and all core and containment cooling systems are operable and the NRC is notified r

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this situation, and the plans for prompt restoration of incoming power.

2.

a.

From'and after the date that one of the-diesel generators and/or-its associated bus is inoperable, reactor operation is permissible accord-ing to Specification 3.9.B.2.c and 3.9.D L

only during the suc-l ceeding seven days unless the diesel generator and/or bua is sooner made oper-able, provided that during such seven days two offsite lines as specified in 3.9.A are available.

If the diesel became inoper-able for any cause 3/4.9-3

DRESDEN II DPR-19 i

Amendment No. 119 j

3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cor +. ' d. )

(Cont'd.)

other than pre planned preventative mainten-ance or testing, the operable diesel gen-erator shall be demon-strated operable per Specification 4.9.D.I.a immediately and daily thereafter.

3/4.9-3a

DRESDEN 11 DPR-19 Annndment No. 119 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

b.

Deleted, c.

During any period when the unit or shared diesel genera-tor is inoperable, continued reactor operation is permis-sible only during the succeeding seven days provided that all of the low pres-sure core cooling and containment cooling subsystems shall be operable.

If this requirement cannot be met, an 3/4.9-4

DRESDEN II

.DPR-19 Amendment No.119-3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

orderly shutdown shall be initiated and the reac'or shall be in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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.4, Unit l

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 sooaer made operable.

4.

a.

Each 250 volt battery may l

be inoperable for a maxi-mum of 7 days per operating cycle for maintenance and testing.

b.

If it is determined that a 250 volt battery need be l

replaced as a result of maintecance or testing, a specific battery may be inoperable for an addi-tional 7 days per operating cycle.

c.

With both units operating, each 125 volt battery may be inoperable for up to a maxi-mum of seven days per.operat-ing cycle for maintenance or testing, provided the alter-nate 125. volt battery is placed

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into service and is operable per specification ' 9.A.6 d.

With the other unit in cold shutdown or refueling, oper-ations may continue with one 3/4.9-5

DRESDG II DPR-19 Amendment No.119 -

3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVFILLANCE REQUIREMERT

[ Cont'd.)

(Cont 'd. )

of the two 125 volt battery systems inoperable provided the alternate 125 volt battery is placed into service and is operable per specifica-tion 4.9.A.6.

e.

If it is determined that a 125 volt battery need be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional seven days provided the alternate 125 volt battery is placed into service and is operable per specification 4.9.A.6.

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 1.

Once per month:

Whenever the reactor is a.

Each diesel generator l

in the Cold Shutdown or shall be started.and verified to deliver-rated voltage and frequency.

L b.

Each diesel generator shall be synchronized, fully loaded and run for at least one hour, l

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3/4.9-Sa i

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.MESDEN II DPR-19 Aniendment No.119

3. 9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

Ref ling modes, a minimum of one diesel generator (either the Dresden 2 diesel generator or the Unit 2/3 diesel generator) shall be operable whenever any work is being done which has the potential for draining the vessel, secondary containment is required, or a core or containment cooling system is required.

2.

During the monthly 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 offsite power in conjunction with an ECCS initiation signal test shall be performed on-the 4160 volt emergency bus by:

(a) Verifying de-energization of the "> esacy buses and

.sJ shedding from the emergency buses.

3/4.9-6

T DRESDEN II DPR-19 Amendment No. 119 3.9 LIM: TING 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 lubricate the plant during shutdown, and to operate the engineered safeguards following an accident. There are three sources of electrical energy available; namely, the 138 KV transmission 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.e., one active offsite source and a back-up source of off-site power and the maximum amount of onsite sources.

An alternate 125 volt DC battery has been installed for each unit with the primary purpose of supporting the performance of the rated discharge test on the permanent 125 volt battery.

The alternate battery is utilized to avoid a reduction in the single failure capability of the 125-volt system during the performance of the discharge test on the permanent battery.

B.

Auxiliary power for Unit 2 is supplied from two sources, either the Unit 2 auxiliary transformer or the Unit 2 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 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 such cases, diesel generator operability demonstrations will be limited to an unloaded start test.

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

Offsite power is quite re-liable.

In the last 25 years there has only been one instance in which all offsite power was lost at a Commonwealth Edison generatiag station.

l B 3/4.9-7

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e DRESDEN II DPR-19 Amendeent No.119 3.9 LIMITING CONDITION FOR OPERATION BASE _S (Cont'd./

For low-pressure ECCS, the verification of operability, as used in this context, means to administratively check by examining logs or other information to determine if certain components /

systems are ont-of-service for maintenance or other reasons.- It does not mean to perform the surveillance requirements needed to demonstrate the operability of the component / system.

For the remaining diesel generator, an operability demonstration to iden-tify any potential common causes for failure will be performed.

In such cases, the demonstration will be limited to an unloaded start test.

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

B 3/4.9-7a

DRESDEN II DPR-19 Amendment No. 119 3.9 LIMITING CONDITION FOR OPERATION BASES (Coct'd.)

C.

The diesel fuel supply of 10,000 gallons will supply each diesel generator with a minimum of two days of full load operation or about four days at 1/2 load. Additional diesel fuel can be obtained and delivered to the site within an 8-hour period; thus a 2-day supply provides for adequate margin.

4.9 SURVEILI.ANCE REQUIREMENT BASES A.

Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indicat.on of a cell becoming irregular or unserviceable long before it becomes a failure.

In addition, the checks described also provide adequate indication that the batteries have the specified ampere hour capability.

B.

The diesel fuel oil quality must be checked to ensure prcper operation of the diesel generators. Water content should be minimized because water in the fuel would contribute to excessive corrosion of the system causing decreased reliability. The growth of micro-organisms results in slime formations which are one of the chief causes of jellying in hydro-carbon fuels. Minimizing of such slimes is also essential to assuring high reliability.

C.

The monthly test of the diesel generator is conducted to check for equipment failures and deterioration. Testing is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions.

The diesel will be manually started, synchronized to the be.s and load picked up.

Diesel generator experience at other Commonwealth l

Edison generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.

In addition, during the test when the generator is synchronized to the bus, it is also synchronized to the offsite power source and thus not completely independent of this source. To maintain the maximum amount of independence, a thirty-day testing interval is also desirable.

B 3/4.9-8

1. gpA' 46uq'o UNITED STATES

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NUCLEAR REGULATORY OOMMISSION t

WASHINGTON, D. C. 20$5s e

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COMMONWEALTH [ DIS 0N COMPANY EQCKET NO. 50-249 DRESDEN NUCLEAR POWER STAT 10th UNIT 3 AMENDMENT TO FAC_lLITY OPERATLNG LL(LNSL Amendment No.115 License No. DPR-25 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated June 29, 1992, as supplemented August 28, 1992, 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.

inere is reasonable assurance (i) that the activities authorized by this amendment can be conducted w.inout endangering the health and safety of the public, and (ii) that such acthities 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 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 f acility Operating License No. OPR-25 is hereby amended to read as follows:

. 4 4 B.

Technical Specifications The Technical Specifications contained ir Appendix A, as revised through Amendment No.115, are hereby ii.corporated in the license. The licensee'shall operate the facility in accordance with the Technical Srecifications.

3.

This license amendment is effective as of the date of its issuance to be

. implemented within 60 days FOR THE NUCLEAR REGULATORY iMISSION h

N/1/]f f Richa arr t, Director Projec Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reacter Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 19, 1992

SITACHMENT TO LICENSE AMENDMENT NO 115 FACILITY-0PL8ATING LICENSE N0. DPR-21 DOCKET NO. 50-249 -

Revise the Apper dix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revited pages are:

identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT iv

-iv vi vi 3/4.9-1 3/4.9-1 3/4.9-la 3/4.9-2 3/4.9-2 3/4.9-3 3/4.9-3 3/4.9-3a 3/4.9-4 3/4.9-4 3/4.9-5 3/4.9-5 3/4.9-Sa 3/4.9-6 3/4.9-6 B 3/4.9-7 8 3/4.9-7 B 3/4.9-7a B 3/4.9 B 3/4.9-8 i-f.-

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OkESDEN III DPR Amendment No.115 (Tatie of Contents, Cont'd.)

Paoe 3.9.C Diesel Fuel 3/4.9-5a

3. 9,0 Diesel Generator Operability 3/4.9-Sa Limiting Conditions for Operation Bases (3.9)

B 3/4.9-7 Surveillance Requirement Bases (4.9)

B 3/4. 9-8 3.10 Refueling 3/4.10-1 3.10.A Refueling Interlocks 3/4.10-1 3.10.8 Core Monitoring 3/4.10-1 3.10.C Fuel Storage Pool Water Level 3/4.10-2 3.10. D Control Rod and Control Rod Drive Maintenance 3/4.10-3 3.10.E Extended Core Maintersnce 3/4.10-4 3.10.F Spent Fuel Cask Handling 3/4.10-5 Limiting Conditions for Operation Bases (3.10)

B 3/4.10-9 Surveillance Requirement Bases (4.10)

B 3/4.10-12 3.11 High Energy Piping Integrity (outsioe containment) 3/4.11-1 Limiting Conditions for Operation Bases (3.11)

B 3/4.11-4 Surveillance Requirement Bases (4.11)

B 3/4.11-4 3.12 Fire Protection Systems - Sections 3.12.A through 3.12.H -

Deleted per Generic Letters 86-10 and 88-12 (Amendment 101) 4.0 2URVEILLANCE RE0VIREMt'NTS 4.1 Reactor Protection System 3/4.1-1 4.2 Protective Instrumentation 3/4.2-1 4.2.A Primary Containment Isolation Functions 3/4.2-1 4.2.B Core e.nd Containment Cooling Systems --

Ini6iation and Control 3/4.2-1 4.2.C Control Rod Block Actuation 3/4.2-2 4.2.D

_ Refueling Floot Radiation Monitors 3/4.2-2 4.2.E Post Accident Instrumentation 3/4.2-3 4.2.F Radioactive Liquid Effluent Instrumentation 3/4.2-4 4.2.G Radioactive Gaseous Effluent Instrumentation 3/4.2-5 4.3 Reactivity Control 3/4.3-1 4.3.A Reactivity Limitations 3/4.3-1 4.3.B Control Rods 3/4.3-4 4.3.C Scram Insertion Times 3/4.3-10 l

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DRESDEN III DPR-25 Amendment No.115 (TableofContents, Cont'd.)

f.ag 4.9 Auxiliary Electrical Systems 3/4.9-1 4.9.A Station Batteries 3/4.9-1

4. 9. B (N/A) 4.9.C Diesel Fuel 3/4.9-Sa 4.9.D Dies 21 Generator Operability 3/4.9-5a 4.10.

Refuelin 3/4.10-1 4.10.A Refuelin Interlocks 3/4.10-1 4.10.B Core Mon toring 3/4.10-1 4.10.C ' Fuel Storage Pool Water Level 3/4.10-2 4.10.0 Control. Rod Drive and Control Rod Drive Maintenance 3/4.10-3 4.10.E Extended Core Maintenance 3/4.10-4 4.10.F Spent Fuel Cask Handling 3/4.10-5 4.10.G Fuel Storage Reactivity Limit 3/4.10-8 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems -

Sections 4.12.A through 4.12.H -

Deleted per Generic Letters 86-10 and 88-12 (Amendment 101) 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Procedures and Programs 6-13 6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation 6-15 3

6.4 Action to be taken in the Event a safety Limit is Exceeded 6-15 6.5 Plant Operating Records 6-15 6.6 Reporti'ng Requirements 6-17 6.7 Environtental Qualification 6-21 6.8 Offsite Dose Calculation Manual (ODCH) 6-23 6.9 Process Control Program (PCP) 6-24 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-24 vi 1

i 9

DRESDEt. III DPR-25 Amendment No.115 3.9 LIMITING LvNDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT AUXILIARY ELECTRICAL SYSTEMS AUXILIARY ELECTRICAL SYSTEMS Applicability:

Applicability:

Applies to the puxiliary Applies to the periodic testing electrical power system, requirements of the auxilisri electrical system.

Objective:

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 te satisfied:

1.

One 345 KV line, 1.

Every week the specific associated switchgear, gravity, voltage and and the remarve temperature of the e ir pilot cell and overall auxiliary transformer capable battery voltage shall of carrying power to be measured.

Unit 3 shall t,e available.

2.

The Dresden 3 diesel 2.

Every three months the generator and the measurements shall be Un h 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, t.

One 138 KV line from 3.

At least once each oper-Unit 2 capable of ating cycle, the unit's carrying auxiliary batteries shall be tested I

power to an essential to verify that the battery electrical bus of Unit capacity is adequate to 3 through the 4160 volt-supply and maintain oper-bus tie shall be able the actual or.simu~

l available.

lated emergency loads for 3/4.9-1

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DRESDEN III DPR-25 Amendment No, 115 3.9 LIMITING CONDITION _FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT TCont'd.)

{ Cont'd.)

the design duty cycle when the battery is subjected to a battery service test.

Spe-cliic gravity and voltage of each cell shall be determined af ter each service test.

4.

At least once per 60 months, in lieu of the battery service test required by 4.9.A.3, the Unit's batteries shall be subjected to a performance discharge : est to verify that the battery capacity

's the greater of either 80% of the manufacturer's rating or the minimum acceptable battery capacity from the latest revision of the load profile when subjected to a performance discharge test.

5.

For any battery that shows signs of degradntion or has reached 85% of the service life for the expected application as determined under Section 4.9.A.4, a perform-ance discharge test of battery capacity shall be performed at least once each operating cycle.

Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

6.

To assure operability prior to use, once the alternate 125 volt battery cell-to-cell connectione are completed and the maintenance charger placed into service, each such battery shall adhere to the surveillances specified in 4.9. A.

l.

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L DRESDEN III DPR-25 Amendment No. 115 j

3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

(Cont'd.)

4.

(a) 4160 volt buses 33-1 and 34-1 are i

energized.

(b) 480 volt buses 38 and 39 are energized.

5 The unit 24/48 volt batteries, the two station 125 volt batteries and the two station 250 volt batteries and a battery charger for each

- required battery are operable.

B.

Except when the reactor B.

N/A ia in the Cold shutdown or Refueling modes, the avail-l

= ability of electric power shall be as specified in____

3.9.A, except as-specified in 3.9.B.1, 3.9.B.2, and

3. 9,8. 3.

1.

From and i. iter the date that incoming power is available-from only one of the lines specified in 3.9.A., reactor operation is 3/4.9-2

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DPR-25 Amendment No.115 3.9 L7

• E CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREHLNT T!<

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(Cont'd.)

pertissible only during the succeeding seven days unless the second i

lina is sooner placed in service providing both the Unit 3 and Unit 2/3 emergency diesel generators are demonstrated operable per Specifica-tion 4.9.D.I.a.

From snd af ter ti e dat e that it.com-ing power is not available from any line, reactor operation is permissible providing both the Unit 3 and Unit 2/3 emergency diesel generators are demonstrated operable per Specification 4.9.D.I.a and all core and containment cooling systems are operable

.and the NRC is notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this situation, and~the plans for prompt restoration of incoming power.

2.

a.

From and after the date that one of the diesel generators and/or its associated bus is inoperable, reactor operation is permissible _ accord-ing to Specification 3.9.B.2.c and 3.9.D only during the suc-ceeding seven days unless the diesel generator and/or bus is sooner made oper-able, provided that during such seven days two offsite lines as specified in 3.9.A are available.

lf the-diesel became inoper-able for any cause 3/4.9-3

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3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

[ Cont'd.)

other than pre planned preventative mainteu-i ance or testing, the operable diesel stu-erator shall be demon-strated operable per Specification 4.9.D.1.a immediately and daily thereafter.

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(Cont'd.)

t b.

Deleted.

c.

During any period when the unit or shared diesel generator is inoperabic, continued reactor operation is permissible only during the succeeding seven days provided that all of the low pressure core cooling and containment cooling subsystems shall be operable.

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

3.

From and after the date that one of the two 125

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DRESDEN III DPR-25 Amendment No.115 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT (Cont'd.)

[ Cont'd.)

or 250V battery systems is made or found to be inoperable, except as specified in 3.9.8.4, 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 i

made operable.

4.

a.

Each 250 volt battery may be inoperable for a maximum of 7 d.1ys per operating cycle for maintenance and testing, b.

If it is determined that a 250 volt battery need be l

replaced as a result of maintenance or testing, a specific battery may be inoperable for an addi-tional 7 days per operat-ing cycle.

c.

With both units operating, each 125 volt battery may be inoperable for up to a maximum of seven days per operating cycle for mainten-ance or testing, provided the alternate 125 volt battery is placed into ser-vice and is operable per specification 4.9.A.6.

d.

With the other unit in cold shutdown or refueling, oper-ations may continue with one of the two 125 volt battery systems inoperable provided the alternate 125 volt battery is placed into service and is operable per specification 4.9.A.6.

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3. 9 LIMITING CONDITION FOR OPERATION 4.9 $URVEILLANCE REQU)REMENT

{ Cont'd.)

(Cont'd.)

e.

If it is determined that a 125 volt battery need be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional soven days provided the alternate 125 bo't battery is placed into se ' ice and.

is operable per specification 4.9.A.6.

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 1.

Once per month:

Whenever the reactor is a.

Each diesel gen-in the Cold Shutdown or erator shall be Refueling modes, a started and riuimum of one diesel verified to deliver generator (either the rated voltage andL Dresden 3 diesel generator frequency.

or the Unit 2/3 diesel generator) shall be b.

Each diesel gen-erator-shall be synchronized,

fully loaded and t

run for at least

.one hour.

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ORESDEN III DPR-25 Amendment No.115 3.9 LIMITING CONDITION FOR OPERATION 4.9 SURVEILLANCE REQUIREMENT TCont'd.)

(Cont'd.)

operable whenever any work is being done which has the potential for draining the vessel, secondary containment is required, or a core or containment cooling system is required.

2.

During the monthly 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 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 l

from the emergency buses.

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ORE $ DEN III DPR-25 Amendment No.115 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 lubri-cate 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 switchgear and engineered safety features.

The electrical power required provides for the maximum availability of por r; i.e., one active off-site source ano a back-up source of off-site power and the maximum amount of on-site sources.

An alternate 125 volt DC battery has been installed for each unit with the primary purpose of supporting the performance of the rated discharge test on the permanent 125 volt battery.

The alternate battery is utilized to avoid 6 reduction in the single failure capability of the 125-volt system during the performance of the discharge test on the permanent battery.

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 si.:ed to carry 100% of the auxiliary load.

If the reserve auxiliary transformer is lost, the unit can continue to run for 7 days 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 such cases, diesel generator operability demonstrations will be limited to an unloaded start test.

In the normal mode of operation the 345 KV systert is operating and two diesel generators are operational.

One diesel genera-tor 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 equip-eent 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.

3 3/4.9-7

DRESDEN Ill DPR-35 Amondment No.115

3. 9 LIMITING CONDITION FOR OPERATION BASES (Cont'd)

For low pressure ECCS, the verification of operability, as used in this context, means to administratively check by examining logs or other information to determine if certain components /

systems are out-of-service for maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the operability of the component / system, for the remaining diesel generator, an operability demonstration to iden-tify any potential common causes for failure will be performed.

In such cases, the demonstration will be limited to an unloaded start test.

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

4 B 3/4.9-7a

DRESDEN III DPR-25 Amendment No.115 3.9 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)

C.

The diesel fuel supply of 10,000 gallons will supply each diesel generator with a minimum of two days of full load operation or about four days at 1/2 load.

Additional diesel fuel can be obtained and delivered to the site within an 8-hour period; thus a 2-day supply provides for adequate margin.

4.9 SURVEILLANCE REQUIREMENT BASES t

A.

Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of pre-cipitous failure.

The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

In addition, the checks described also provide adequate indir,ation tha+ the batteries have the specified ampere hour capability.

B.

The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators.

Water content should be minimized because water in the fuel would contribute to exces-sive corrosion of the system causing decreased reliability.

The growth of micro-organisms results in 511rne formations which are one of the chief causes of jellying in hydro carbon fuels.

Hinimizing of such slimes is also essential to assuring high reliability.

C.

The monthly test of the diesel generator is conducted to check for equipment failures and deterioration.

Testing is conducted up to equilibrium operatin0 conditions to demonstrate proper operation at these conditions.

The diesel will be manually started, synchronized to the bus and load picked up.

Diesel generator experience at other Commonwealth Edison generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.

In addition, durin;; the test when the generator is synchronized to the bus, it is also synchronized'to the off-l site power source and thus not completely independent of this j

source.

To maintain the maximum amount of independence, a thirty-day testing interval is also desirable, l

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NUCLEAR REGULATORY COMMISSION p,

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(QMMONWEALTH EDISON COMPANY DEKET NO. 50-ZM RA.(L(lll15 NUCl[ AR POWER STATION. UNIT 1 nil @M[NT_10 FACILITY OPERATI@ LICENSE Amendment No.138 License No. DPR-29 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated June 29, 1992, as supplemented August 28, 1992, 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 it 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 Coi.wission'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 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 2.C.(2) of facility Operating License No. DPR-29 is hereby amended to read as follows:

. )

(2)

Jtchnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 138, are hereby incorporated in the license.

The licensee shall operate the f acility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance to be implemented within 60 days.

FOR THE i10 CLEAR REGULATORY PJilSS10N

/

OAQ Rictard arrett, Director Proj6ct Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Speciflations Date of Issuance: October 19, 1992 m

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&TTACHMENT TO LICENSE AMENDMENT NO.138 LA_ lllTY OPERATING llCENSE NO. DPR-29 DOCKET NO. 50-254 Revise the 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.

+

fl[.MLOE JNSERT iii i i i 3.9/4.9-1 3.9/4.9-1 3.9/4.9-2 3.9/4.9-2

, 1/4.9-3 3.9/4.9-3 3.9/4.9-3a 3.9/4.9-4 3.9/4.9-4 3.9/4.3-5 3.9/4.9-5 3 9/4.9-6 3.9/4.9-6 3.9/4.9-9 3.9/4.9-9 3.9/4.9-10 3.9/4.9-10 3.9/4.9-11 3.9/4.9-11 b

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DPR-29 TABLE OF CONTENTS (Cont'd)

Page 3.7 Limiting Conditions for Operation Bases 3.7/4.7-21 4.7 Surveillance Requirements Bases 3.7/4.7-27 3.8/4.8 RADIOACTIVE EFFLUENTS 3.8/4.8-1 A.

Gaseous Ef fluents 3.8/4.8-1 B.

Liquid Effluents 3.8/4.8-9 C.

Mechanical Vacuum Pump 3.8/4.8-13 D.

Environmental Monitoring Program 3.8/4.8-13 E.

Solid Radioactive Waste 3.8/4.8-17 F.

Miscellaneous Radioactive Materials Sources 3.8/4.8-17 H.

Control Room Emergency Filtration System 3.8/4.8-18 3.8/4.8 Limiting Conditions for Operation and Surveillance Req. Bases 3.8/4.8-22 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9/4.9-1 A.

Normal and Emergency A-C Auxiliary Power 3.9/4.9-1 B.

Station Batteries 3.9/4.9-3 C.

Electric Power Availability 3.9/4.9-3a D.

Diesel Fuel 3.9/4.9-5 E.

Diesel-Generator Operability 3.9/4.9-5 F.

Reactor Protection Bus Power Monitoring System 3.9/4.9-6 3.9 Limiting Conditions for Operation Bases

3. 9/4. 9-9 4.9 Surve111ance Requiremem 4 Bases 3.9/4.9 3.10/4.10 REFUELING 3.10/4.10-1 A.

Refueling Interlocks 3.10/4.10-1 B.

Core Monitoring 3.10/4.10-2 C.

Fuel Storage Pool Water Level 3.10/4.10-3 D.

Control Rod and Control Rod Drive Maintenance 3.10/4.10-3'

[.

Extended Care Maintenance 3.10/4.10-4 F.

Spent Fuel Cask Handling 3.10/4.10-5 3.10 Limiting Conditions for Operation Bases 3.10/4.10-7 4.10 Surveillance Requirements Bases 3.10/4.10-10 3.11/4.11 HIGh ENr.RGY PIPING INTEGRITY (Outside Containment) 3.11/4.11-1 3.11/4.11 Bases 3.11/4.11-2 i

l l

111 Amendment No. 138

i QUAD-CITIES DPR-29 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Applicability:

Applicability:

[

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

requirement of the auxiliary electrical system.

Objective:

Objective:

To assure an adequate supply of electri-To verify the operability of the auxil-cal power during plant operation.

iary electrical system SPECIFICATIONS A.

Normal and Emergency A-C Auxiliary A.

Normal and Emergency A-C Auxiliary Power Power The reactor shall not be made criti-cal unless all the following require-1.

a.

Once per month:

ments are satisfied.

(1)

Each diesel generator 1.

The Unit diesel generator and shall be started and the Unit 1/2 diesel generator verified to deliver shall be operable, rated voltage and frequency.

(2)

Each diesel generator shall be synchronized, fully loaded and run for at least one hour.

1' l

b.

During the monthly generator test, the diesel-starting l

air compressor shall be l

checked for operation and its ability to recharge air receivers.

L i

3.9/4.9-1 Amendment No.138

4 4

e QUAD CITIES DPR-29 c.

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

2.

One 345-kV line, associated 2.

The status of the 345-kV lines, switchgear, and the reserve associated switchgear, and the auxiliary power transformer reserve auxiliary power capable of carrying aower to the transformer shall be checked unit shall be availa>1e.

daily.

3.

One other 345-kV line capable l

3.

The status of the additiona!

of carrying auxiliary power to source of power via the an essential electrical bus of 4160-volt bus tie shall be the unit through the 4160-volt checked daily.

bus tie shall be available.

4.

a.

The Unit engineered safety features 4160-volt buses 4.

The Unit engineered safety (13-1 and 14-1, Unit 1; 23-1 features 4160-volt and 480-volt and 24-1, Unit 2) are buses shall be checked daily, energized.

b.

The Unit engineered safety features 400-volt buses (18 and 19, Unit 1; 28 and 29, Unit 2) are energized.

3.9/4.9-2 Amendment No.138 4

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QUAD CITIES DPR-29 B.

Station Batteries B.

Station Batteries The unit 24/48-volt batteries, two 1.

Every week the specific gravity station 125-volt batteries, the two and voltage of the pilot cell, station 250 volt batteries, and a the temperature of adjacent battery charger for each required cell, and overall battery battery shall be operable before the voltage shall be measured.

reactor can be made critical.-

2.

Every 3 months the measurement shall be made of the voltage of each cell to the nearest 0.01 l

volt, the specific gravity of each cell, and the temperature of every fif th cell.

i 3.

At least once each operating cycle, the unit's batteries shall be tested to verify that the battery capacity is adequate to-supply and maintain operable the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test.

Specific gravity and voltage of each cell shall be determined after each service test.

4.

At least once per 60 months, in lieu of the battery service test required by 4.9.B.3, the Unit's batteries shall be subjected to a performance discharge test to verify that the battery capacity is the greater of either 80% of the manufacturer's rating or the minimum acceptable battery capacity from the latest revision of the load profile when subjected to a performance discharge test.

5.

For any battery that shows signs of degradation or has reached 85%

of the service life for the expected application as determined under.

Section 4.9.B.4, a performance dis-charge test of battery capacity shall be performed at least once each operating cycle.

Degradation is indicated when the battery capacity drops more than 10% of rated capacity 3.9/4.9-3 Amendment No.138

QUAD-CITIES DPR-29 from its average on previous per-formance tests, or is below 90% of the manufacturer's rating.

6.

To assure operability prior to use, once the alternate 125 volt battery cell-to cell connections are completed and the maintenance charger placed into service, each such battery shall adhere to the surveillances specified in 4.9.B.

C.

Electric Power Availability C.

Electric Power Availability Wnenever the reactor is in the Run The availability status of electric 4

mode or for startup from a hot shut-power shall be checked daily, down condition, the availability of electric power shall be as specified in Specifications 3.9.A and 3.9.B except as stated in Specifications 3.9.C.1, 3.9.C.2, 3.9.C.3, and 3.9 E.

3.9/4.9-3a Amendment No.138 -

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QUAD CITIES DPR-29 1.

From and after the date that incoming power is available from only one of the lines specified in 3.9 A. continued reactor operation is permissible only during the succeeding 7 days, unless the second line is sooner made available, providing both the Unit and Unit 1/2 emergency diesel generators are demonstrated operable per Specification 4.9.A.I.a(1).

2.

From and after the date the incoming power is not availabic from any line, continued reactor operation is permissible aro-viding both the Unit and Jnit 1/2 emergency diesel generators are demonstrated operable per Specification 4.9.A.I a(1), all core and containment cooling systems are operable, reactor power level is reduced to 40% of rated, and the NRC is notitied within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken dur-ing this period,and the plans for prompt restoration of in-coming power.

3.

From and after the date that one of the two 125/250-volt battery systems is made or found to be inoperable for any reason, continued reactor operation is parmissible only during.the succeeding 3 days unless such battery system is sooner made operabin.

a.

With both units operating, each 125 volt battery may be inoperable for up to a maximum of seven days per operating cycle for maintenance or testing, provided the alternate 125 volt battery is placed into service and is operable per specification 4.9.8.6.

b.

With the other unit in cold shutdown or refueling, l

3.9/4.9-4 Amendment No. 138 l

(

QUAD-CITIES DPR-29 operations may continue with one of the two 125 volt battery systems inoperable provided the alternate 125 volt battery is placed into service and is operable per specification 4.9.B.6.

c.

If it is determined that a 125 volt battery need be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional seven days provided the alternate 125 volt battery is placed into service and is operable per specification 4.9.B.6.

D.

Diesel fual D.

Diesel Fuel There shall be a minimum of 10,000 Once a month the quantity of gallons of diesel fuel supply on site diesel fuel available shall be for each diesel generator, logged.

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

E.

Diesel-Generator Operability E.

Diesel-Generator Operability 1.

Whenever the reactor is in the 1.

Deleted.

Startup/ Hot Standby or Run mode and the unit or shared diesel 2.

During each refueling outage, generators and/cr their respective a simulated loss of off-site associated buses are inoperable, powerinconjunctionwithan continued reactor operation is ECCS initiati:n signal test permissible only during the suc-shall be performed on the ceeding 7 days provided that all 4160 volt emergency bus by:

of the low-pressure core cooling and all loops of the containment cooling mode of the RHR system associated with the operable diesel generator shall be operable and two offsite lines as specified in 3.9.A are available.

If the diesel generator became inoperable due to any cause other than pre-planned preventive maintenance or testing, 3.9/4.9-5 Amendment No.138

QUAD-CITIES DPR-29 a.

Verifying de-energization of the emergency buses, and load shedding from the emergency buses, b.

Verifying the diesel starts demonstrate the operability of the from ambient condition on remaining operable diesel generator the auto-start signal, by performing surveillance require-energizes the emergency ment 4.9.A.I.a(1) immediately and buses with permenently daily thereafter.

If these require-connected loads, energizes ments cannot be met, an orderly the auto-connected emergency shutdown shall be initiated and the loads through the load reactor shall be in the cold shut-sequencer, and operates for down condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

greater than 5 minutes while its generator is loaded with 2.

Deleted.

the emergency loads.

3.

When the reactor is in the Cold Shutdown or Refueling mode, a minimum of one diesel generator (either the Unit diesel genera-tor or the Unit 1/2 diesel generator) shall be operable whenever any work is being done which has the potential for draining the vessel, secondary containment is required, or a core or containment cooling system is required.

F.

REACTOR PROTECTION BUS POWER F.

REACTOR PROTECTION BUS POWER MON 110 RING SYSTEM MONITORING SYSTEM 1.

Two RPS electric power monitor-1.

The RPS Bus power monitoring ing channels for each inservice system instrumentation shall be RPS MG set or inservice alter-determined OPERABLE:

nate power source shall be OPERABLE except when the reactor is in the SHUTDOWN mode.

3.9/4.9-6 Amendment No. 138

QUAD-CITIES DPR-29 3.9 LIMITING CONDITIONS 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 lubricate the plant during shutdown, and to operate the engineered safety features following an accident.

There are two sources of electrical energy available, namely, the 345-kV transmission system and the diesel generators.

B.

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.e., one active of fsite source and one backup source of offsite power and the maximum numbers of onsite sources.

An alternate 125 volt DC battery has been installed for each unit with the primary purpose of supporting the performance of the rated discharge test on the permanent 125 volt battery.

The alternate battery is utilized to avoid a reductLn in the single failure capability of the 125-volt system during the performance of the discharge test on the permanent battery.

C.

Auxiliary power for the Unit is supplied from two sources, either the Unit auxiliary transformer or the Unit 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, since the Unit auxiliary transformer is available and both diesel generators are operational.

A 7-day period is provided if one source of offsite power is lost.

This period is based on having two diesels operable which are, adequate to handle an accident assuming a single failure.

In 1ddition, auxiliary power + rom the other unit can be obtained through the 4160-volt bus tie.

If both offsite lines are lost, power is reduced to 40% of rated so that the turbine bypass system could accept the steam flow without reactor trip should the generator be separated from the system or a turbine trip occur.

In this condition, the turbine generator is capable of supplying house load and ECCS load if necessary through the unit auxiliary transformer.

If the unit were shut down on loss of both lines, fewer sources of power would be available than for sustained' operation at 40% power.

Attention will be given to restoring normal offsite power to minimize the length of time operation is' allowed in a condition where both sources are available.

In such cases, diesel generator operability demonstrations will be limitd to an unloaded start test.

3.9/4.9-9 Amendment No.138 y

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QUAD-CITIES DPR-29 In the normal mode of operation, the 345-kV system is operable and two diesel generators are operable.

One diesel generator may be allowed out of service for a short period of time to conduct pre-planned preven-tative maintenance or testing provided that power is available from the 345-kV system through a 4160-volt bus tie to supply the emergency buses, i

and the alternate diesel generator is operable.

Offsite power is quite l

reliable, and in the last 25 years there has been only one instance in which all offsite power was lost at a Commonwealth Edison Generating i

Station.

When the unit or shared diesel generator is made or found inoperable for reasons other than pre-planned preventative maintenance or testing, the l

remaining diesel generator and its associated low-pressure core cooling and containment cooling systems, which provide sufficient engineered i

safety features equipment to cover all breaks, will be operable.

l For low pressure ECCS, the verification of operability, as used in this context, means to administrative 1y check by examining logs or other information to determine if certain components / systems are out-of-service for maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the operability of the component / system.

For +.he remaining diesel generator, an operability demonstration to identify any potential common causes for failure will be perfcPmcd.

In such cases, the demonstration will be limited to an unloaded start test.

D.

The diesel fuel supply of 10,000 gallons will supply each diesel generator with a minimum of 2 days of full load operation or about 4 days at 1/2 load.

Additional diesel fuel can be obtained and delivered to the site within an 8-hour period; tims a 2-day supply provides for adequate margin.

E.

Diesel generator operability is discussed in Paragraph 3.9.C above.

F.

Specifications are provided to ensure the operability of the RPS Bus electrical protection assemblies (EPA's).

Each RPS HG set and the alternate power source has 2 EPA channels wired in series.

A trip of either channel from either overvoltage, undervoltage, or underfrequency will trip the associated MG set or alternate power source.

3.9/4.9-10 Amendment No.138

_ -. - - - - = -.

QUAD-CITIES DPR-29 i

4.9 $URVEILt.ANCE REQUIREMENTS BASES A.

The monthly test of the diesel generator is conducted to check for equipment failures and deterioration.

Testing is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions.

The diesel will be manually started, synchronized to the bus, and load picked up.

Diesel generator experience at other Commonwcalth Edison generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.

In addition, during the test, the generator is synchronized to the offsite power sources and thus not completely independent of this source.

To maintain the maximum amount of independence, a 30-day testing interval is also desirable.

Each diesel generator has two air compressors and four air tanks.

Two air tanks are piped together to form an air receiver.

Each air compressor supplies an air receiver.

This arrangement provides redundancy in starting capability.

It is expected that the air compressors will run only infrequently.

During the monthly check of the diesel, the receivers will be drawn down below the point at which the compressor automatically starts to check operation and the ability of the compressors to recharge the receivers.

Pressure indicators are provided on each of the receivers.

Following the monthly test of the diesels, the fuel oil day tank will be approximately half full based on the 2-hour test at ful! load and 205 gph at full load.

At the end of the monthly load test of the diesel generators, the fuel oil transfer pumps will be operated to refill the day tank and to check the operation of these pumps from the emergency source.

The test of the emergency diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system, i.e., it will check diesel starting, closure of diesel breaker, and sequencing of loads on the diesel.

The diesel will be started by simulation of a loss-of-coolant accident.

In addition, an undervoltage condition will be imposed to simulate a less of the tilne required.

The only load on the diesel is that due to friction and windage and a small amount of bypass flow on each pump.

Periodic tests between refueling outages verify the ability of the diesel to run at full load and the core and containment cooling pumps to deliver full flow.

Periodic testing of the various components plus a functional test at the refueling interval are sufficient to maintain adequate reliability.

B.

Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure.

The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

3.9/4.9-11 Amendment No.138

1. gm:g'o UNITED STATES

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NUCLE AR REGULATORY COMMISSION n

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COMMQt[ WEALTH EDIS0t1 COMPAfiY POCKET NO. 50-265 QUAD CITIES I4VfLEAR POWER STATION. Utill_2 MfjiDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. DPR-30 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated June 29, 1992, as supplemented August 28, 1992, 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 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; U.

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 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-30 is hereby amended to read as follows:

m.

. B.

leshnical Specifications The Tech 2ical Specifications contained in Appendix A, as revised through Amendment No. 134, are hereby incorporated in the

license, lhe licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance to be implemented within 60 days.

FOR THE NUCLEAR REGVLATO 7p0MMISS10N g f' qAA Richar Barrett, Director t.

Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specif. ations Date of Issuance: October 19, 1992

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4 ATTACHMENT TO LICENSE AMEfi1LMENT-NO.134

-[ACILITY OPERATING LICENSE NO._DPR-30

' DOCKET NO. 50-2E5 l

Revise the Appeno:

sechnical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by the captianed amendment number and contain marginal lines indicating the area of change.

REMOVL INSERT iii iii 3.9/4.9-1 3,9/4.9-1 S.9/4.9-2 3.9/4.9-2 3.9/4.9-3 3.9/4.9-3 3.9/4.5 4 3.9/4.9-4 3.9/4.9-5 3.9/4.9-5 3.9/4.9-6 3.9/4.9-6 3.9/4.9-7 3.- 9 / 4. 9-7 3.9/4.9-8 3.9/4.9-8 3.9/4.9-9 3.9/4.9-9 3.9/4.9,

3.9/4.9-10 3.9/4.9-11 3.9/4.9-11

.3.9/4.9-12 3.9/4.9 _

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QUAD CITIES DPR-30 TABLE OF CO> TENTS (Cont'd)

Page 3.8/4.8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1 A.

Gaseous Effluents 3.8/4.8-1 B.

Liquid Effluents 3.8/4.8-6a C.

Mechanical Vacuum Pump 3.8/4.8-9 D.

Environmental Monitoring Program 3.8/4.8-10 E.

Solid Radioactive Haste 3.8/4.8-13 F.

Miscellaneous Radioactive Materials Sources 3.8/4.8-14 H.

Control Room Emergency Filtration System 3.8/4.8-14a 3.8/4.8 Limiting Conditions for Operation and Survelliance 3.8/4.8-15 Req. Bases 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9/4.9 1 A.

Normal and Emergency A-C Aux 111ary Power 3.9/4.9.1 B.

Station Batteries 3.9/4.9-3 C.

Electric Power Availability D.

Diesel Fuel 3.9/4.9-4 3.9/4.9-5 E.

Diesel-Generator Operability 3.9/4.9-6 F.

Reactor Protection Bus Power Monitoring System 3.9/4.9-7 3.9 Limiting Conditions for Operation Bases 4.9 Surveillance Requirements Bases 3.9/4.9-9 3.9/4.9-11 3.10/4.10 REFUELING 3.10/4.10-1 A.

Refueling Interlocks 3.10/4.10-1 B.

Core Monitoring 3.10/4.10-2 C.

Fuel Storage Pool Water Level 3.10/4.10-2 D.

Control Rod and Control Rod Drive Haintenance 3.10/4.10-2 E.

Extended Core Maintenance 3.10/4.10-3 F.

Spent fuel Cask Handling 3.10/4.10-3 3.10 Limiting Conditions for Operation Bases 4.10 Surveillance Requirements Bases 3.10/4.10 3.10/4.10-6 3.11/4.11 HIGH ENERGY PIPING INTEGRITY (Outside Containment) 3.11/4.11-1 3.11/4.11 Bases 3.11/4.11-2 3.12/4.12 FIRE PROTECTION SYSTEMS 3.12/4.12-1 A.

Fire Detection Instrumentation 3.12/4.12-1 B.

Fire Suppression Water System 3.12/4.12-2 C.

Sprinkler Systems 3.12/4.12-3 D.

CO2 Systems E.

Fire Hose Station 3.12/4.12-4 3.12/4.12-4 F.

Penetration Fire Barriers 3.12/4.12-4 G.

Fire Pump Diesel Engine 3.12/4.12-5 til Amendment No.134

. - ~ _.. _.

Quad Cl.ies 3

DPR.30 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS llMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Applicability:

Applicability:

Applies to the auxiliary electrical power Applies to the periodi: testing systern.

requirement of the auxiliary electrical

system, lective:

Objective:

Isure an adequate supply of electrical To verify the operability of the auxiliary er during plant operation.

electrical system.

SPECIFICATIONS A.

Normal and Emergency A C Auxiliary A. Normal and Emergency A C Auxiliary Power Power The reactor shall not be made critical utiless all the following requirements are satisfied:

1. The Unit diesel generator and the 1.

a.

Once per month:

Unit 1/2 diesel generator shall be operable.

(1) Each diesel generator shali be started and verified to deliver rated voltage and frequency.

~

(2) Each diesel generator shall be synchronized, fully loaded and run for at least one hour,

b. During the monthl/ generator test, the diesel starting air j

compressor shall be checked for -

i operation and its ability to recharge air receivers.

i.

3.9/4.9-1 Amendment No.134.-

Quad Citi:s DPR 30 c.

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

1. One 345-kV line, associated

2. The status of the 345-kV lines, switchgear, and the reserve associated switchgear, and the auxiliary power transformer reserve auxiliary power capable of carrying power to the transformer shall be checked unit shall be available.

daily.

3. One other 345 kV line capable of l

3. The status of the additional carrying auxiliary power to an source of power via the 4160-vNt essential electrical bus of the unit bus tie shall be checked daily, through the 4160-volt bus tie shall be available.

4.

a.

The Unit engineered safety

4. The Unit engineered safety features 4160-volt buses (13-1 features 4160-volt and 480 volt and 141, Unit 1; 231 and 24-buses shall be checked daily.

1, Unit 2) are energized,

b. The Unit engineered safety features 480 volt buses (18 and 19, Unit 1: 28 and 29 Unit 2) are energized.

3.9/4.9-2 Amendment No.134

4 Ouad-Cities

+

DPR 30 B. Station Batteries B. Stetion Batteries The unit 24/48 volt batteries, two

1. Every week the specific gravity and station 125-volt batteries, the two voltage of the pilot cell, the station 250 volt batteries, and a temperature of adjacent cell, and battery charger for each required overall battery voltage shall be battery shall be operable before the

measured, reactor can be made critical.

2. Every 3 months the measurement shall be made of the voltage of each cell to the nearest 0.01 volt, the specific gravity of each cell, and the temperature of every fifth cell.

3. At least once each operating cycle, the unit's batteries shall be tested to verify that the battery capacity is adequate to supply and maintain operable the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test.

Specific gravity and voltage of each cell shall ba determined after each service test.

4. At least once per 60 months, in lieu of the battery servica test required by 4.9.B.3, the Unit's batteries shall be subjected to a performance discharge test to verify that the battery capacity is the greater of either 80% of the manufacturer's rating or the minimum acceptable battery capacity from the latest revision of the load profile when subjected to a performance discharge test.

5. For any battery that shows signs of degradation or has reached 85% of the service life for the expected application as determined under Section 4.9.B.4, a performance discharge test of battery capacity shall be performed at least once each operating cycle. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's 3.9/4.9 3 Amendment No. 134

Quad-Citi:s DPR 30

6. To assure operability prior to use, once the alternate 125 voit battery cell to-cell connections are completed and the maintenance charger placed into service, each such battery shat!

adhere to the surveillances specified in 4.9.B.

C. Electric Power Availability C. Electric Power Availability Whenever the reactor is in the Run The availability status of electric mode or for startup from a hot power shall be checked daily.

shutdown condition, the availability of electric power shall be as specified in Specifications 3.9.A and 3.9.B except as stated in Specifications 3.9.C.1, 3.9.C.2, 3.9.C 3, and 3,9.E.

1.

From and after the date that incoming power is available from only one of the lines specified in 3.9.A, continued reactor operation is permissible only during the succeeding 7 days, unless the second line is sooner made available, providing both the Unit and Unit 1/2 emergency diesel generators are demonstrated operable per Specification 4.9.A.1.a(1h

2. From and after the date the incoming power is not available from any line, continued reactor operation is permissible providing both the Unit and Unit 1/2 emergency diesel generators are demonstrated operable per Specification 4.9.A.1.a(1), all core and containment cooling systems are operable, reactor power level is reduced to 40% of rated, and the NRC is notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period, and the plans for prompt restoration of incoming power.

3.9/4.9-4 Amendment No. 134

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- Quad-Citi s DPR 30

3. From and aftei the date that one of the two 125/250-volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible only during the succeeding 3 days unless such battery system is sooner made operable, a.

With bcth units operating, each 125 volt battery may be inoperable for up to a maximum of seven days per operating cycle for maintenance or testing, provided the alternate 125 volt battery is placed into service and is operable per specificatioa 4.9.B.6.

b, With the other unit in cold shutdown or refueling, operations may continue with one of the two 125 volt battery systems inoperable provided the alternate 125 volt battery is placed into serv?ce and is operable per specification 4.9.B.6.

c.

If it is determined that a 125 volt battery need be replaced as a result of maintenance or testing, a specific battery may be inoperable for an additional seven days provided the -

alternate 125 volt battery is oleced into service and is operable e.

specification 4.9.B.6.

D. Diesel Fuel D.

Diesel Fuel -

There shall be a minimum of 10,000 Once a month the quantity of diesel gallons of diesel fuel supply on site for fuel available shall be logged.

each diesel generator.-

Once a month a samole of diesel fuel

- shall be checked for quality.-

-3.9/4.9-5 Amendment No. 134

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Quas Cities I

DPR 30 E.

Diesel Generator Operability E.

Diesel Generator Operability 1.

Whenever the reactor is in the 1,

Deleted.

Startup/ Hot Standby or Run mode and the unit or shared diesel generators and/or their respective associated buses are inoperable, continued reactor operation is prmissible only during the succeeding 7 days provided that all of the low-pressure core cooling and allloops of the contair ment cooling mode of the RHR system associated with the operable diesel generator shall be operable and two offsite lines as specified in 3.9 A are available. If the diesel generator became inoperable due to any cause other than pre-planned preventive maintenance or testing, demonstrate the operability of the remaining operable diesel generator by performing surveillance requirement 4.9.A.1.a(1) immediately and daily thereafter. If these requirements cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the 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. Deleteo.

2. During each refueling outage, a simulated loss of off site power in conjunction with an ECCS initiation signal test shall be performed on the 4160 voit emergency bus by:

a.

Verifying de-energization of the emergency buses, and load shedding from the emergency buses.

3.9/4.9 6 Amendment No.134

Quad Citi2s

. DPR 30

b. Verifying the diesel starts frem 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 5 minutes l

while its generator is loaded with the emergency loads.

l

3. When the reactor is in the Cold Shutdown or Refueling mode, a minimum of one diesel generator (either the Unit diesel generator or the Unit 1/2 diesel generator) shall be operable whenever any work is being done which has the potential for draining the vessel, secondary containment is required, or a core or containment cooling system is required.

F.

REACTOR PROTECTION BUS POWER F.

REACTOR PROTECTION BUS POWER MONITORING SYSTEM MONITORING SYSTEM

1. Two RPS electric power monitoring

1. The RPS Bus power monitoring channels for each inservice RPS system instrumentation shall be MG set or inservice alternate determined OPERABLE:

power source shall be OPERABLE except when the reactor is in the a.

At least once per 6 months by SHUTDOWN mode.

performing a channel functional test, and b.

At least once per operating cycle by demonstrating the operability of overvoltage, undervoltage, and the underfrequency protective instrumentation by performance of a channel calibration including simu;ated automatic activation of the protective relays, tripping logic, and output circuit breakers, and verifying the folloviing setpoints:

3.9/4.9-7 Amendment No.134

Quad-Citi:;s DPR 30 (1) overvoltage 126.5 V = 2.5%

Min.

123.3 V Max.

129.6 V (2) undervoltage 108 V = 2.5%

Min.

10ti.3 V Max.

110.7 V (3) underfrequency 56.0 Hz,.1 %

of 60 Hz Min.

55.4 Hr.

Max.

56.6 Hi

2. a.

With one RPS electric power monitoring channel for an inservice RPS MG set or inservice alternate power

- source inoperable, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power source from service, b.

With both RPS electric power monitoring channels for an inservice RPS MG set or inservice alternate power source inoperable, restore at least one channel to OPERABLE status within 30 minutes, or remove the associated RPS MG set or alternate power source from service.

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l 3.9/4.98 Amendment No.134

- - ~ -

Quad-Cities DPR 30 3.9 LIMITING CONDITIONS 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 lubricate the plant during shutdown, and to operate the engineered safety features following an accident. There are two sources of electrical energy available, namely, the 345 kV transmission system and the diesel generators, B.

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 availab;lity of power, i.e., one active offsite source and one backup source of offsite power and the maximum numbers of onsite sources.

Ar alternate 125 voit DC battery has been installed for each unit with the primary purpose of supporting the performance of the rated discharge test on the permanent 125 volt battery. The alternate battery is utilized to avoid a reduction in the single failure capability of the 125 volt system during the performance of the discharge test on the permanent

battery, C.

Auxiliary power for the Unit is supplied from two sources, either the Unit auxiliary transformer or the Unit 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, since the Unit auxiliary transformer is available and both diesel generators are operational. A 7-day period is provided if one source of offsite power is lost.

This period is based on having two diesels opercole which are adequate to handle an accident assuming a single failure. In addition, auxiliary power from the other unit can be obtained through the 4160 volt bus tie if both offsite lines are lost, power is reduced to 40% of rated so that the turbine bypass system could accept the steam flow without reactor trip should the generator be separated from the system or a turbine trip occur. In this condition, the turbine generator is capabie of supplying house load and ECCS load if necessary through the unit auxiliary transformer. If the unit were shut down on loss of both lines, fewer sources of power wculd be available then for sustained operation at 40%

power. Attention will be given to restoring normal offsite power to minimize the length of time operation is allowed in a condition where both sources are available. In such cases, diesel generator operability demonstrations will be limited to an unloaded start test.

In the normal mode of operation, the 345 kV system is operable and two diesel generators arc operable. One oiesel generator may be allowed out of service for a short period of time to conduct pre-planned preventative maintenance or testing provided that power is available l

from the 345-kV system through a 4160-volt bus tie to supply the emergency buse., and the alternate diesel generator is operable. Offsite power is quite reliable, and in the last 25 l

years there has been only one instance in which all offsite power was lost at a Commonwealth Edison Generating Station.

When the unit or sharoc diesel generator is made or found inoperable for reasons other than pre-planned preventative maintenance or testing, the remaining diesel generator arid its l

associated Icw pressure core cooling and containment cooling systems, which provide sufficient engineered safety features equipment to cover all breaks, will be operable.

l For low pressure ECCS, the verification of operability, as used in this context, means to administratively check by examining logs or cther information to determine if certain components / systems are out of service for maintenance or other reasons. It does not mean 3.9/4.9 9 Amendment No. 134

Quad-Cities DPR-30 to perform the surveillance requirements needed to demonstrat6 the operability of the component / system. For the remaining diesel generator, an operability demonstration to identify any potential cor-mon causes for failure will be performed.

In such cases, the demonstration will be limited to an unloaded start test.

D.

The diesel fuel supply of 10,000 gallons will supply each diesel generator with a minimum of 2 days of fullload operation or about 4 days at 1/2 load. Additional diesel fuel can be obtained and delivered to the site within an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period; thus a 2-day supply provides for adequate margin.

E.

Diesel generator operability is discussed in Paragraph 3.9.C above.

F.

Specifications are provided to ensure the operability of the RPS Bus electrical protection assemblies (EPA's). Each RPS MG set and the alternate power source has 2 EPA channels wired in series. A trip of either channel from either overvoltage, uridervoltage, or underfrequency will trip the associated MG set or alternate power source.

3.9/4.9 10 Amendment No.134

4 4

Quad Citiss-DPR-30 1

4.9 SURVEILLANCE REQUIREMENTS BASES 1

A.

The monthly test of the diesel generator is conducted to check for equipment f ailures and deterioration. Testing is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions. The diesel will be manually started, synchronized to the bus, and load picked up. Diesel generator experience at other Commonwealth Edison generating stations indicates that the testing frequency is adequate and provides a high reliability of operatior should the system be required; in addition, during the test, the generator is synchronized to the offsite power sources and thus not completely independent of this source. To maintain the maximum amount of inoependence, a 30-day testing intervalis also desirable.

Each diesel generator has two air compressors and four air tanks. Two air tanks are piped together to form an air receiver. Each air compressor supplies an air receiver.

This arrangement provides redundancy in starting capability. It is expected that the air compressors will run only infrequently.

During the monthly check of the diesel, the receivers will be drawn down below the -

point at which the compsessor automatically starts to check operation and the ability of the compressors to recharge the receivers. Pressure indicators are provided on each of the receivers.

Following the monthly test of the diesels, the fuel oil day tank will be approximately half full based on the 2-hour test at fullload and 205 gph at fullload. At the end of the monthly load test of the diesel generators, the fuel oil transfer pumps will be operated to refill the day tank and to check ths operation of these pumps from the emergency-source.

The test of the emergency diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system, i.e., it will check diesel starting, closure of diesel breaker, and sequencing of loads on the diesel The diesel will be started by simulation of a loss-of coolant accident.. In addition, an undervoltage condition will be imposed to simulate a loss of the time required. The only load on the dieselis that due to friction and windage and a small amount of bypass flow on each pump.

Feriodic tests between refueling outages verify the ability of the diesel to run at fullload -

and the core and containment cooling pumps to deliver full flow. Periodic testing of the various components plus a functional test at the refueling interv6! are sufficient to maintain adequate reliability.

B.

Although sti. tion batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. -The type of surveillance described in this specification is that which has been demonstrated over the years to provide an

-indication of e cell becoming irregular or unserviceable long before it becomes a failure, in addition, the checks described also provide adequate indication that the batteries have the specified ampere-hour capability.

3.9/4.9 11 Amendment No,134

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09ad Citias DPR 30 C.

Because the availability of electricity to the system is a normal cperating function, a check of the status of these systems provides adequate surveillance.

D.

The diesel fuel oil quality must ' checked to ensure proper operation of the diesel generators. Water content should be minimized, because water in the fuel would contribute to excessive corrosion of the system, causing decreased reliability. The growth of micro-organisms results in slime formations, which are one of the chief causes of jellying in hydrocarbon fuels. Minimizing of such si:mes is also essential to assuring high reliability.

E.

Diesel generator operability surveillsnee is discussed in Paragraph 4.9.A above.

F.

Surveillance requirements are provided for the RPS EPA's to demonstrate their operability.

The setpoints for overvoltage, u.)dervoltage, and underirequency have been chosen based on analysis (ref. February 4,1983 letter to H. Denton from T. Rausch).

3.9/4.9-12 Amendment No.134