Text

Amends 100 & 96 to Licenses DPR-19 & DPR-25,respectively, Eliminating APRM Scram Requirement & Removing Bypass Permissive on Main Steam Line High Radiation Scram
	ML20153D312
Person / Time
Site:	Dresden
Issue date:	08/24/1988
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20153D315	List: ML20153D312; ML20153D318;
References
	DPR-19-A-100, DPR-25-A-096 NUDOCS 8809020166
	Download: ML20153D312 (14)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20655 y.....)

COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR p0WER STATION, UNIT NO. 2 fMENDMENTTOPROVISIONALOPERATINGLICENSE Amendment No. 100 License No. DPR-19 1.

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

A.

The application for amendment by the Comonwealth Edison Company (the licensee)datedApril 25, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attechment 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. 100, are b reby incorporated in the license.

The Itcensee shall operate the facility in accordance with the Technical Specifications.

8809020166 800024 gDR ADOCK0500g37

. t 3.

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

FOR THE NUCLEAR REGULATORY COMMISSI N Daniel R. Muller, Director Project Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: August 24, 1988

n ATTACHMENT TO LICENSE AMENDMENT NO.100 1

PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 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.

REMOVE INSERT 3/4.1-5 3/4.1-5 3/4.1-6 3/4.1-6 3/4.1-7 3/4.1-7 3/4.1-8 3/4.1-8 4

DRESDEN II DPR-19 Amendment No. 82, 84, 99, 1 0 0 TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAN) INSTRtMENTATION REQUIREENTS Minimam Number Modes in Which Function Operable Inst.

Must be Operable Channels per Trip Startup/ Hot (1) System Trip Function Trip Level Setting Refuel (6)

Standby Run Action

l 1

Mode Switch le Shutdown X

X X

A 1

Manual Scram X

X X

A IRM 3

High Flux (LT/E) 120/125 X

X N/A A

l of Full Scale 3

Inoperative X

X N/A A

I APRM 2

High Flux Specification 2.1.A.1 X

X(8)

X A or B 2

Inoperative **

X X(8)

X A or B

~

2 High Flux (15% Scram)

Specification 2.1.A.2 X

X N/A A

2 High Reactor Pressure (LT/E) 1060 psig X(10)

X X

A I

2.

High Drywell Pressure (LT/E) 2 psig X(7),X(9)

X(7),(9) X(9)

A I

2 Reactor Low Water Level (GT/E) 1 incha**

X X

X A

2 High Water Level in (LT/E) 40 inches above X(2)

X X

A or D (Per Bank)

Scram Discharge Volume bottom of the Instrument (Thermal and dP Switch)

Volume 2

Turbine Condenser Low (GT/E) 23 in. Hg Vacuum X(3)

X(3)

X A or C Vacuum 2

Male Stem Line High (LT/E) 3 X Normal X

X X(11)

A or C l

Radiation Full Power Background 4(5)

Main Steam Line (LT/E) 10% Valve Closure X(3)

X(3)

X A or C l

Isolation Valve Closure 2

Generator Load X(4)

X(4)

A or C Rejection 2

Turbine Stop Valve (LT/E) 10% Valve closure X(4)

X(4)

A or C Closure 2

Turbine Control -

(GT/E) 900 psig X(4)

X(4)

A or C l

Loss of Control Oil Pressure Notes: (LT/E) = Less than or equal to.

(GT/E) = Greater than or equal to.

(Notes continue on next two pages) 3/4.1-5

j s

~\\

DRESDEN II OPR-19 Amendment No. 13, 71, 75, 82, 99, 100 NOTES:

(For Table 3.1.1)

1. There shall be two operable or tripped trip systems for each function.

2. Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions of the reactor mode switch.

3. Permissible to bypass when reactor pressure less than 600 psig.

4. Permissible to bypass when first stage turbine pressure less than that which corresponds to 45% rated steam flow.

-4

5. The design permits closure of any one valve without a scram being l

initiated.

6. When the reactor is subcritical and the reactor water temperature is l

1ess than 212*F, only the following trip functions need to be operable:

a.

Mode Switch in Shutdown b.

Manual Scram c.

High Flux IRH d.

Scram Discharge Volume High Lovel

7. Not required to be operable when primary containment integrity is not I

remired.

8. Not required while performing low power physics tests at atmospherir i

pressure during or after refueling at power levels not to exceed 5 MW(t).

9. Hay be bypassed when necessary during purging for containment inerting I

or deinerr.ing.

10. Not required to be operable when the reactor pressure vessel head is I

not bolted to the vessel, q

11. Due to addition of hydrogen to the primary coolant, the Main Steam Line Radiation monitor setting will be less than or equal to 3 times full power background without hydrogen addition for all conditions except for greater than 20% power with hydrogen beinn injected during which the Main Steam Line Radiation trip setting 4iii he less than or equal to 3 times full power i;&.kground with hydrogen audition.

(Cont'd. next page) 3/4.1-6

DRESDEN II DPR-19 Amendment No. 13, 71, 75, 82, 99 100 NOTES:

(For Table 3.1.1 Cont'd.)

1 Required changes in Maia Steam Line Radiation Monitor trip setting vill be made within 24 hrs, except during controlled power descensions at which time the setpoint change will be made prior to going below 20% power.

If due to a recirculation pump trip or other unanticipated power reduction event the reactor is below 20% power without the setpoint change, control rod motion will be suspended until the necessary trip setpoint adjustment is made If the first column cannot be met for one of the trip systems, that trip system shall be tripped.

If the first column cannot be met for both trip systems, the appropriate actions listed below shall be taken:

a.

Initiate insertion of operable rods and complete insertion of all operable rods within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

Reduce power level to IRM range and place mode switch in the Startup/ Hot Standby position within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

Reduce turbine load and close main steam line isolation valves within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , d.

In the refuel mode, when any control rod is withdrawn, suspend all operations involving core alterations and insert all insertable control rods within one hour.

- An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there are less than 50% of the normal complement I

of LPRM's to an APRM.

- - 1 inch on the water level instrumentation is greater than or equal to 504" above vessel zero (see Bases 3.2).

- - - Trips upon actuation of the fast closure solenoid which trips the turbine control valves.

i 3/4.1-7

DRESDEN II DPR-19 Amendment No. 82, 84, 99, 100 TABLE 4.1.1 SCRAM INSTRUMENTATION FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTR. AND CONTROL CIRCUITS Instrument Channel Group (3)

Functional Test Minimum Frequency (4) j Mode Switch in Shutdown A

Place Mode Switch in Shutdown Each Refueling Outage Manual Scram A

Trip Channel and Alarm Every 3 Months IRM

High Flux C

Trip Channel and Alarm (5)

Before Each Startup (6) j

Inoperative C

Trip Channel and Alarm Before Each Startup (6)

APRM High Flux B

Trip Output Relays (5)

Once Each Week Inoperative B

Trip Output Relays Once Each Week q

j High Flux (15% scram)

B Trip Output Relays Before Each Startup High Reactor Pressure A

Trip Channel and Alarm (1)

High Drywell Pressure A

Trip Channel and Alarm (1)

Reactor Low Water Level (2)

B (8)

(1)

High Water Level in Scram Discharge A

Trip Channel and Alarm (7)

Every 3 Months Volumes (Thermal and dp Switch)

Turbine Condenser low Vacuum A

Trip Channel and Alarm (1)

Main Steam Line High Radiation (2)

B Trip Channel and Alarm (5)

Once Each Week Main Steam Line A

Trip Channel and Alarm (1)

Isolatior. Valve Closure Generator Load Rejection A

Trip Channel and Alarm (1)

Turbine Stop Valve Closure A

Trip Channel and Alarm (1)

Turbine Control - Loss of Control A

Trip Channel and Alarm (1) l Oil Pressure Notes:

{See next page.)

3/4.1-8

f

'o UNITED STATES

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NUCLEAR REGULATORY COMMISSION o

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E WASHINGTON, D. C. 20655 4, *....,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-25 1.

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

A.

The application for amendment by the Comonwealth Edison Company (the licensee) dated April 25, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

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

2.

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

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

1

, 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 24, 1988 h

e

ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE OPR-25 DOCKET NO. 50-249 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.

REMOVE INSERT 3/4.1-5 3/4.1-5 3/4.1-6 3/4.1-6 3/4.1-7 3/4.1-7 3/4.1-8 3/4.1-8

CRESDEN III DPR-25 Amendment No. 59, ss, 75, 95, 96 TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM' 'MTRUMENTATION REQUIREENTS Minimum Number Modes in idhich Function Operable Inst.

Must be Operable Channels per Trip Startup/ Hot (1) Systee Trip Function Trip Level Setting Refuel (6) 5taney g

Action

I 1

Mode Switch in Shutdown 1

X X

A 1

Manual Scram X

X X

A IRM 3

High Flux (LT/E) 120/125 X

X N/A A

l cf Full Scale 3

Inoperativ X

X N/A A

[

APRM 2

High Flux Specification 2.1.A.1 X

X(8)

X A or 8 2

Inoperative **

X X(8)

X A or 5 2

High Flux (15% Scram)

Specification 2.1.A.2 X

X N/A A

2 High Reactor Pressure (LT/E) 1060 psig X(10)

X X

A l

2 High Drywell Pressure (LT/E) 2 psig X(7),X(9)

X(7),(9) X(9)

A l

2 Reactor Low 1 dater Level (GT/E) 1 incha**

X X

X A

2 High ideter Level in (LT/E) 37.25 inches above X(2)

X X

A or D (Per Bank)

Scram Discharge Volum bottom of the Instr==ent (Float and dP Switch)

Volume 2

Turbine Condenser Low (GT/E) 23 in. Hg vacuum X(3)

X(3)

X A or C Vacuum 2

Main Steam Line High (LT/E) 3 X Normal 1

X X

A or C l

Radiation Full Power Background 4(5)

Main Steam Line (LT/E) 101 Valve closure X(3)

X(3)

X A or C l

Isolation Valve Closure 2

Generator Load X(4)

X(4)

A or C Rejection 2

Turbine Stop Valve (LT/E) 101 Valve Closure X(4)

X(4)

A or C Closure 2

Terbine Control -

(GT/E) 900 psig X(4)

X(4)

A or C l

Loss of Control Oil Pressure 4* P Notes: (LT/E) = Less than or equal to.

(GT/E) = Greater then or equal to.

(Notes continue on next two pages) 3/4.1-5 0

DRESDEN III DPR-25 Amendment No. 59, 65, 75, 95, 96 NOTES:

(For Table 3.1.1) 1.

There shall be two operable or tripped trip systems for each function.

2.

Permissible to bypass, with control rod block, for reactor protection f:' stem reset in refuel and shutdown positions of the reactor mode switch.

3.

Permissible to bypass when reactor pressure less than 600 psig.

4.

Permissible to bypass when first stage turbine pressure less than that which corresponds to 45% rated steam flow.

d 5.

The design permits closure of any one valve without a scram being l

initiated.

6.

When the reactor is suberitical and the reactor water temperature is l

1ess than 212*F, only the following trip functions need to be operable:

a.

Mode Switch in Shutdown b.

Manual Scram c.

High Flux IRH d.

Scram Discharge Volume High Level 7.

Not required to be operable when primary containment integrity is not i

required.

8.

Not required while performing low power physics tests at atmospheric l

pressure during or after refueling at power levels not to exceed 5 MW(t).

9.

May be bypassed when necessary during purging for containment inerting I

or deinerting.

10. Not required to be operable when the reactor pressure vessel head is l

not bolted to the vessel.

d (Cont'd. next page) 3/4.1-6 I

i~

l DRESDEN III DPR-25 Amendment No. 59, 65, 75, 95, 96 NOTES:

(For Table 3.1.1 Cont'd.)

d If the first column cannot be met for one of the trip systems, that trip system shall be tripped.

If the first column cannot be met for both trip systems, the appropriate actions listed below shall be taken:

a.

Initiate insertion of operable rods and complete insertion of all operable rods within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

Reduce power level to IRM range and place mode switch in the Startup/ Hot Standby position within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

Reduce turbine load and close main steam line isolation valves within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

d.

In the refuel mode, when any control rod is withdrawn, suspend all operations involving core alterations and insert all insertable control rods within one hour.

An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there are less than 50% of the normal complement I

of LPRM's to an APRM.

1 inch on the water level instrumentation is greater than or equal to 504" above vessel zero (see Bases 3.2).

Trips upon actuation of the fast closure solenoid which trips the turbine control valves.

i 3/4.1-7

DRESDEN III DPR-25 Amendment No. 75, 89, 95, 96

^

TABLE 4.1.1 SCRAM INSTRUMENTATION FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTR. AND CONTROL CIRCUITS Instrument Channel Group (3)

Functional Test Minimum Frequency (4)

Mode Switch in Shutdown A

Place Mode Switch in Shutdown Each Refueling Outage Manual Scram A

Trip Channel and Alarm Every 3 Months IRM

High Flux C

Trip Channel and Alarm (5)

Before Each Startup (6)

Inoperative C

Trip Channel and Alarm oefore Each Startup (6)

APRM High Flux B

Trip Output Relays (5)

Once Each Week Inoperative B

Trip Output Relays Once Each Week a

High Flux (15% scram)

B Trip Output Relays Before Each Startup i

High Reactor Pressure A

Trip Channcl and Alarm (1)

High Drywell Pressure A

Trip Channel and Alarm (1)

Reactor Low Water Level (2)

B (8)

(1)

High Water Level in Scram Discharge A

Trip Channel and Alarm (7)

Every 3 Months Volumes (Float and dp Switch)

Turbine Condenser low Vacuum A

Trip Channel and Alarm (1)

Main Steam Line High Radiation (2)

B Trip Channel and Alarm (5)

Once Each Week Main Steam Line A

Trip Channel and Alarm (1)

Isolation Valve Closure Generator Load Rejection A

Trip Channel and Alarm (1)

Turtiine Stop Valve Closure A

Trip Channel and Alarm (1)

Turbine Control - Loss of Control A

Trip Channel and Alarm (1)

Oil Pressure Notes: (See next page.)

3/4.1-8

ML20153D312

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