Text

Annual Operating Rept,1981
	ML20053C909
Person / Time
Site:	Dresden
Issue date:	03/10/1982
From:	; COMMONWEALTH EDISON CO.
To:	;
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ANNUAL OPERATING REPORT OF DRESDEN NUCLEAR POWER ' STATION, COMMONWEALTH EDISON COMPANY FOR 1981 i

UNIT NO.

DOCKET NO.

LICENSE NO.

1 050-010 DPR-2 2

050-237 DPR-19 9

3 050-249 DPR-25 i

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i 8206030151 820310 PDR ADOCK 05000010 i

R PDR

b TABLE OF CONTENTS

?.*L' Section 1: Dresden Unit 1

- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendments to Facility License or Technical Specifications 1

- Other Changes, Tests and Experiments 2

Section 2: Dresden Unit 2

- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendments to Facility License or Technical Specifications 3

- Other Changes, Tests and Experiments 7

Section 3: Dresden Unit 3

- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendments to Facility License or Technical Specifications 15

- Other Changes, Tests and Experiments 18

- DRESDEN 2 AND 3 SAFETY / RELIEF VALVE STATEMENT 21

- GLOSSARY 22 l

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AMENDMENTS TO FACILITY LICENSE DPR-2 (UNIT 1) OR ASSOCIATED

,r TECHNICAL 3PECIFICATIONS AMENDMENT #33 On February 11, 1981, the Nuclear Regulatory Commission issued Amendment #33 to the Dresden Facility License No. DPR-2.

The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment states that the licensee shall fully implement and maintain in effect all provisions of the Commission-approved safeguards contingency plan. These shall include amendments and changes made pursuant to the authority of 10 CFR 50.54(p) and 10 CFR 2.790(d) an'd 10 CFR 73.40(b) and 10 CFR 73.55(b)(4).

AMENDMENT #34 On June 25, 1981, the Nuclear Regulatory Commission issued Amendment

34 to the Dresden Facility License No. DPR-2.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment clarifies the term " operable" and its many uses as stated in the Technical Specifications, specifically on pages 1, 4, 19a, 19b, 96, 122d, 122g, and 122h.

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UNIT 1 OTHER CHANGES, TESTS AND EXPERIMENTS MODIFICATION M12-1-75-31 Installation of a HVAC Isolation and Steam Leak Detection System The change involved installing HVAC isolation dampers and a steam leak detection system to initiate damper closure. This change was implemented to prevent steam from entering essential electrical equipment areas in the unlikely event of a high energy line rupture.

The safety evaluation concluded that the margin of safety actually increases because any steam leaks can now be detected in the steam tunnel area and then will be isolated from the-HVAC system if a major pipe failure was to occur.

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AMENDMENTS TO FACILITY LICENSE DPR-19 (UNIT 2) OR ASSOCIATED TECHNICAL SPECIFICATIONS AMENDMENT #52 On December 29, 1980, the Nuclear Regulatory Commission issued Amendment #52 to the Dresden Facility License No. DPR-19.

The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment allows one 2/3 chimney sampling system to be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for installation of the high range noble gas monitor, with cartain very definitive conditions as specified very clearly on page 133a.

AMENDMENT #53 On December 30, 1980, the Nuclear Regulatory Commission issued Amendment #53 to the Dresden Facility License No. DPR-19.

The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment specifies installation of a recirculation pump trip or place and maintain Unit 2 in cold shutdown or the refuel mode by January 4,1981.

AMENDMENT #54 On December 31, 1980, the Nuclear Regulatory Commission issued Amendment #54 to the Dresden Facility License No. DPR-19.

The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment specifies that the component in-service inspection program shall be performed per Section :KI of the ASME Boiler and Pressure Code as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been given by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

AMENDMENT #55 On February 6, 1981, the Nuclear Regulatory Commission issued Amendment

55 to the Dresden Facility License No. DPR-19.

The following is e 1

list of the changes in the license for the incorporation of the Amendment.

Paragraph 3.J (page 4) -.-. -

AMENDMENT #55 (Continued)

The Amendment states that a program to reduce leakage from those systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The program shall include maintenance, inspec-tion, and testing requirements at intervals not to exceed refuel-ing outages.

Paragraph 3.K The Amendment states that a program which ensures capability to accurately determing airborne iodine concentrations in vital areas under accident conditions must be implemented.

It shall include training of personnel, procedures for monitoring, and provisions for maintenance of sampling and analysis equipment.

Table 4.2.1 The Amendment provides time limits on testing, calibration, and checks on instrumentation for the Safety / Relief Valve Monitoring System.

AMENDMENT #56 On February 11, 1981, the Nuclear Regulatory Commission issued Amendment #56 to the Dresden Facility License No. DPR-19. The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment states that the licensee shall fully implement and maintain in 'effect all provisions of the Commission-approved safeguards contingency plan.

These shall include amendments and changes made pursuant to the authority of 10 CFR 50.54(p) and 10 CFR 2.790(d) and 10 CFR 73.40(b) and 10 CFR 73.55(b)(4).

AMENDMENT #57 on March 27, 1981, the Nuclear Regulatory Commission issued Amendment

57 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment provides time limits for monitoring, sampling and recording results of the reactor coolant system leakage as specified in 4.6.D (reactor sump flows).

AMENDMENT #58 On March 31, 1981, the Nuclear Regulatory Commission issued Amendment

58 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment. _.

AMENDMENT #58 (Continued)

The Amendment provided those Technical Specification changes that were required prior to reload of fuel in Unit 2 reactor during the refueling outage of Spring, 1981, per Code of Federal Regulations 50.59.

AMENDMENT #59 On April 30, 1981, the Nuclear Regulatory Commission issued Amendment

59 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment establishes the new values for the flow control line, the core thermal power calcalations, and the scram and rod block settings. Also, it provides implementation and surveillance requirements for these values.

AMENDMENT #60 On May 6, 1981, the Nuclear Regulatory Commission issued Amendment

60 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment allows removal of, additions to, and reclassification of certain shock suppressors (snubbers) as outlined in I.E.

Bulletin 79-14.

AMENDMENT #61 On June 1, 1981, the Nuclear Regulatory Commission issued Amendment

61 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment establishes conditions for continued operation of Unit 2, utilizing only one recirculation pump for a period not to exceed four weeks. All of these very specific conditions are listed on page 5 of the revised Technical Specifications.

AMENDMENT #62 On June 25, 1981, the Nuclear Regulatory Commission issued Amendment

62 to the Dresden Facility License No. DPR-19. The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment clarifies the term " operable" and its many uses as stated in the Technical Specifications, specifically on pages i, 2, 21a, 21b, 135, 156d, 156g, 156h, and 156i..

AMENDMENT #63 On June 30, 1981, the Nuclear Regulatory Commission issued Amendment

63 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment establishes conditions for continued operation of Unit 2, utilizing only one recirculation pump. All of these very specific conditions are listed on page 5 of the revised Technical Specifications.

AMENDMENT #64 On August 21, 1981, the Nuclear Regulatory Commission issued Amendment

64 to the Dresden Facility License No. DPR-19.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment provides for the position of Shif t Technical Advisor (SCRE) and that individual's qualifications and duties.

Also, it provides for minimum shift crew composition and its implementation.

AMENDMENT #65 On September 15, 1981, the Nuclear Regulatory Co mission issued Amendment #65 to the Dresden Facility License No. DPR-19.

The follow-ing is a list of the changes in the license for the incorporation of the Amendment,

,f The Amendment allowed, during the period of September 4, 1981 through September 10, 1981 when the HPCI system was declared inoperable, that Unit 2 was not required to demonstrate opera-bility of the automatic pressure relief system daily.

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UNIT 2 OTHER CHANGES, TESTS AND EXPERIMENTS MODIFICATION M12-2-76-78 Replace the Existing Motors on Valves 2-1501-22A, 2-1501-22B, 2-2301-3, 2-2301-5, 2-2301-8, and 2-2301-9 The change involved replacing the Limitorque valve motors on the above-specified valves. This was accomplished to reduce the torque on the valve stems to a lesser level, while at the same time providing normal operation.

The safety evaluation concluded the the margin of safety is not reduced because all the motors are adequately sized and will be tested regularly to ensure proper operation.

MODIFICATION M12-2-77-2 Replace All Drywell Hydraulic Snubbers with Mechanical Snubbers Over the Next Three Refueling Outages The change involved replacing all the hydraulic snubbers in the Unit 2 drywell with mechanical snubbers over a time period of three (3) refueling outages. This was accomplished in the stated time period so that the radiation dose incurred by station personnel would be kept to a minimum.

The safety evaluation concluded that the hydraulic snubbers are being replaced with mechanical snubbers of equal ratings and the minimum performance requirements as specified by ASME Section III, Subsection NF, are not being modified.

MODIFICATION M12-2-78-18 Modify LPCI Loop Selection Logic Closure of the Recirculation Suction System Valve The change involved modifying the LPCI loop selection circuitry to disable closure of the recirculation pump selection valve so that, when completed, there would be two (2) open contacts in the closing circuit which would reduce the likelihood of a short causing spurious operation.

The safety evaluation concluded that the margin of safety is unaffected because maintaining both recirculating suction valves in open position decreases chances of vessel pressure buildup in the unlikely event of a water line break and also the surveillance requirements remain as before; thus, no new accident or malfunction is created, and the system remains unchanged as previously evaluated.

1 jdODIFICATIONM12-2-78-33 Provide Local Control Capability for Unit 2 Control Rod Drive Pumps The change involved modifications of the local controls to the main feed circuit breakers that are necessary for energizing the buses which feed the CRD pumps. The following 4160 volt circuit breakers are provided with local control:

2301, 2302, 2329, 2333, 2411, 2414, 2430, 2422, and 2432.

The safety evaluation concluded that, in the unlikely event of a fire in the Control Room or Auxiliary Electric Room, local control of these breakers will insure that a high pressure system (CRD) will be available to provide reactor make-up water and that the buses that feed the CRD pumps een be energized. Local control of the breakers will not impair the capability of the CRD's because their automatic tripping and closing logic has not been altered; also, manual initiation frem the Control Room has not been hindered.

MODIFICATION M12-2-79-05 Modify the HPCI Control Circuit to Bypass the Pump Low Suction Pressure Trip During Automatic Start The change involved a few wiring changes in the Auxiliary Electric Room panel 902-39, and the electrical drawings were revised to show this modification.

The safety evaluation concluded that eliminating this trip of the HPCI pump because of a low booster pump suction pressure will not impede its ability to perform its intended function.

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MODIFICATION M12-2-79-31 Install DC Operated Valves in Parallel With the Emergency AC Operated Valves for Fire Water Make-up to the Isolation Condenser The change involved converting the motor operators on valves 2-1301-10 and 2-4102 to direct current and powered from MCC #2.

The safety evaluation concluded that the margin of safety is actually increased because the valves may now be remotely operated rather than manually opened.

MODIFICATION M12-2-79-32 Permanently Isolate the Corrosion Test Loop from the Reactor and Feedwater Cleanups The change involved removing certain sections of the corrosion loop piping and installing welded caps on the pipe stubs, thus test eliminating any need for testing of the loop.

MODIFICATION M12-2-79-32 (Continued)

The safety evalvetion concluded that the system serves no real purpose; therefore, its retirement will not adversely affect any safety margin.

MODIFICATION M12-2-79-39 Install Individual Control Switches for the Holdup Line Drain Valves on Panel 902-54 The change involved installing wiring and control switches in panel 902-54 so that the holdup drain valves are controlled from their own independent switches, rather than by switch 5440 which operates the offgas and drain valves together.

The safety evaluation concluded that the margin of safety re-mains the same since the individual valve operation remains the same i

electrically.

MODIFICATION M12-2-79-44 Replace the Barton #296 Level Transmitter for the Isolation Condenser with a Sealed Rosemont #1151 Differential Pressure Transmitter The change involved replacing the existing Barton transmitter with the new and more dependable Rosemont Model #1151 because (1) the Barton model is no longer manufactured and spare parts are hard to obtain, and (2) the Rosemont model is more reliable and accurate than the Barton model.

.I The safety evaluation conluded that the margin of safety is not reduced because system initiation results from different instrumentation.

MODIFICATION M12-2-79-47 Install a HPCI Automatic Initiation Pushbutton in Control Room to Allow Rapid Manual System Initiation The change involved installing a General Electric type CR2940 switch in parallel with other existing low reactor water level and primary containment high pressure sensors.

It also has an arming collar to pre-vent accidental initiation.

The safety evaluation concluded that the margin of safety will not be affected because the modification will ensure a manual fast start capability of the HPCI system.

MODIFICATION M12-2-80-1 Provide Additional Pipe Supports for Seismic Qualification of the Target Rock Safety Relief Valve Pneumatic Supply Line (NRC Commitment)

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MODIFICATION M12-2-80-1 (Continued)

The change involved adding pipe supports and brackets to the Target Rock Safety Relief Valve pneumatic supply line so that the line is ensured to have seismic capability and also enhance the overall reliability of the pneumatic supply system.

The safety evaluation concluded that this modification upgrades the capability of existing equipment to withstand design basis events and enhance its operability, thus increasing its margin of safety and that its intended function will not be changed.

MODIFICATION M12-2-80-6 Replace the Shaft Bushings on All Twelve (12) Vacuum Breakers with Phosphor-Bronze Bushings The change involved replacing the teflon torus-to-drywell vacuum breaker valve bushings with phosphor-bronze bushings on all twelve (12) of the valves.

The safety evaluation concluded that the new bushings are softer and make a better seal; and as the new bushings have greater reliability, the function of the valves remains unchanged; thereby, the potential for creation of a new accident remains unchanged.

MODIFICATION M12-2-80-7 Provide Disc Replacement for the Twelve (12) Torus-Drywell Vacuum Breakers with Stronger and Dimensionally Same Discs The change involved replacing the 18-inch torus-drywell vacuum breaker valve discs of sand cast aluminum with wrought aluminum alloy discs for all twelve (12) of the valves.

The safety evaluation concluded that the new discs are stronger and have increased reliability; and as the function of the valves remains unchanged, the potential for creation of a new accident remains unchanged.

MODIFICATION M12-2-80-26 Remove Clad on Feedwater Nozzles and Install New Double Seal /

Triple Thermal Sleeve Feedwater Spargers The change involved replacing the interference fit spargers with the new dual seal interference type spargers per NRC commitments NUREG 0619 and General Electric FDI 494/23205, Rev. O.

The safety evaluation concluded that this nodification actually increases the margin of safety by decreasing the possibility of nozzle cracking, thereby preserving the primary pressure boundary integrity...

MODIFICATION M12-2-80-27 Installation cf a Temperature Monitoring System en the Feedwater

'Sparger Nozzles 1

The change involved providing attachments of thermocouples to the feedwater nozzles and routing of cables to a recorder outside of the primary containment.

b The safety evaluation concluded that the margin of safety would be increased because the monitoring system will provide an early warning of any leakage around the new thermal sleeves of the feedwater spargers installed by Modification M12-2-80-26.

MODIFICATION M12-2-80-33 i

j Modify the Existing Logic and Control Switches Such That Isolation Co.ndenser Valves 2-1301-1,

-2, and -4 are i

Prevented from Automatically Opening When the Group 1E Isolation Signal is Reset The change involved replacing the existing switches with General Electric type SBM control switches and modifying the circuitry so that automatic valve opening of the above-mentioned valves is prevented when ithe Group V isolation signal is reset.

The safety evaluation concluded that the margin of safety

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actually increases since the valves no longer open automatically upon a successful reset of the isolation signal.

i MODIFICATION M12-2-80-39 Change the Power Supply for the MSL Radiation Monitors 2-1705-2B and 2-1705-2D from the.RPS Bus to the ESS Bus 1

The change involved rewiring the 2B and 2D MSL radiation monitors to the ESS bus. By accomplishing this change, in the event that 'a loss of power occurred to the RPS bus, the resultant auxiliary power transient would be less severe an'd more in line with the FSAR.

The safety evaluation concluded that the probability the radia-tion monitors will perform their intended safety function is actually in-creased because of a more reliable power source.

MODIFICATION M12-2-80-42 Install an Auxiliary Relay to Ensure Electrical Isolation to the Automatic Depressurization System (ADS) Division I and Il Cables The change involved the addition of the General Electric relay j

type #CR 120 to ADS cable #20738 to ensure adequate and proper separation l

of Division I and II cables as specified by NRC Information Notice 79-32.

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MODIFICATION M12-2-80-42 (Continued)

The safety evaluation concluded that the margin of safety is actually increased because of the improved reliability of the ADS.

MCDIFICATION M12-2-80-44 Insta'11 a Miniature, Normally-Open, Momentary Contact Pushbutton Switch on IRM Monitors 11 Through 18 The change involved installing the above-mentioned switch across terminals 6 and 12 on mode selector switch S1A of the IRM monitors 11 through 18 and label the switch "INOP INHIBIT." This change allows routine, func-tional, and calibration surveillances in a more timely and efficient manner.

The wafety evaluation concluded that this installation does not affect the margin of safety as defined in the Technical Specifications.

MODIFICATION M12-2-80-45 Install Time Delay Relays to Prevent HPCI Steam Line Isolation Resulting from a Spurious HPCI Steam Line High Flow Signal The change involved replacing the 102A and 102B relays with new three (3) second time delay relays. These new relays are General Electric part #164C5257P007, and they assure that the HPCI steam line isolation signal is, in fact, due to continuous high flow and not a spurious signal.

The safety evaluation concluded that the margin of safety is in-creased since the HPCI system will become more resistant to spurious

,f isolation.

l MODIFICATION h12-2-80-47 Remove Valves 2-1501-151A(B) and 2-lS01-150A(B) and Install Supports on Valves 2-1501-92A(B) and 2-1501-90A(B) l The change involved removing LPCI valves 2-1501-151A(B) and j

2-1501-150A(B) and their associated piping. Also, supporting with hanger type support valves 2-1501-92A(B) and 2-1501-90A(B) and their associated piping to reduce the weld failures found on the 3/4" drain line.

The safety evaluation concluded that the margin of safety is actually increased with the addition of pipe supports and removal of unnecessary piping and valves.

MODIFICATION M12-2-80-50 Revise HPCI Circuitry to Have the Drain Valves and Auxiliary Oil Pump Remain in Their Emergency Mode After Reset of the Group II Isolation Signal _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _

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MODIFICATION M12-2-80-50 (Contir.ued)

The change involved replacing the two-position valve control switch and the two-position pump control switch with three-position switches and also adding seal-in relays so that the valves and pump operate in the emergency condition until reset to preclude a possible inadvertent activity release.

The safety evaluation concluded that the margin of safety is in-creased by keeping this equipment in the emergency node until no longer re-quired and then resetting it.

MODIFICATION M12-2-81-4 Install an Automatic Air Dump on the Scram Air Header as Required by the NRC per I.E. Bulletin 81-12 The change involv'd installing two pressure indicators and e

associated piping and valves along with scram air dump electrical circuitry changes so that the unit will scram quickly (approximately 30 seconds),

rather than the former 7 or 8 minutes, when the scram air header pressure is below its scram setpoint.

The safety evaluation concluded that the margin of safety has increased.

In the event of low pressure in the scram valve air header line, the unit will shut down automatically if the operator cannot act quickly enough.

MODIFICATION M12-2-81-5 Modify the Containment Purge and Vent Isolation Valves to Isolate on a High Radiation Signal in the Drywell per NRC NUREG-0737,Section II.E.4.2 I

The change involved modifying the Group II isolation logic for primary containment vent and purge valves 2-1601-22, -23, -24, -55, -57,

-58, -59, -60, -61, -62, and -63 so that the valves would isolate when a radiation signal from the containment radiation monitors occurred.

The safety evaluation concluded that the margin of safety is not reduced because no Technical Specification is involved in this modification.

MODIFICATION M12-2-81-8 Deactivation of Certain Supports on Safety-Related Systems per 1.E. Bulletin 79-14 The change involved removing D2 drywell snubbers #13, 14, 15, 16, 17, 18, 19, 20, 22, 23, 24, 25, 26, 27, 28, and 29 because they were no longer needed per an analysis of EDS Nuclear, Inc.

The safety evaluation concluded that the piping systems meet or exceed the original design. Deactivation will not 'ecrease the safety factor defined by the Technical Specifications. - - -

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MODIFICATION M12-2-81-27 Install a Drain Line on HPCI Steam Supply Line 2-2305-10" The change involved installing a 1" drain line on the 10" line 2-2305, above the torus area of the line and then rcuted to the line up-stream of the 2-2301-3 valve. This was accomplished to alleviate conden-sate buildup in the steam line.

The safety evaluation concluded that the margin of safety is not reduced because'this change does not affect the basis for any Technical Specifications.

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l AMENDMENTS TO FACILITY LICENSE i

DPR-25 (UNIT 3) OR ASSOCIATED 4

i TECHNICAL SPECIFICATIONS j

AMENDMENT #46 On December 29, 1980, the Nuclear Regulatory Commission issued i

Amendment #46 to the Dresden Facility License No. DPR-25. The follow-ing is a list of the changes in the license for the incorporation of i.

the Amendment.

l The Amendment allows the 2/3 chimney sampling system to be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for installation of the high range noble gas monitor, with certain very definitive conditions as specified very clearly on page 133a.

I i

AMENDMENT #47 1

1 On December 31, 1980, the Nuclear Regulatory Commission issued Amendment #47 to the Dresden Facility License No. DPR-25. The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment specifies that the component in-service inspection I

program shall be performed per Section:[L of the ASME Boiler and f

Pressure Code as required by 10 CFR 50, Section 50.55alg), except where specific written relief has been given by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

2 AMENDMENT #48 i

On February 6, 1981, the Nuclear Regulatory Commission issued l

Amendment #48 to the Dresden Facility License No. DPR-25. The follow-ing is a list of the changes in the license for the incorporation of.

1 the Amendment.

Paragraph 3.J The Amendment states that a program to reduce leakage from those systems outside containment that could contain highly radioactive

]

fluids during a serious transient or accident to as low as practical levels. The program shall include maintenance, inspec-tion, and testing requirements at intervals not to exceed refuel-ing outages.

4 l

Paragraph 3.K The Amendment states that a program which ensures capability to accurately determine airborne iodine concentrations in vital areas under accident conditions must be implemented. It shall include training of personnel, procedures for monitoring, and provisions for maintenance of sampling and analysis equipment.

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i AMENDMENT #48 (Continued)

Table 4.2.1 The Amendment provides time limits on testing, calibration, and checks on instrumentation for the Safety / Relief Valve Monitoring System.

AMENDMENT #49 On February 11, 1981, the Nuclear Regulatory Commission issued Amendment #49 to the Dresden Facility License No. DPR-25. The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

The Amendment states that the licensee shall fully implement and maintain in effect all provisions of the Commission-approved safeguards contingency plan. These shall include amendments and changes made pursuant to the authority of 10 CFR 50.54(p) and 10 CFR 2.790(d) and 10 CFR 73.40(b) and 10 CFR 73.55(b)(4).

AFEND1ENT #50 On March 27, 1981, the Nuclear Regulatory Commission issued Amendment

50 to the Dresden Facility License No. DPR-25.

The following is a list of the changes in the license for the incorporation of the Amendment.

The Amendment provides time limits for monitoring, sampling and recording results of the reactor coolant system leakage as specified in 4.6.D (reactor sump flows).

AMENDMENT #51 On April 3, 1981, the Nuclear Regulatory Commission issued Amendment

51 to the Dresden Facility License No. DPR-25.

The following is a list of the changes in the license for the incorporacion of the Amendment.

The Amendment allows removal of, additions to, and reclassifica-tion of certain shock suppressors (snubbers) as' outlined in I.E. Bulletin 79-14.

AMENDMENT #52 the Nuclear Regulatory Commissica issued Amendment On April 30, 1981;~

DPR-25; the following is a

52 to the Dresden Facility License Nos list of the chan;ss in the license for the incorp; ration of the Amendment.

i The Anendment establishes the new values for the, flow control line, the" core thermal power calcelat ions, and the, scran and rod' bloc.t settings. Also, it providas amplementation and sarveillance requirements for these values.

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AMENDMENT #53 On June 25, 1981, the Nuclear Regulatory Commission issued Amendment-

53 to the Dresden Facility License No. DPR-25. The following is a l

list of the changes in the license for the incorporation of the j

Amendment, i

The Amendment clarifies the term "operabic" and its many uses as st'ated in the Technical Specifications, specifically on pages i

i, 2, 21a, 21b, 135, 156d, 156g, 156h, and 1561.

4 AMENDMENT #54

(

On June 30, 1981, the Nuclear Regulatory Commission issued Amendment.

54 to the Dresden Facility License No. DPR-25. The following is a list of the changes in the license for the incorporation of the Amendment.

i i

The Amendment establishes conditions for continued operation of Unit 3, utilizing only one recirculation pump. All of these j

j very specific conditions are listed on page 5 of the revised l

Technical Specifications.

1 i

AMENDMENT #55 On August 21, 1981, the Nuclear Regulatory Commission issued Amendment #55 to the Dresden Facility License No. DPR-25. The follow-i ing is a list of the changes in the' license for the incorporation of the Amendment.

I The Amendment provides for the position of Shift Technical Advisor (SCRE) and that individual's qualifications and duties.

Also, it provides for minimum shift crew composition and its i

implementation.

i AMENDMENT #56 i

On October 29, 1981, the Nuclear Regulatory Commission issued Amendment #56 to the Dresden Facility License No. DPR-25. The follow-ing is a list of the changes in the license for the incorporation of the Amendment.

I The Amendment allows the installation and use of five (5) high density fuel storage racks on the Unit 3 spent fuel storage pool. Also, it provides very definitive provisions for their use.

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UNIT 3 OTHER CHANCES, TESTS AND EXPERIMENTS MODIFICATION M12-3-79-39 Install Individual Control Switchc. for the Holdup Line Drain Valves on Panel 903-54 The change involved installing wiring and control switches on panel 903-54 so that the holdup drain valves are controlled from their own independent switches, rather than by switch 5440 which operates the offgas and drain valves together.

The srJety evaluation concluded that the margin of safety remains the same since the individual valve operation remains the same electrically.

MODIFICATION M12-3-79-47 Ir. stall a !!PCI Automatic Initiation Pushbutton in Control Room to Allow Rapid Manual System Initiation The change involved installing a General Electric type CR 2940 switch in parallel with other existing low reactor water level and primary containment high pressure sensors.

It also has an arming collar to prevent accidental initiation.

The safety evaluation concluded that the margit. of safety will not be affected because the modification will ensure a manual fast start capability of the HPCI system.

.E MODIFICATION M12-3-80-31 Provide New +60 to -340 Scales for the Lower Wide Range Reactor Water Level Yarways and the GEMAC Recorder The change involved recalibrating the Wide-Range Yarways to the new settings per NRC NUREG 0626-II-K.3.27.

This requirement states that all reactor water level instrumentation be referenced to the same level in order to reduce the possibilities of operator confusion.

The safety evaluation concluded that the margin of safety is in-creased because the operators will more easily make comparisons among reactor water level instrumentation which more accurately record existing conditions.

MOLIFICATION M12-3-80-33 Modify the Existing Logic and Control Switches Such That Isolation Condenser Valves 3-1301-1, -2, and -4 are Prevented from Automatically Opening When the Group V Isolation Signal is Reset MODIFICATION M12-3-80-33 (Continued)

The change involved replacing the existing switches with General Electric type SBM control switches and modifying the circuitry so that automatic valve opening of the above-mentioned valves is prevented when the Group V isolation signal is reset.

The safety evaluation concluded that the margin of safety actually increa'ses since the valves no longer open automatically upon a successful reset of the isolation signal.

MODIFICATION M12-3-80-43 Install a Miniature, Normally Open, Momentary Contact Pushbutton Switch on SRM Monitors 21 Through 24 The change involved installing the above-mentioned switch across terminals 6 and 12 on mode selector switch S1A of the SRM monitors 21 through 24 and label the switch "INOP INHIBIT." This change allows routine, I

functional, and calibration surveillances in a more timely and efficient manner.

The safety evaluation concluded that this installation does not affect the margin of safety as defined in the Technical Specifications.

MODIFICATION M12-3-80-44 Install a Miniature, Normally Open, Momentary Contact Pushbutton Switch on IRM Monitors 11 Through 18 The change involved installing the above-mentioned switch across terminals 6 and 12 on mode selector switch S1A of the IRM monitors 11 through 18 and label the switch "INOP INHIBIT." This change allows routine, functional, and calibration surveillances in a more timely and efficient manner.

The safety evaluation concluded that this installation does not affect the margin of safety as defined in the Technical Specifications.

MODIFICATION M12-3-80-45 Install Time Delay Relays to Prevent HPCI Steam Line Isolation Resulting from a Spurious HPCI Steam Line High Flow Signal The change involved replacing the 102A and 102B relays w*th new three (3) second time delay relays. These new relays are General Electric part #164C5257P007, and they assure that the HPCI steam line isolation signal is, in fact, due to continuous high flow and not a spurious signal.

The safety evaluation concluded that the margin of safety is in-creased since the HPCI system will become more resistant to spurious isolation.

MODIFICATION M12-3-81-4 Install an Automatic Air Dump on the Scram Air Header as Required by the NRC per I.E. Bulletin 81-12 The change involved installing two pressure indicators and associated piping and valves along with scram air dump electrical circuitry changes so that the unit will scram quickly (approximately 30 seconds),

rather than the'former 7 or 8 minutes, when the scram air header pressure is below its scram setpoint.

The safety evaluation concluded that the margin of safety has increased. In the event of low pressure in the scram valve air header line, the unit will shut down automatically if the operator cannot act quickly enough.

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d Dresden 2 and 3 Safety / Relief Valve Statement During 1981, the electrcanatic relief valves on Unit 2 were challenged several times:

a) Uponstart-upafterrEfuelingoutageon5-10-81eachvalvewas tested twice (at low and rated pressure); the valves functioned properly.

b) During the period when HPCI was declared inoperable the valves were tested daily on 6-2, 6-3, 6-4 and 6-5-81 and functioned Properly.

The electromatic relief valves on Unit 3 were not challenged during 1981.

During Unit 2 refueling outage, four of the eight safety valves were replaced and tested. No failures of these safety valves.have been noted to date.

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