ML20249C849
| ML20249C849 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/30/1999 |
| From: | Heffley J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JMHLTR:#99-0112, NUDOCS 9910290239 | |
| Download: ML20249C849 (15) | |
Text
O>mmonwealth Ihn Company i-Drrwico Generating station 6500 Nonh Darwien Ibud 10CFR50.4 Morris, it 604so 10CFR50'59 l'
Tei H15-9i2 292c j
i October 21,1999
)
JMHLTR: #99-0112
' U.S. Nuclear Regulato,y Commission ATTN: Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 1,2, and 3 Facility Oparating License Nos. DPR-2, DPR-19 and DPR-25 NPC Docket Nos. 50-01,50-237 and 50-249
Subject:
1999 Third Quarter 10 CFR 50.59 Report Enclosed is the 1999 third quarter report of completed Changes, Tests, and Experiments evaluated per 10 CFR 50.59 (b)(2) for Dresden Nuclear Power Station. This report also contains a summary of the safety evaluations completed in accordance with 10 CFR 50.59(a)(2).
Should there be any questions regarding this report, please contact Mr. D. F. Ambler at (815) 942-2920, ext. 3800.
Respectfully, l
Y-Heff ey Vice Preside Dresden Nuclear Power Station Enclosure cc:
Regional Administrator-Region l11 NRC Senior Resident Inspector - Dresden Nuclear Power Station 991029' f
990930 PDR
/
05000010 j
R PDR A Unkom Gimpany l
~
E 1
.l l
10 CFR 50.59 Quarter: 1999-03 l
Safety Evaluation Summary Report i
Safety Evaluation Numb 0r: 1997-04-245 Type of Safety Evaluation:
Set Point Changes Evaluation Reference Number: SPC 2-97.037
Title:
Feedwater Heater Area Rad Monitor (ARM) Sta. #23 DCP 9700309 Desenption: The Area Rad Monitor Indicator and Trip Unit, and Sensor / Converter unit with a detection range of 0.1-1,000 mR/Hr will be replaced with a new ARM Indicator and Trip Unit and Sensor / Converter with a detection range of 1.0 to 10,000 mR/Hr. A setpoint change will also be included. The high radtation setpoint will be changed from 450 mR/Hr to a value determined by Health Physics (HP) based on background dose and the downscale setpoint will be changed from 0.1 mR/Hr to 1.0 mR/Hr. The effect of this change is to provide an ARM with a sufficient range for on-scale indication and an alarm setpoint sufficiently above the normal operating level to detect abnormal radiation levels as determined by HP.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02-101 Type of Safety Evaluation:
Modification Evaluation Reference Number: M12-3-96-001
Title:
Install Advanced Resin Cleaner (ARC)
Desenption: This modification is to install the advanced rcsin cleaner (ARC). The ARC is a device for cleaning the ion-exchange resins in the deep bed condensate demineraliger system. An advanced resin cleaner will be installed in the Unit 3 condensate demineralizer system. The condensate demineralizer sys ems are cross-connected to permit use of the advanced resin cleaner with either unit. TF PC foatures a vibrating-screen system containing a coarse screen and fine screen in sens and a high-pressure water spray both of which aid in
)
removing corrosion products and resin fines ' rom the resin heads. The spray water and cleaned resin-transfer water are recycled continuously in minimize the volume of wastewater generated.
Recult:
This evaluation determined that an unreviewed safety question did not exist.
]
Safety Evaluation Number: 1998-03-186 Type of Safety Evaluation:
Exempt Change Evaluation Reference Number: E12-0-98-201 i
Title:
OSRE Modification
==
Description:==
The proposed activity for this Exempt Change is to provide for secunty installations directed by the Operational Safeguards Response Evaluation (OSRE) The OSRE installations and associated electrical requirements are being added to provide an additionalline of defense for the Station Secunty Group. This additional defense is being directed by NRC Inspection Manual, inspection Procedure 81110, which provides for the following inspection objectives:
- 1. To evaluate a licensee's ability to respond to the extemal design basis threat by focusing on (1) the interaction between a licensee's operations and secunty departments in estabhshing priorities for protecting equipment and (2) the protective strategies used.
- 2. To review the impact of security measures on safe plant operations.
Supersedes Safety Evaluation 1998-02 164 i
i Result:
This evaluation determined that an unreviewed safetv question did not exist.
Page 1 of 14
10 CFR 50.59 Quarter: 1999-03 Safety EvaNation Summary Report Safety Evaluation Number. 1998-03-209 Type of Safety Evaluation:
Miscellaneous Evaluation Reference Number: DCP 9800245 & 9800247
\\
Title.
Turbine Low Pressure Hood Turbine Trip
==
Description:==
Modify turbine trip logic such that the time delay relay normally closed contact K3-D1C will have a second contact in parallel. This will add redundancy to turbine trip logic in order to prevent unnecessary turbine trips and reactor scrams.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number:1998-04-253 Type of Safety Evaluation:
Modification Evaluation Reference Number: M12-3-98-001
Title:
Unit 3 Voltage f4gulator Replacement
==
Description:==
The modification will replace the Unit 3 main generator voltage regulator. The modication will also completely remove the voltage regulator amplidyne. The existing voltage regulator has aged beyond its expected service life afid is no longer capable of sustained reliable performance.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-279H Type of Safety Evaluation:
Miscellaneous Evaluation Reference Number: DCP 9800424
Title:
Unit 2 HPCI GSLO Condenser Vent Line
==
Description:==
Install a small bore vent line from the HPCI Gland Seal Leak Off Pump to the Gland Seal Leak Off Condenser in order to enhance air removal from the pump and the associated piping.
This vent line will make use of installed taps ion the condenser and on the pump. The design calls for an inline onfice installed as part of the design to limit flow and reduce the pressure at the GSC connection.
Validation of Previous Safety Evaluation 1998-04-258 Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-280 Tyoe of Safety Evaluation:
Miscehaneous Evaluation Reference Number: DCP 9900293
Title:
Unit i Service Air Compressor / f nin Line
==
Description:==
The proposed design changes associated with DCP 9800293 (DCNs 0012b7M and 001258M)
~
will replace the existing water-cooled Unit 1 service air compressors with a single air-cooled air compressor and provide a new clean demineralized water supply line to the Unit 1 Fuel Building from the Unit 2/3 Clean Demineralized Water System.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Page 4 of 14
10 CFR 50.59 Quarter: 1999-03
- Safety Evaluation Summary Report Safety Evaluation Number - 1998-04-282 Type of Safety Evaluation.
Miscellaneous I
Evaluahon Reference Number: DCP 9800302
Title:
Unit 2HPCI
==
Description:==
Revise the control circuit for HPCI Auxiliary Oil Pump (AOP) 2-2303-AOP. The existing design does not allow the HPCI AOP to be secured (stopped! tripped) from the Control Room. As a result, current procedures require station persortnel to enter the Reactor Building and trip the HPCI AOP at MCC 2A (CUB B01) when the 250 VDC battery chargers are not available. This is allowed since the HPCI AOP is not required to operate once HPCI Turbine reaches 2000 RPM. Entering the Reactor Building following a Design Basis Accident (DBA)is a major personnel safety concern due to the potential high radiation levels. This design change will allow the HPCI AOP to be secured by the contro! switch from the Control Room while the LOCA signalis present.
Result:
This evaluation determined that an unreviewed safety question did not exist.
l Safety Evaluation Number: 1998-04-286 Type of Safety Evaluation:
FSAR Change Evaluation Reference Number: DCP 9800368,9800369
Title:
ATM Time Delay Relay Setpoint Changes
==
Description:==
- Revise time requirements for the time delay relays utilized for ATWS reset. G E. revised requirements to reflect plant specific conditions as described in G.E. letter C1100261 (65) dated 6/8/95. This change also allows more flexibility in setting system reset timers.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-01-004H Type of Safety Evaluation:
Temporary Alteration Evaluation Reference Number: Temp Alt 111-03-99, DCP 9900008
Title:
Turbine Building Equipment Drain Sump Pit
==
Description:==
Install a submersible sump pump (120V max) and transfer line in the Turbine Building Equipment Drain Sump Pit. This transfer line will permit fluids in tha Equipment Drain Sump Pit to be transferred via the submersible pump and transfer line to the Turbine Building Floor Drain Sump Pit.
Validation of Previous Safety Evaluation 1998-04-249 Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number; 1999-01-009 Type of Safety Evaluation:
Temporary Alteration Evaluation Reference Number: SPl 99-01-003 Rev. 00
Title:
Special Procedure to install Temporary Actuator on Head Spray Valve 3-0205-24 Desenption: The special procedure gags valve 3-0205-24 in place, removes MOV actuator, and installs temporary actuator to allow valve movement when required to support unit shutdown.
Result:
This evaluation determined that an unreviewed safety qi estion did not exist.
j Page 5 t,T 14 1
I l
i
]
g i
.10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report i
Safety Evaluation Number: 1999-01-021H Type of Safety Evaluation:
Proceduie j
Evaluation Reference Number: SPI 98-11-037
Title:
Unit 3 Voltage Regulator in-Service Test Desenption: The proposed activity is a Special Procedure for Post Modification Testirig. The mGdification to be tested replaced the Unit 3 Generator voltage regulator.
Validation of Previoes Safety Evaluation 1998-04-253 l
Result:
This evaluation determined that an unreviewed safety question did not e xist.
Safety Evaluation Number: 1999-01-027H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR 3/4 25, Rev.1
Title:
RWCU Area Temperature Monitoring
==
Description:==
The DATR 3/4 25 for RWCU Area Temperature Monitoring is being revised to reflect the changes of Modification M12-3-97-006 which is upgrading the Area Temperature Monitoring i
of the RWCU system to include automatic isolation of the RWCU System when a leak is j
detected. The revision to the DATR only affects Unit 3 and lists the appropriate actions to be j
taken when one or both channels of the leak detection system are unavailable. When one channel is unavailable for a particular area, it must be restored within 30 days or RWCU must be isolated. If both channels of a given area are unavailable, a visual venfication must be conducted once per day. If both channels of a given area are unavailable, a visual verification must be conducted once per day. If both channels of a given area remain inoperable for 7 days, the RWCU system must be isolated. Also, a surveillance is required once per 18 months to verify the system is functional. The requiremerts for Unit 2 are unchanged.
Validation of Previous Safety Evaluation 1998-03-197, Rev.1 Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-01 041 Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DCP 9700062
Title:
Drywell Floor Drain Sump Transmitter Replacement Descwtion: The existing flow transmitter requires replacement. In addition, the Drywell Floor Drain Sump Pump Totalizer winng will be revised to allow the totalizer to start and continue totalizing while the isolation valves are open when flow is present. The wiring change allows the totalizer to provide an actuated indication of.he total volumo of unidentified leakage pumped from the Drywell Floor Drain Sump.
Result.
This evaluation determined that an unreviewed safety question did not exist.
Page 4 of 14
I e
10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report.
Safety Evaluation Number: 1999-01-043H Type of Safety Evaluation: Procedure l'
Evaluation Reference Number: SPI-99-03-006
Title:
Unit 3 Voltage Regulator on-line Firing Circuit Adjustment
==
Description:==
The proposed activity is a Special Procedure (SP) cor.taining testing necessary to adjust both Firing Circuit modules of the Dresden Unit 3 voltage regulation equipment.
Validation of previous Safety Evaluation 1998-04-253 Result:
This evaluation determined that an unreviewed safety Question did not exist.
Safety Evaluation Number: 1999-01-045 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DGP11
Title:
Closing Main Steam Line Drain Valve 2(3)-220-3 During Power Operations
==
Description:==
Change valve 2(3)-220-3, Main Steam Lines inboard Drain Valve, position during plant operations. The valve position has been changed from open to closed after unit startup.
This change will prevent the loss of steam, giving each unit an 0.3 MWe gain in generation.
Also valves 2(3)-3008A-500,2(3)-3008B-500,2(?)-3008C-500 and 2(3)-3008D-500 will be closed. These valves are the manual isolations to the flow restricting onfices that feed into the header controlled by the 2(3)-220-3 valve. The initial start-up will follow the current practice of opening the 2(3)-220-90 valves, which bypass the flow restncling orifices, to ensure complete draining of the main steam lines. Procedure DGP 1-1 will have to add this on a;tep G.106 Also drawings M-12 and M-345 will have to be changed to show this valve as normally c% sed.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-02-051 Type of Safety Evaluation: FSAR Change L. -luation Reference Number: DFL 99-018, DSAR #11
Title:
Revise ODCM to reflect Unit 1 As-Built
==
Description:==
- 1) Revise the Off-Site Dose Calculation Manual (ODCM), Unit 1 DSAR, and Unit 2/3 FSAR to accurataly reflect plant configuration and operation for Dresden Unit 1.
- 2) Retire the Unit i Discharge Canal Sampler
- 3) Add a footnote to CSCM Table 12.2-1 and correct the LLD value in Action #10 on the same table.
These changes to the ODCM, Unit 1 DSAR and Unit 2/3 FSAR will not affect the operation of
)
Dresden Unit 1 and Unit 2/3.
i Result:
This evaluation determined that an unreviewed safety question did not exist.
I l
Page 5 of 14 1
1 I-1
10 CFR 50.59 Quarter: 1999-03
' Safety Evaluation Summary Report Safety Evaluation Number: 1999-02-053 Type of Safety Evaluabon:
Procedure Evaluation Reference Number: DATR 3/4 6.2 Revision
' Title-
' The Yechnical Support Center (TSC) HVAC System
==
Description:==
Revised DATR to reflect new Limiting Condition for Operation and surveillances.
l.
- Result
This e 't Jation determined that an unreviewed s'afety question did not exist.
f Safety Evaluation Number: 1999-02-055 Type of Safety Evaluation:
Technical Specification Change Evaluation Reference Number: Tech Spec Section 4.7.D.6
Title:
Main Steam IsrAation Valve Leakage Amendment Desenption:. The Technical Specification section 4.7.D.6 will be amended to remove the allowable leakage limit for a single main steam isolation valve (MSIV) of 11.5 scfh and replace it with the maximum pathway leakage limit of 46 scfh for all valves The maximum pathway leakage is
' established by the Primary Containment Leakage Rate Testing Program which determines the leakage rates in accordance with the requirements of 10 CFR 50 Appendix J. The value of 46 scfh is the current licensing basis of the units. The effect of the change doel not reduce the margin of surety to the 10 CFR 100 limits for off-site exposure kmits for a loss of coolant accident in the containment as determined by the NRC for Systematic Evaluation Program (SEP) topic XV-19. Other accident scenarios, which assume total MSIV leakage of 46 scfh, or those for which MSIV leakage is not a factor in the analysis will not be affected. The aggregate kmit of 46 sc* would provide additional flexibility in scheduling maintenance for the MSIVss. Monticello suce 1sfully changed their Technical Specifications hmit from the single vatve limit to the agg u *'s limit of 46 scfh in 1996..
Resutt:
This evaluation identified the need to change the Technical Specifications.
Safety Evaluation Number: 1999-02-057 Type of Safety Evaluat on:
Miscellaneous i
Evaluation Reference Number: DATR 3/4 4
Title:
DEOP Support Systems & Components I
==
Description:==
Revised LCO 3.4.2 to require at least one LPCI or Core Spray pump operable and capable of supplying water to the reactor from the CSTs rather than requiring all LPCl and Core Spray l
paths.. Corrected temperature sensor numbers for Unit 2 IC area in Table 3 4.5.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-02-064H Type of Safety Evaluation:
Procedure Evaluation Reference Number: DOP 5650-02, Rev 02 Title.
EHC Pressure Regulator Transfer
==
Description:==
This procedure revision is to incorporate data values for EHC System from SLRC Modification, DCP 9800432.
Validation of previous Safety Evaluation 1999-01-008.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Page 6 of 14
10 CFR 50.59 Quarter:
1999-03 Safety Evaluation Summary Report Safety Evaluation Number:
1999-02 069H Type of Safety Evaluation:
Procedure Evaluation Reference Number: SPI 99-05-008
Title:
Revision to SPI 98-02-017, Radvesste Cleanup
==
Description:==
This project hvolves the removal, processing and packaging for disposal of residual wastes, spent resins, and filter elements currently contained within the Dresden Unit 1 Radwaste Facility's tanks, vaults, sumps, and filter housings.- This will be accomplished by pumping, slurrying. filtering and dewatering through disposal liners. All process liquid wastes will be transferred to Unit 1 Chemical Cleaning Facility or Unit 2/3 Radwaste for additional proce'esing. An additional drying step of the waste product will be performed in order to concentrate the remaining waste into a smaller disposal volume. The project vill be performed by a Processor Vendor (NUKEM) utilizing Station approved Vendor Procedures r.nd equipment.
Validation of Previous Safety Evaluation 1997-03-161.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-02-072H Type of Safety Evaluation:
Procedure Evaluation Reference Number: DEP 0040-42, Rev. O
Title:
Set Limits on Circulating Water Pump Discharge Valve v.aile Other Pumps are Running Desenption: New procedure to capture an evolution previously performed using a specia! procedure to set the limits on a circulating water pump discharge valve while other pumps are running.
This requires temporarily disabling the automaticinterlocks between the applicable Circulating Water Pump and its associated discharge valve while running the pump and then restores it to normal configuration.
Vahdation of Previous Safety Evaluation 1998-04-259 Result:
Th'. evaluation determined that an un'eviewed safety question did not exist.
Safety Evaluation Number: 1999-02-075H Type of safety Evaluation:
Procedure Eva!ucion Reference Number: SPl 99-06-011
Title:
SP for Unit 3 Voltage Regulator on Line Finng Circuit Adjustment
==
Description:==
The propos6d activity is a Special Procedure (SP) containing tes+'ng necessary to adjust both
' Firing Circuit modules of the Dresden Unit 3 voltage regulation equipment.
Validation of previous Safety Evaluation 1998-04-253.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-02-076 Type of Safety Evaluation:
Procedure Evaluation Reference Number: SPI-99-05-010, Revision 0
Title:
Hydrogen and Oxygen System Tie In
==
Description:==
This special procedure performs the tie in of the new liquid hydrogen and oxygen tanks to i
the Unit 3 generator hydrogen system and the Unit 2 hydrogen / oxygen addition and generator hydrogen system. This procedure will also alegn the syste.m to use as much inventory in the existing supply sources as possible.
Result:
This evaluation determined that an unreviewed safe'y question did not exist.
Page 7 of 14
r t
10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report l
Safety Evaluation Number-1999-02-078 -
Type of Safety Evaluation:
- Procedure Evaluation Reference Number: SPI 99-06-012
Title:
Transfer of Unit 1 T-109 to Unit 2/3 Radweste Desenption: A temporary air operated pump will be. installed in the Radwaste TankNault area to recirculate the T 109 tank contents through a NUKEM Demineralizer. Once the water is cleaned up to meet Unit 2/3 Radwaste Chemistry specifications, the water will be transferred by the same pump to Unit 2/3 Radwaste through a temporary connection to the Unit 1 to Unit 2/3 Radwaste cross-tie header.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1939-02-083 Type of Safety Evaluation: Miscellaneous i
Evaluation Reference Number: ODCM Revision 2, April 1999
Title:
Off-Site Dose Calculation Manual. Dresoen Docket Numbers: 50-10,50-237,50-249 Descrir,,, tion: C.',anges are being made to the Dresden ODCM in order to simplify the text. Descriptive text, references and historical information are being removed or clanfied. These changes are common to all Comed ODCMs. The Dresden specific sections (Chapter 10,11 and 12 and Appendix F) are not being changed by this revision.
One incorrect value in the ODCM is being changed to match the correct value found in Reg Guide 1.109.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number:1999-02-086 Type of Safety Evaluation: Modification Evaluation Reference Number: M12-2(3)-85-060
Title:
Outage Power Feeder Modifications
==
Description:==
The modifications provide an alternate source of power for outage related loads.
Construction documents were issued for 52 new cables four new MCCs, one new switchgear, three 480-120/240V transformers, as well as various disconnects, protective devices, cable trays, conduits, and accessories.
The reason for the design changes is to provide added capacity fur temporary, j
outage-related loads. The reason 1:sr this evaluation is to evaluate and justify the current, j
partially-installed configuration.
i NOTE: The purpnse of this safety evaluation is to assess the as-built configuration of the Outage Power Feeder Modifications, which are not fully installed. This evaluation covers issues which pertain to thrt assessment of the partialinstallation. It doe 3 not cover design issues related to the full modifications. The safety evaluation presently on file for the full modifications, as re-validated during evalu ation of FCRs, remains valid.
j Result.
This evaluation determined that an unreviewed safety question did not exist.
Page 8 of 14
10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report Safety Evaluation Number 1999-03-092H Type of Safety Evaluation:
' Procedure Evaluation Reference Number: SPI-99-05-010, Revision 1
Title:
Hydrogen and Oxygen System Tie in Desenption: This procedure performs the tie in of the new liquid hydrogen and oxygen tanks to the Unit 3 generator hydrogen system and the Unit 2 hydrogen / oxygen addition and generator hydrogen systems. This procedure will also align the system to use as much inventory in the existing supply sources as possible.
Vahdation of previous Safety Evaluation 199942-076 Result:
This evaluation determined that an unreviewed safety questo" elid not exist.
Safety Evaluation Number: 1999-03-093 Type of Safety Evaluation:
f SAR Change Evaluation Reference Number: DFL 99-034
Title:
Revise Section 13.5 to include Provisions to Use NGG Procedures Descriptioni Revise UFSAR Section 13.5 to include provisions to use NGG procedures reviewed and approved on-site in place of Station Procedures for various tasks.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 199603-094 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DCP 9900050
Title:
Permanent spool pieces between SDC and FPC systems Desenption: Currently during refuel outages, spool pieces are connected from the Fuel Pool Cooling (FPC) system to the Shutdown Cooling (SDC) system pump suctions and heat exchanger outlets in order to a!!gn SDC in the fuel pool cooling assist mode. Once assisted fuel pool cooling is no longer needad, the upool pieces are removed and blind flanges installed. This modifcation will design and install spool pieces that will permanently remain at these connections. Each spool piece will consist of a high prt.ssure spectacle flange (which consists of a blind and full bore spectacle), ; low pressure isolation valve, and a low pressure flange.
Result:
This evaNation determined that an unreviewed safety question did not exist.
l Page 9 of 14 I
)
I 10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report Safety Evaluation Number: 1999-03-095 Type of Safety Evaluation:
Miscellaneous Evaluation Reference Number-Abnormal Component Line-ups
Title:
Abnormal Component Line-ups Condenser vaive taps for temporary sightp<s
==
Description:==
An Abnormal Component Line-ups Sheet was completed to operate valve laps on the West Main Condenser water-boxes. This evolution is required after pipe caps on the nipples.
attached to the valves are removed and 30' of temporary ty-gon tubing is attached with double hose clamps and ty-wraps. The tubing will be used as a sightglass showing the height of water with 3 CW pumps operating in the outlet water-boxes. Afterwards, the temporary sightglass will be removed and the valves closed and the pipe caps replaced. This evolution is needed to determine if the condenser tubes are full of Circulating Water for proper thermal efficiency and heat exchanger operation.
Result:
Safety Evaluation Number: 1999-03-096H Type of Safety Evaluation:
Miscellaneous Evaluation Reference Number: DCP 9800329
Title:
Unit 2 HPCI Drain Line Support Modification
==
Description:==
This Design Change Package (DCP) has 2 DCN's to complete - DCN 001314M modifies four existing and adds three new pipe supports to Unit 2 HPCI drain line 2-2323-1"-L; also adds new support for SW line 2-3912-16"-0. DCN 001315M ::dds three, removes three existing, and modifies one support for HPCI liens 2-2324-1"-L and 2-2309-2"-L.
Validation of Previous Safety Evaluation 1997-01-077 51esult:
This evaluation determined that an unreviewed safety question did not exist.
)
i Safety Evaluation Number: 1999-03-100 Type of Safety Evaluation:
Modification Evaluation Reference Number: DCP 9900081
Title:
Install Additional Battery Cells to the Unit 2, Alternate 125-V Station Bauery Description' The Unit 2125-V Alternate Station Battery was added in 1990 to eliminate dual unit outages for battery testing and cell replacements of the normal station battery. The battery was installed
. in the Unit i HPCI building (now 2/3 SBO building). Existing spare cables between the SBO building and the plant were utilized to connect the battery. A 60-cell battery was installed to compensate for the voltage drop as a result of the long cable run. As part of the initial i
design, it was recommended that additional cables be paralleled with the existing feed cables to further reduce the voltage drop as the battery ages and the capacity decreases. The installation of the parallel cables did not get implemented.
In December 1997. Operability 97108 addressed tne voltage drop concerns and it was determined that the alternate battery was operable. However, a station commitment was made to install additional cells to increase the battery voltage in anticipation of the reduced battery capacity due to aging.
This design change installs three (3) addition cells to the Unit 2125-V Alternate Station Battery in fulfillment of tNs commitment. The total number of cells will be increased from 60 to 63.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Page 10 of 14
m 10 CFR 50.59' Quarter: 1999-03 Safety Evaluation Summary Report Safety Evaluation NumberL 1999-03105 :
Type of Safety Evaluation:
Temporary Alteration Evaluation Reference Number: DCP 9900212, TALT 1119-99
Title:
Unit 2 Main Condenser Chemical Cleaning
==
Description:==
Support the chemical cleaning of the Unit 2 Main Condenser,2-3301, during Refueling Outage D2R16. This Safety Evaluation shall address the facility changes required to support the chemicalinjection and the carbon dioxide removal system. Special Procedure 99-08-030, Unit 2 Main Condenser Acid Cleaning, Tracking Number 1999-03-118 shall address the operational aspects of the cleaning process. The following facility changes shall be performed' install a method of injecting sulfuric acid into the Circulating Water System. This shall be accomplished by temporarily replacing the manway access cover to the Circulating Water Header,2-4401-168*-L. The temporary replacement cover shall contain a quilt for sulfuric acid injection and vent line to release any carbon dioxide, which may become entrained in the manway.
Install a temporary ventilation system on the 2-3301 A East Condenser Waterbox to remove any carbon dioxide which does not remain entrained in the circulating water. This shall be accomplished by removing the 2-4926A-700, Circulating Water / Water Box Vent Trap Valve from the East Water Box North Condenser Half and installing a four inch isolation valve and four inch vent hose to a dewatering tank located on the Turbine Building Elevation 561*-0".
The dewatering tank shall be vented via a hose through the Unit 2 Turbine Building Trackway to the outside atmosphere.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-106H Type of Safety Evaluation:
FSAR Change Evaluation Reference Number: DFL 99-040
Title:
UFSAR Saction 6.5.3.2 Revision
Description:
A revision to UFSAR section 6 5.3.2 is required to address modificatior,4 P12-3-90-658 and M12-3-90-066 which electrically disconnected and removed remote control for the 3-7503 MOV. UFSAR section 6.5.3.2 currently contains a note which reads " Note: valve MO 2-7503 is retained open with remote control removed " The note is being revised to read, " Note:
valves MO 2-7503 and 3-7503 are retained open with remote control removed." A previous safety evaluation, tracking number 1997-01-073, is being validated to serve as the evaluation for this change.
Validation of previous Safety Evaluation 1997-01-073 for M12-2-90-066, WR #D26927 Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-107 Type of Safety Evaluation.
FSAR Change Evaluation Reference Number; DFL 99-041
Title:
UFSAR Section 11.3 3.3 Effects of Hydrogen Addition
==
Description:==
Change; the values for dose rates to the nearest public individual due to Hydrogen Water Chemistry. This raises the highest value Insted to 8 mrem / year compared to 40CFR190 limit of 25 mrem /yer.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Page 11 of 14
g l
4 l
i 10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report
' Safety Evaluation Number: 1999-03-108 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DOS 5750-05, Rev,0$
Title:
Technical Support Center HVAC System
==
Description:==
DOS 5750-05, revised to implement new DATR 3/4 6.2, Revision 05 requirements. The Safety evaluation for revision 05 of DATR 3/4.6.2 was vahdated for application to DOS 5750-05, Revision 06.
Resutt:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03 113 Type of Safety Evaluation:
FSAR Change Evaluation Reference Number: DFL 99-050
Title:
UFSAR Change to Delete Reference to RR Pump Discharge Bypass Valves
==
Description:==
Revise Section 7.3.1.2.2 to delete reference to the Reactor Recirculation Pump discharge valve bypass valves that were removed from both Units.
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-114 Type of Safety Evaluation:
FSAR Change Evaluation Reference Number: DFL 99-042
Title:
UFSAR Section 9.C.5
==
Description:==
The purpose of this change is to update the information in the UFSAR with the current -
analysis for the minimum Diesel Generator Cooling Water (DGCW) flow requirements.
Currently, the UFSAR Section 9.5.5 states that the minimum DGCW flow requirements are 800 gpm at 95 degrees F for the 2/3 DGCW pump and 900 gpm at 95 degrees F for the 2 and 3 DGCW pumps. Stone and Webster calculaiton 18662-M(Cl)-10, Diesel Generator Cooling Water Requirements for Temperature Alarm Point Conditions, revision 1, and Sargent and Lundy calculabon MPED-9215111-01, Calculation for Diesel Generator Cooling Water Flow Vs. Temperature, revision 0, provide consistent minimum flow requirements for all of the DGCW system based on cooling water inlet temperature.
There are no physical changes to the plant or any SSC. This change updates design documents and station procedurer with the most current analysis.
Result.
This evaluation determined that an unreviewed safety question did not exist.
l i
)
Page 12 of 14 I
10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report Safety Evaluation Number: 1999-03-116H Type of Safety Evaluation:
FSAR Change Evaluation Reference Number: DFL 99-0:i1
Title:
UFSAR Section 7.3.1.2.2. Loop Selection Logic
==
Description:==
Make editorial corrections to UFSAR Section 7.3.1.2.2 and revise Figures 7.3-5 & 7.3-6 for clarity and accuracy of description.
Validation of previous Safety Evaluation for M12-2-90-066 dated 6/30/92 Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-120 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DlS 1500-05, Rev.19
Title:
Division I & il LPCI ECCS Initiation Circuitry Logic System Functional Test Description-DIS 1500-05 was modified to allow on-line testing of smaller portions of the LPCI logic system. The procedure may also be performed during an outage if desired. The expected uninterrupted duration of the procedure is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The procedure performs Logic System functional Testing of the Division I & il Low Pressure Coolant Injection (LPCI) System ECCS initiation logic circuitry..
Result:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number' 1999-03-121 Type of Safety Evaluation:
Procedure i
Evaluation Reference Number: DIS 1500-32, Rev. O
Title:
Division I & il LPCI ECCS Loop Selection Circuitry Logic System Functional Test
==
Description:==
This procedure was created from the previous Checklists D & E of DIS 1500-05 to minimize LCO time and to allow on-line testing of smaller portions of the Low Pressure Coolant injection (LPCI) logic system. The procedure may also be performed dunng an outage if desired. The expected uninterrupted duration of the procedure is 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />. The procedure performs Loop Selection Logic System Functional Testing of the Division 1811 LPCI System ECCS toop selection logic circuitry.
Resutt:
This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-122 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DIS 1400-05, Rev. 21
Title:
Core Spray System Logic System Functional Test Desenption: Revise procedure to a'. ?w 90% of the Core Spray logic to be tested on-line and the remaining 10% of the testing to be done during an outage. The new revision of the procedure may also be performed in its entirety dunng an outage, if desired. When testing in Mode 1 (Power Operation) only one CS toop will be tested at one time, the opposite loop will always be fully operational. The expected uninterrupted duration of the procedure is 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Result:.
This evaluation determined that an unreviewed safety question did not exist.
Page 13 of 14
1 l
10 CFR 50.59 Quarter: 1999-03 Safety Evaluation Summary Report
' Safety Evaluation Number: 1999-03-126 Type of Safety Evaluation:
Procedure Evaluation Reference Number: DFP 080040, Rev 3
Title:
Recire Suction Plug
==
Description:==
The Suction Plug functions as the isolation peint for the vessel coolant inventory when the i
Recire Suction valve or any other valve that is the first isolation point from the vessel, is 1
opened. This installation is required when the Recirc suction valve or any other valve that is the first isolation point from the vessel must be opened to allow maintenance activities on these valves.
~
Result:
This evabation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-127 Type of Safety Evaluation:
FSAR Change 1
Evaluation Reference Number: DFL 99-056
Title:
UFSAR Table 3.11 1 & 3.112
==
Description:==
The proposed change to the UFSAR is the revision of Tables 3.11-1 ano 3.11-2. The temperature for EQ Zone 18 (Shutdown Cooling Pump Room) during the plant normal service condition and High Energy Line Break (HELB) will be changed from 104 degrees F to 120 degrees F. This change conservatively reflects elevated temperatures that are recorded for this roor, - he increase of the room ambient temperature might impact performance of equipment located in the room.
l Ren, ult:
Thie evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1999-03-135 Type of Safety Evaluation:FSAR Change Evaluation Reference Number
- DFL 99-057
Title:
UFSAR Section 5 -Integrity of Rx Coolant Pressure Boundary
==
Description:==
The purpose of this activity is to provide for the injection of Noble Metats into the reactor dunng shutdown cooling operation and to control reactor temperature during this process.
This activity also controls the temporary modifications to the plant associated with this evolution. It is the intend to inject noble metal compounds into the reactor vessel to prevent crack initiation and to mitigate any existing crack growth in the reactor vessel surfaces,
{
internal components and piping due to intergranular Stress Corrosion P -king This process j
is commonly called the NobleChem process or Noble Chemical Additic. process.
Result.
This evaluation iowntified the need to change the Technical Specifications Safety Evaluation Number: 1999-03-137H Type of Safety Evaluation:
Miscellaneous Evaluation Reference Number: DATR 4 3.1-a
Title:
ATWS-Recirculation Pun'p Trip / Alternate Rod Insertion
==
Description:==
Change time delay setpoint from at least 39+/-1 seconds to "at least 44.2 seconds but not to exceed 54.2 seconds".
Validation of previous Safety Evaluation 1998-04-286.
1 Result:
This evaluation determined that an unreviewed safety question did not exist.
End of Report Page 14 of 14 l
l t.