ML20199D326
| ML20199D326 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/31/1998 |
| From: | Heffley J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JMHLTR:#99-0002, JMHLTR:#99-2, NUDOCS 9901200069 | |
| Download: ML20199D326 (11) | |
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- Cornmonwcalth Fdison Company Drnden Generating station 654) North Drtsien Road Morris. 11.60150 Tel m s.942 2920 l
January 11,1999 JMHLTR: #99-0002 U. S. Nuclear Regulatory Commission ATTIt Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 1,2 and 3 Facility Operating License Nos. DPR-2, DPR-19 and DPR-25 NRC Docket Nos. 50-10. 50-237 and 50-249
Subject:
1998 Fourth Quan:er 10 CFR 50.59 Report Enclosed is the Fourth Quarter 10CFR50.59 Report of completed Changes, Tests, and Experiments for Dresden Nuclear Power Station. These evaluations examined the conditions identified in 10 CFR 50.59(a)(2) to determine whether a proposed change, test, or experiment involves an unreviewed safety question.
Should you have any questions concerning this report, please contact Mr. Frank Spangenberg, Dresden Nuclear Power Station Regulatory Assurance Manager, at (815) 942-2920, extension 3800.
Respectfully, Vice Presid t Dresden Niiclea r Station Attachment {
cc: Legional Administrator, Region III [}'
Senior Resident inspector, Dresden Nuclear Power Station r'
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.! 9901200 49 981231 PDR R ADOCK 05000010t PDR ;_
A 1inicom Company
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i Attachment i
Dresden Nuclear Power Station 10CFR50.59 Safety Evaluation Report i
for the 1998-04 Quarter ;
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l 10 CFR 50.59 Quarter: 1998-04
! _S_afety Evaluation Summary Report __
Safety Evaluation Number: 1997-03-183 . Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E121-97-200 l
Title:
Isolate Condensate and Rinsewater Storage Tanks for Demolition
Description:
This Exempt Change will mechanically and electrically isolate the T-104A. B (Condensate and l Rinse Water Storage) tanks to allow for eventual demolition. It provides the details to isolate the chemical cleaning tank farm, which consists of the Rinse Water and Condensate Tanks T-104A and T 1048, and the associated components: (1) service air piping. (2) nitrogen system piping. (3) sump and associated pumps and piping, (4) transfer pumps and piping. The lines will be cut and capped inside the Chemical Cleaning Building, which is heated, to avoid the possibility of trapped water freezing and rupturing the lines. Electricalisolation of the l associated equipment will consist of lifting leads at the breakers and/or terminal boards in the Chemical Cleaning Building.
i Result: This evaluation determined that an unreviewed safety question did not exist. l Safety Evaluation Number: 1998-01092H Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E12-2-98-212
Title:
Shutdown Coo!!ng Pumps
Description:
The Exempt Change installs a time delay relay to the low suction pressure trip circuitry of each Shutdown Cooling Pump. The time delay (7.5 +/- 2.5 see) prevents spurious trips of the l pump during pump starts, when momentary low suction pressure conditions exist.
j Validation of previous safety evaluation 1997-02-142 Result: This evaluation determined tt st an unreviewed safety question did not exist.
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l Safety Evaluation Number 1998-02-127 Type of Safisty Evaluation: Modif6 cation !
l Evaluation Reference Number E12-1-97-202 I l
Title:
Unit 1 Fuel Rechanneling Machin( Refurbishment
Description:
. Exempt Change E12-1-97-202 spec fies the refurbishment and upgrade of the existing Unit 1 l Fuel Prep Machine (FPM)/Rechanrning Machine. The FPM is utilized for dechanneling and j rechanneling the Unit i spent fuel a/nemblies. Operation of the FPM is required for '
inspecting the spent fuel assemblies 3rior to placing them in dry cask storage. Refurbishment of the FPM ensures the machine will .eliably support the spent fuel assemblies, which is essential for preventing damage to th assemblies. The FPM upgrades enhance performance and increase efficiency and they do not adversely affect the intended function ,
of the machine. I Result: This evaluation determined that ar t.nreviewed safety question did not exist.
Safety Evaluation Number 1998-02-130 Typt f Safety Evaluation: Miscellaneous Evat.ntion Reference Number: DATR 3/4.13/4.2
Title:
Revise Fire Protection DATR's i l
Description:
TI e proposed activity associated with this evaluation involves revising DATR Sections 3/4.1 l' (Fire Protection),3/4.2 (Post Fire Safe Shutdown Equipment), and DATR Bases 3/4.1. This f poposed activity does not constitute a change to any SSC. Changes made to the plant were pe rformed to the applicable procedures for design changes and as such were reviewed under s'.parate 50.59 evaluations.
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, Resuit: This evaluation determined tha' an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-04 pajetLQapa@pegary Repprt__ ___ _ _ _ _ _ _ _ _ _ _ _ _
Safety Evaluation Number: 1998-02-183 Type of Safety Evaluation: Procedure j Evaluation Reference Number: SPI 98-06-050 Title. Power increase Following Resolution of increased Steam Flow issues
Description:
The proposed activity is to increase unit power until a maximum power of 2527 MWt is reached. Dunng the power increase, performance parameters will be monitored against i criteria in the procedure. The Special Procedure restncts flow rate to less than 9 87 Mlbm/hr.
Plant efficiency has been irnproved due to a combination of changes to the Reactor Water Cleanup (RWCU) system and re-calibration of the feedwater flow nozzles. As a result, steam flow at the licensed thermal power of 2527 MWt is expected to exceed the original rated steam flow rate. New accident and transient analyses are based on a steam flow rate of 9.90 l Mlbm/hr (which corresponds to a feedwater flow rate of 9.87 Mlbm/hr during the SP), higher l than the rated steam flow rate. The reason for the procedure is to confirm that operation at a higher than rated steam flow rate does not adversely impact plant components. The steam ,
flow rate during the SP is bounded by the value of 9.90 Mlbm/hr which was used in new I accident and transient analyses.
l Result: This evaluation determined that an unreviowed safety question did not exist.
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Safety Evaluation Number: 1998-03-194 Type of Safety Evaluation: Procedure )
Evaluation Reference Number: DIS 0250-01 i
Title:
Main Steam Line High Flow Isolation Switch Calibration
Description:
Revise DIS 0250-01 to include provisions for installation of a test switch across the sensor trip relay output contacts (contacts 1-2 on 2(3)-595-102A 102B,-102C and -1020) in the trip l logic subchannel. The test switch will be in the 'ON' position (switch contact closed) while '
connecting test equipment necessary to check operation of the Main Steam Line (MSL) High Flow differential pressure (dp) switches. The test switch will remain in the 'ON' position until l just before increasing the dp for the iirst switch in each trip logic subsystem. The test switch )
will be placed in the 'OFF' position (switch contact open) and dp increased until the switch actuates causing the trip logic subsystem to de-energize. Then the switch will be returned to j the 'ON' position, re-energizing the inp logic subsystem. Any adjustments and additional checks will be performed with the test switch in the 'ON' position.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-212 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-047
Title:
Expedite Fuel Off-Load
Description:
Update Section 9.1.2 & 9.1.3 of the UFSAR to allow outage specific calculations of the spent fuel pool heat load based upon the number of fuel assemblies to be discharged, the time !
between reactor shutdown and the start of fuel offload, and the rate of fuel offload. The i
calculated heat load includes decay heat from all previously discharged spent fuel assembhes in the fuel pool The acceptance enteria for the calculations to satisfy hcensing basis requirements are provided.
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-04 Safety Evajuation Summary Report _
l- Safety Evaluation Number: 1998-03-217 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-050
Title:
Alternate Method of Decay Heat Removal l
Description:
Use systems that cool the fuel pool (fuel pool cooling [FPC) system and shutdown cookng
[SDC) fuel pool assist [FPA]) to satisfy TS 3.10.K Action Statement i requirement for an altemate method of decay heat removal for the RPV, This will be achieved by crediting heat transfer from the reactor cavity to the spent fuel pool via natural circulation through the fuel l transfer canal. Also, credit natural circulation as an alternate method of reactor coolant circulation to satisfy TS 3.10.K Action Statement 2 Result: This evaluation determined that an unreviewed safety question did not exist.
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i Safety Evaluation Number: 1998-03-230 Type of Safety Evaluation: FSAR Change Evaluation Reference Number DFL 98-046
Title:
UFSAR Section 11.4, Radioactive Waste Processing
Description:
Change the UFSAR Section 11.4 to reflect new methods of processing solid radioactive wastes. New technologies have changed the way that the station processes solid radwaste.
This change will reference the fact that Dresden now sends radioactive sludge to an off-site vendor for solidification or drying. It will also add the process of thermal destruction of spent resin beads as an afternate method of processing resin. This change will also reflect the fact 1 that DAW can be packaged un-compacted into shipping containers for further volurr's reduction processes.
Result: This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number: 1998-03-233 Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-09-051
Title:
Unit 1 Processing T-102A & B Tanks j
Description:
This Special Procedure will be used to process the Dresden Unit 1 Chemical Cleaning l
Radweste Receiving Tanks (T-102A/B) contents using a Vendor Ultra-filtration / Reverse l Osmosis /Deminerakzer (UF/RO/DEMIN) Water Processing System so that the slightly contaminated water can be transferred to Unit 2/3 Radwaste for disposal. Processing of liquid radioactive water is no longer performed on Unit 1 due to the shutdown and decommissioning of the Unit i radioactive waste processing facilities. The Tanks will be processed by recircing the Tank T-102A/B contents through a skid mounted UF/RO/DEMIN Processing system, as allowed by the Station Process Control Program, The processing will be performed by a vendor, NUKEM, utilizing Vendor Procedures and equipment. When the chemistry parameters are within discharge specifications, then the shghtly contaminated water will be transferred to Unit 2/3 Radwaste for discharge. Water in the T-102A/B will continue to be processed and then batch transferred to Unit 2/3 Radwaste until one tank is empty and the other tank water level is 25% or less of concentrated waste.
Result: This evaluation determined that an unreviewed safety question did not exist.
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9 10 CFR 50.59 Quarter: 1998-04 Safety Evaluation Summary Report _ _ _ _ _ _
Safety Evaluateon Number: 1998-03-23BH Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: D3C15 Core Oper. Limits Report
Title:
Revbion to D3C15 COLR (September 1998)
Desenption: Revision to the D3C15 COLR due to changes to the D3C15 COLR due to changes to the D3C15 reload analysis documents. The changes to the COLR include changes to the MCPR i Operating Limits and referencing and attaching excerpts from the new Plant Transient "
Analysis Report and the new Reload Analysis Report for D3C15. The analyses were re-performed to incorporate the revised ATRIUM-9B additive constants from the critical power I ratio correlation, the interim NRC approved generic ATRIUM-9B additive constant uncertainty, I reduced steam dome pressure, the updated fuel gap conductance inputs and the use of cycle exposure dependent MCPR Operating Limit values. Only the limiting events, which are analyzed on a cycle specific basis, were reanalyzed to incorporate the revisions to these inputs. -
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-241H Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-04-022, Rev, 01
Title:
Unit 1 Fuel Characteriration Plan - Phase 11 !
Description:
This Unit 1 Fuel Characterization Plan Phase 11, Special Procedure will perform a remote underwater inspection of select Unit 1 Fuel stored in the Unit 1 Fuel Storage Pool and Fuel Transfer Pool. There are 659 fuel assemblies and 1 fuel rod basket stored in the Fuel i Storage Pool and 24 fuel assemblies stored in Fuel Baskets in the Fuel Transfer Pool.
Approximately 550 of these fuel assemblies are channeled and the rest are not channeled. j Selected Unit 1 spent fuel assemblies will be removed from their storage locations and transported to a video inspection area where cameras will be set up to perform the underwater inspection. Those fuel assemblies that require dechanneling prior to inspection will be dechanneled at the Dechanneling Machine. It is planned to rechannel all assemblies that will ba dechanneled for inspection. However, if channels can not be reinstalled, the channel will be stored separately from the fuel assembly in a safe location within the Fuel Transfer Pool or Fuel Storage Pool.
The inspechon of the fuel assemblies will be performed by Siemens Power Corporation (SPC)
Vendor Personnel with station approved Siemens Procedures using underwater color cameras and a video recording system. The fuel will then be taken back to its original storage location in the Fuel Storage Pool or Fuel Transfer Pool. The Unit 1 Fuel Grapple l Crane will be used to handle the fuel in conjunction with the Unit 1 Grapple Tool.
Result: This evaluation determined that an unreviewed safety question did not exist.
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4 10 CFR 50.59 Quarter: 1998-04 j Safety Evaluation Summary Report _ _ __ _ _ _ _ _ _
Safety Evaluation Number: 1998-04-245 Type of Safety Evaluation: Procedure Evaluation Reference Number DFP 0800-41
Title:
Unit 1 Fuel Channel Fastener Bolts l
Description:
Dresden Unit 1 is undergoing a Fuel Characterization inspection process pnor to placing its spent fuelinto Dry Cask Storage, As part of this inspection process, a percentage of the fuel will be dechanneled so that the fuel inside the channeled area can be inspected. The fuel will then be rechanneled after the inspection prior to replacement in the Fuel Storage / Transfer Pool.
- One high strength capscrew may be used or two of the low strv.gth cap screws to replace the original two channel bolts. However, use of one low strength capscrew is acceptable for Fuel Pool storage if only one low strength capscrew can be installed, the assemblies will be l'
marked in the NCTL to change out the cap screw to one high strength cap screw prior to loading the assembly into the Fuel Storage Cask.
This Safety Evaluation will address the use of the new cap screws and revision to the Dechanneling Procedure for use of cap screws.
Result: This evaluation determined that an unreviewed safety question did not exist.
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' Safety Esaluation Number. 1998-04 248 R1 Type of Safety Evaluation: Nuclear Work Request Evaluation Reference Number; NWR 980086252,970077173
Title:
Unit 1 Transformer Removal i
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Description:
Dresden Unit 1 Transformer is being removed from the Station. Auxiliary components on the I transformer will be removed. The transformer, weighing approximately 300,000 lbs., will be j moved to a transport vehicle. The transformer will be moved around the eastern end of the site and out the main gate. The transformer will be checked for radioactive contamination j and decontaminated as required prior to being transported off site.
Dresden Unit i Transformer 11 was previously dismantled and removed from the station in small peces.
- Revision 1 of this Safety Evaluation addresses the attemate travel path over the East Parking Lot, and Hot and Cold Canals.
Resutt: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 199844
, Safety Evaluation _ Summary Report ___ _
i Safety Evaluation Number: 1998-04-250 Type of Safety Evaluation:
(. Procedure Evaluation Reference Number- DEP 0040-40. Rev. O
Title:
Differential Pressure (D/P) Testing of Unit 3 LPCI Motor Operated Valves l
Description:
Certain LPCI Motor-Operated Valves (MOVs) are being dynamically D/P tested per test procedure DEP 0040-40 These MOVs will be operated in the usual mannerjust as they I wc.ild under normal LPCI system operating procedures. Test procedure DEP 0040-40 operates the LPCI system in the same manner as the norma! Operating Procedures and !
- Surveillances. The only exception is that extemal(non-intrusive) test equipment will be connected to the valves for data collection. On the exterior of each MOV tested there is a permanently mounted (usually on the valve yoke) strain gauge device used to measure valve thrust.
1 This D/P testing also requires that Current (1) clamp-on probe wi!! be placed around the 480 VAC power supply wires / leads at the MOV to measure current. Vcitage,. (V) for tr.s U,JJ l being tested are obtained via contact probes at the valve's respective motor control center l (MCC). In addition to these above measurement devices, a temporary pressure transmitter ;
l and gauge will be installed to monitor both the upstream and downstream pressure for the ,
MOVs being tested. These non-intrusive measurement devices are required in order to )
l gather test data to ensure that these valves will be able to meet their intended design function (s).
l Result: This evaluation determined that an unreviewed safety queshon did not exist.
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! Safety Evaluation Number. 1998-04-251H Type of Safety Evaluation: Procedure Evaluation Reference Number: SPl 98-10-031
Title:
Hydrogen Addition Pre-Startup Test 1
Description:
' This is a Prestartup Modification Test of the Unit 3 Hydrogen / Oxygen Addition System.
Validation of Previous Safety Evaluation 1998-01-012 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-258 Type of Safety Evaluation: Nuclear Work Request Evaluation Reference Number: DCP 9800386. WR 980115010
Title:
HPCI GSLP Vent Line Desenption: Install a small vent line from the HPCI Gland Seal Leakoff Pump (GSLP) discharge back to the Gland Seal Condenser (GSC) in order to enhance air removal from the pump and associated piping. The new vent line will tap into the GSLP discharge and connect to an existing tap on the GSC. An onfice is being installed to limit flow and reduce the pressure at I the GSC connection.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-259 Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-11-034
Title:
3C Cire Water Pump Discharge Valve i
Description:
This evolution requires temporary disabling of the interlock between 3-4401-C, CW Pump and its Discharge Valve while running the pump, and then restores the normal configuration.
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-04 Sa{ety Evaluation Summary Report Safety Evaluation Number: 1998-04-261H - Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-11-035 Tale: Unit 1 Storage Pool Phase ll Fuel Characterization
Description:
This Special Procedure will move fuel assemblies between Fuel Baskets in the Fuel Transfer l Pool. This will allow the Fuel Baskets to be cleaned and inspected with the fuel removed.
The Empty Fuel Basket located in the Transfer Carrier has been previously inspected and is ready to receive fuel. This Special Procedure will allow movement of fuel, as directed by an NCTL from the North Fuel Basket to the Empty Fuel Basket. The North Fuel Basket will be cleaned and inspected per a Special Procedure written specifically for that evolution. If the North Fuel Basket is determined as acceptable to receive fuel, then the fuel fiom the South Fuel Basket will be moved to the North Basked per this Special P ocedure.
Validation of previous safety evaluation 1998-02-118 i
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-262H Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-051
Title:
UFSAR Section 6.0.8, Containment Atmosphere Control
Description:
Revise UFSAR Section 6.0.8 to improve desenption of Containment Atmosphere Control.
The reference to the ACAD system in this paragraph will be updated to clanfy the atmosphere dilution function has been permanently disabled and the equipment abandoned in place.
Validation of Previous Safety Evaluations 1997-02-081 & 1997-02-082.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-04-264H Type of Safety Evaluation: Procedure l
Evaluation Reference Number; SPl 98-11-036 !
Title:
Clean and Inspect Fuel Baskets ,
l Desenption: This Special Procedure will perform a cleaning and inspection of the remaining Fuel Baskets !
stored in the Fuel Transfer Pool. The empty Fuel Basket stored in the Fuel Transfer Carrier !
was previously cleaned and inspected by Special Procedure SPI 98-05-027, for which Safety l
Evaluation 1998-02-145 was wntten. This cleaning and inspection is consistent with the !
process established by the original procedure and Safety Evaluation.
The spent fuel will be removed from the Fuel Basket to be cleaned prior to the start of the l cleaning and inspection process to the empty Fuel Basket in the Basket Carrier by Special i Procedure SPl 98-11-035. The North Basket (ASLN) will be cleaned and inspected first and if found acceptable, then the fuel from the South Basket (SFB) will be moved to the North Basket. The South Basket will then be cleaned and inspected, if required.
Validation of Previous Safety Evaluation 1998-02-145 Result: This evaluation determined that an unreviewed sa'ety question did not exist.
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o 10 CFR 50.59 Quarter: 1998-04 Safety Evaluation Summary Report .
Safety Evaluation Number. 1998-04 266H Type of Safety Evaluation: Procedure Evaluation Reference Number. SPI 98-05-028, Rev. 2
Title:
Operation of 3A Cire Water Pump Discharge Valve MO 3-4401-A Description. This procedure provides the steps necessary to open or close the 3A CW pump discharge valve,3-4401-A while Temporary System Alteration 111-09-98 is installed during normal shutdown or trip of the 3A CW pump.
Validation of Previous Safety Evaluation 1993-02143 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number. 1998-04-267H Type of Safety Evaluation: Procedure l Evaluation Reference Number: SPI 98-10-033
Title:
Draining T102A Tank
Description:
This procedure will provide direction for the transfer of water via a gravity drain from the Unit 1 Chemical Cleaning T 102A Tank to the Unit 1 Secondary Steam Generator Collector Tanks, i T-26A/B and the Unit 1 Waste Neutralizer Tank. T 117. This will reduce the amount of water J in T-102A Tank so that the tank does not overflow prior to the initiation of T-102A/B water i processing under Unit 1 Decommissioning Project #57.
i Result: This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number 1998-04-272H Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-052
Title:
125 / 250 Vdc Station Battery System l
Description:
Change the basis for the 250V battery 4-hour capacity as described in UFSAR Paragraph 8.3.2.1.1.
Change the 250Vdc battery charger ac power source connections as described in UFSAR Paragraph 8.3.2.1.1. .
Change the basis for the 125V battery 4-hour capacity as described in UFSAR Paragraph I 8.3.2.2.
Change the Tech Spec Bases (Section 3/4.9.C.D.C. Sources - Operating) for the 125V and 250V battery 4-hour capacity as described in UFSAR Paragraph 8.3.2.2.
Validation of Previous Safety Evaluation 1997-04-236. l Result: This evaluation determined that an unreviewed safety question did not exist.
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. i l 10 CFR 50.59 Quarter: 1998-04 Sa[gttgyaluation Summary Report _ ___ __ _ _ _
Safety Evaluation Number: 199844 275H Type of Safety Evaluation: Procedure
- Evalustion Reference Number SPI 98-02-017, Rev. 5 Tde
- Completion of U1 Radwaste Cleanup
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l Desenption: This activity involves the removal, processing and packaging for disposal of residual wastes
! and spert resins currently contained within the Dresden Unit 1 Radwaste Facihty's below ground tanks, sumps, and tank vaults. This will be accomplished by pumping, slurrying, i l filtering and dewatering through disposal liners. All process liquid wastes will be stored in the <
i Radwaste Tanks until it can be transferred to Unit 2/3 for additional processing. An additional l drying step will be performed in order to concentrate the remaining waste into a smaller disposal volume. The project will be performed by a Process Vendor (NUKEM) utilizing station approved vendor procedure 3 and equipment.
Validation of Previous Safety Esaluation 1997-03-161, Rev. 02 )
Result: This evaluation determined 'aat an unreviewed safety question did not exist.
Safety Evaluation Number 1998-04-276 Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR 3/4 6.3
Title:
HRSS HVAC System I l
Descript.on: Revise DATR Section 3/4.6.3 to incorporate UFSAR requirements for maintaining the High
! Radiation Sampling System (HRSS) building at approximately 75 degrees F and the HVAC equipment required for operability, it has been determined that "approximately" has been defined as a temperature span of 70 to 80 degiees F.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number.1998-0.b278H Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-09-051, Rev.1
Title:
Process Tank 102A
Description:
This Special Procedure will be used to process the Dresden Unit 1 Chemical Cleaning Radwaste Receiving Tanks (T-102A/B) contents using a Vendor Ultra-filtration / Reverse Osmosis /Demineralizer (UF/RO/DEMIN) Water Processing System. Processing of hquid radioactive water is no longer performed on Unit i due to the shutdown and decommissioning of the Unit i radioactive waste processing facilties. When the chemistry parameters are within discharge specificatiuns, then the processed water will be transferred to Unit 2/3
- Radwaste for discharge. Water in the T-102A/B Tanks will be processed untit one tank is empty and the other tank levelis 25% or less of concentrated waste.
Validation of Previous Safety Evaluation 1998-03-233 Result- This evaluation deterrnined that an unreviewed safety question did not exist. I End of Report I
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