ML20154N413
| ML20154N413 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/30/1998 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20154M432 | List: |
| References | |
| NUDOCS 9810210279 | |
| Download: ML20154N413 (18) | |
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10 CFR 50.59 Quarter: 1998-03 Safety Evaluation Summary Report l l
Safety Evaluation Number; 1996-02-128 Type of Safety Evaluation: Miscellaneous j Evaluation Reference Number: Calc. No. 9389-04 02-SW, Sec.
Title:
Untracked Loads on the LPCI Comer Room Structural Steel l
Description:
This Safety Evaluation was originally reported in the second quarter 1996 Safety evaluation l
report to the Document Control Desk but was incorrectly classified in the quarterly report, i stating "This evaluation determined that an unreviewed safety question did not exist? The '
Safety Evaluation actually determined a USO to be present. An update of this Evaluation will be submitted to the NRC during the Third Quarter 1998 report. The onginal text of the 1996 submittal follows:
This calculation revision to Calc. No. 9389-04-D2-SW, Sec.18,19, 20, & 30 documents the attachment of previously untracked loads on the LPCI corner room structural steel. These loads include pipe support loads and heat exchanger nozzle reactions.
Result: An Unreviewed Safety Question was identified. A license amendment was submitted to the N Safety Evaluation Number: 1997 01-032 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 96-141 and TSUP 3/4.7k
Title:
DFL 96-141 and TSUP 3/4.7K
Description:
This Safety Evaluation was onginally reported in the first quarter 1997 Safety evaluation report to the Document Control Desk but was incorrectly classified in the quarterly report, stating "This evaluation determined that an unreviewed safety question did not exist? The Safety Evaluation actually determined a USO to be present. An update of this Evaluation will be submitted to the NRC during the Third Quarter 1998 report. The original text of the 1997 submittal follows:'
During the Dresden independent Safety inspection, a concern was raised that under DBA LOCA conditions with LPCI and CS pumps at above rated flow, it is possible under some circumstances to have less than required NPSH. Operability evaluation ID 9618 was initiated to evaluate this concern. Subsequently a calculation of the ECCS torus suction strainer head loss was discovered that changed the loss from 1 foot at 10,000 gpm to 5.8 feet. As a result operability evaluation 96-68 was performed. The purpose of this change is to revise UFSAR Sections 6.2.2.3.2 and 6 3.3.4.3 and clarify Tehenical Specification (TSUP)
Basis 3/4.7K regarding the impact from these concerns on NPSH for the LPCI and Core Spray pumps. These calculations of NPSH utilee the reconstituted head loss for the ECCS torus suction strainer and the torus water and CCSW water temperature administrative controls presented in pending UFSAR change DFL 96-140. This will allow operability assessments 96-18 and 96-68 to be closed.
The change to UFSAR Section 6.2.2.3.2 revised the torus suction strainer head loss.
. The change to UFSAR Section 6.3.3 4.3 documents the new NPSH calculations for short term (injection phase, no manual action) and long term (containment cooling phase, manual action ) .
Result: A License Amendment was submitted to the NRC.
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l 10 CFR 50.59 Quarter: 1998-03 SafetLEvajuation Summary Report .
Safety Evaluation Number: 1997-01 065 Type of Safety Evaluation: Nuclear Work Request l
Evaluation Reference Number: NWR 970036306
Title:
24/48V Syst. A
Description:
Place / maintain charger in equalize mode and dial down voltage to float voltage range. This is considered an
- Abnormal Lineup" per NSWP-A-04 Section 4.2.3. This work request was written to allow for utilizing the equa!izing potentiometer to control the float voltage. This action was taken to compensate for an identified problem with the float potentiometer.
Result. This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1997-03-193 Type of Safety Evaluation: FSAR Change ,
Evaluation Reference Number: DFL 97-084
Title:
UFSAR Section 13.2
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Description:
Section 13.2 of UFSAR is being rewntten to comply with 10CFR55,4 and 10CFR50.120.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1997-03-212 Type of Safety Evaluation: Modification Evaluation Reference Number: M12-2-97-004
Title:
MSLRM Scram & Isolation Function Removal
Description:
Remove the Main Steam Line Radiation Monitor high scram and the Main Steam Line Tunnel Radiation high input to the Main Steam Line Isolation function.
Result: A new Technical Specification, revision, or other License Amendment is required.
Safety Evaluation Number. 1997-04-227 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 97-099
Title:
Revision of UFSAR Section 9.5.9
Description:
A Note at the beginning et Section 9.5.9 was added prior to the bi-annual update (revision 2) of the Dresden UFSAR to reflect the fact that the Unit 3 Station Blackout system was not yet i operationally authorized and was planned to be authonzed during the D3R14 refueling outage. The Unit 3 system has since been tested and operationally authorized in method similar to Unit 2. Therefore, the note is being removed and a clarification of Section 9.5.9 2 is being made to state that the Unit 3 generator was tested similarly to Unit 2. Furthermore, there is a reference in Section 9.5.9.2 to the Station Blackout generators being operated per procedure DGA-12 and the Dresden Emergency Operating Procedures (DEOPs). The actual Dresden Emegency Operating Procedures do not mention the operation of the Station Blackout generators.
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03 Safety Evaluation Summary Report Safety Evaluation Number: 1998-01-009 Type of Safety Evaluation: Exempt Change Evaluation Reference Numbec E12-2-98-201
Title:
. . Offgas inspection Port
Description:
A four inch inspection port will be welded into the 16 inch Off Gas pipe 2-5461 B-16", This inspection port will allow inspection and cleaning of the Off Gas piping Cleaning will
,- minimize the Off Gas system Preheater high temperature concern.
Result: This evaluation determined that an unreviewed safety question did not exist.
j Safety Evaluation Number: 1998-01-016H Type of Safety Evaluation: Miscellaneous j Evaluation Reference Numbet DATR Table 3/4.18.2 ,
Title:
Primary Containment isolation Valves )
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Description:
Incorporate the reconfiguration of the primary containment isolation valves into DATR table 3/4.18.2. These valves were installed under exempt changes E12-3-95-241 and E12-3 240.
Validation of previous Safety Evaluation for E12-3-95-240, dated 10/11/95 Result: . This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-01-01' r1 Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
Primary Containment isolation Valves
Description:
Incorporate the reconfiguration of the primary containment isolation valves into DATR table 3/4.18.2. These valves were lnstalled under Exempt change E12-3-95-239.
Validation of previous Safety Evaluation for E12-3-95-239, dated 10/6/95 :
Result: This evaluation determined that an unreviewed safety question did not exist. ]
Safety Evaluation Number: 1998-01-018H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
Primary Containment isolation Valves
Description:
incorporate the reconfiguration of the primary containment isolation valves into DATR tabit 3/4.18.2. These valves were installed under Exempt change E12-3-95-238.
Validation of previous Safety Evaltation for E12 3-95-238, dated 10/12/95 Result: This evaluation determined that an unreviewed safety question did not exist.
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- 10 CFR 50.59 Quarter: 1998-03 Safety----..--..Summar.y Evaluation .- . _ - .- Report Safety Evaluatton Number
- 1998-01-019H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2 i Titie: Primary Containment isolation Valves *
Description:
incorporate the reconfigurationof the rimary containment isolation valves into DATR table 3/4.18.2. These valves were installed under Exempt Change E12 3-95 247, Validation of previous Safety Evaluation for E12-3-95-247, dated 11/13/95 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 199841-020H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
LPCI System Update
Description:
Incorporate the reconfiguration of the primary containment isolation valves into DATR table 3/4.18.2. These valves were installed under Exempt change E12-3-95-241 Validation of previous safety evaluation for E12 3-95-241, dated 10/11/95 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-01-021H . Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
LPCI System Update Desenption: Incorporate the reconfiguration of the primary containment isolation valves into DATR table 3/4.18.2. These valves were installed under Exempt Change E12 3-95-242 Validation of prcc ms safety evaluation for E12-3-95-242, dated 10/11/95 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1S 01022H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
. LPCI System Update r
Description:
Revise DATR to incorporate the reconfiguration of the primary containment isolation valves nto DATR table 3/4.18.2. These valves were installed under Exempt Change E12 3-95-231 Validation of previous Safety Evaluation 1997-03-191 l
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- Result:- This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03
. Safety Evaluation Summary Report Safety Evaluation Number; 199841-023H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR Table 3/4.18.2
Title:
LPCI System Update
Description:
Revise DATR to incorporate the reconfiguration of the primary containment isolation valves into DATR table 3/4.18.2c These valves were installed under Exempt Change E12-2-95-230.
Validation of previous Safety Evaluation 1997-03-190 Result; This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-01-024H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number DATR Table 3/4.18.1
Title:
Pnmary Containment isolation Valves
Description:
Exempt Change E12-2-96-218 requires revision of DATR Table 3/4.18.1 to incorporate the reconfiguration of the primary containment isolation valves.
Result. This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number: 1998-01-046 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-002
Title:
UFSAR Sect. 3.8,4.1.3 and 3.8.4.1.4
Description:
Section 3.8.4.1.3 of the UFSAR is being corrected to reflect the Design Basis for the Reactor Building superstructure. Note "3" stating "The Reactor Building superstructure was analyzed for seismic loads with no crane lifted load and crane lifted load with no seismic loads" and note "4" stating "The Reactor Building superstructure was analyzed for seismic loads with no crane lifted load" are added to Table 3.8-11.
The UFSAR section 3.7.2.2 (onginal FSAR Section 12.1) includes the mathematical models for the seismic analysis and shows that the Reactor Building was analyzed for the seismic events with no crane lifted load. Therefore, the additional information added to Table 3.8-11 is a clanfication of the UFSAR.
Result: This evaluation determined that an unreviewed safety question did not exist. ,
i Safety Evaluation Number: 1998-01-058H Type of Safety Evaluation: Technical Specification Change i
Evaluation Reference Number: Tech Spec Bases ~3/4 9. A ,
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Title:
Clarification for Unit Auxiliary Transformers i J
Description:
Change wording in Technical Specification Basis 3/4.9.A to reflect the fact that the Unit Auxiliary Transformers (TR21 and TR31) are additional sources of offsite power when being back fed from the grid. This is NOT a change to the Technical Specifications but rather a clarification in the basis.
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' Validation of previous Safety Evaluation 1996-04-284 l l
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03 Safety Eyajustion_ Summary Report _.__ _ _
Safety Evaluation Number: 1998-01-085 Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E12-2-98-208, E12-3-98-207
Title:
HPCI Gland Seal Condenser
Description:
(1) installation of an isolation valve and cap with associated piping on the Unit 2(3) HPCI Gland Seal Condenser.
(2) Change the Unit 2 HPCI Cooling Water Pump Vent Valve from a gate valve to a globe valve and install a cap on the end of the piping.
(3) Install a globe valve and cap with associated piping to the Unit 3 HPCl Auxiliary Cooling Water Pump Vent connection.
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This change is being installed to allow a hose to be connected between the Gland Seal
- Condenser and the Aux Cooling Pump during performance of a proceduralized process to venfy the operation of the Condenser Hotwell level switch. This change also a!!ows this process to be performed without having to isolate either the Gland Seal Condenser or the Cooling Water Pump. After the change is installed, the time spent in a radiation field during the performance of the test will be reduced and correspondingly, dose will be reduced.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number; 1998-01-091H Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E12-2-98-210
Title:
Lube Oil Reservoir for 2A Reactor Recirc Pump Motor
Description:
During D2R15, remove the 1/2" fill line from the lower lube oil reservoir for 2A Reactor Recire Pump Motor and plug it with 1/2" plug. On existing 3/4" fill line remove the plugged tee and
- 90 degree elbow and install 3/4" gate valve, reuse 90 degree elbow, and adjust the height of j the existing level switch by adding a nipple in the line. -
Validation of previous Safety Evaluation 1996-04-300 Result: This evaluation determined that an unreviewed safety question did not exist
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' Safety Evaluation Numbec 1998-02-118 Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-04-022 !
Title:
Unit 1 Fuel Charactenzation Phase ll Unit 1 Fuel Pool
Description:
This Unit 1 Fuel Characterization Plan - Phase 11, Special Procedure will perform a remote underwater inspection of all 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 Storage Pool and 24 fuel assemblies stored in Fuel Baskets :n the Fuel Transfer Pool. l Approximately 550 of these fuel assemblies are channeled aid the rest are not channeled.
Each Unit i spent fuel assembly will be removed from its sto< age location 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 assemt lies that will be 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.
Result: This evaluation determined that an unreviewed safety question did not exist.
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. t 10 CFR 50.59 Quarter: 1998-03 Safety Evaluation _ Summary Report __._____ _ _ _ _._
Safety Evaluation Number- 199842 120 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-039
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Title:
Core Spray Cracks
Description:
A description is added to the UFSAR that states that flaws were identified on the core spray piping components and that these components w;ll have a limited remaining operating life due ;
to anticipated growth of the flaws which will eventually either not meet allowable design ;
stresses or leak excessively and impact the ability of the Core Spray system (CS) to adequately cool the fuel after the design basis LOCA. Standard flaw evaluatx)ns to determine the remaining life of these components were completed and conclude that these components will perform their design functions over the next two fuel cycles or for forty-eight rnonths of hot ,
operation.
The flaw evaluation addressed the causes for the CS piping and thermal sleeve conditions; materials; operational seismic loading (including sensitivity); flaw water leakage, pipe stresses; a conservative determinatx)n of flaw growth rate; flaw growth limits; and loose parts. The affected CS piping elbows and collars will be re-examined after two cycles, during refueling outage D2R17.
Result: This evaluation determined that an unreview ', safety question did not exist.
a ety Evaluation Number 998-02 121 Type of Saf Eva ation FSAR Change Evaluation Reference Number DFL 98-040
Title:
Recirc Riser Cracks
Description:
as identified on the Jet Pump During pair 15 andthe D2R15 16 Recirc riserin-vessel inlet elbow atVisual inspection 4pw w(weld designation RS-1) using an the thermaTsleeve c.1hanced visual method with accepted BWR Vessel & Intemals Project criteria The flaw was evaluated per ASME B&PV Sections til and XI evaluation methods. The evaluation l results were then applied to the LOCA analysis applicable for Siemens Power evaluation.
' Results were then applied to the LOCA analysis applicable for Siemens Power Corporation (SPC) fuel which evaluated the impact of the effect of the flaw on limiting break size, MAPLHGR, PCT, and long-term cooling.
The UFSAR will be revised to indicate: (1) the condition of this piping (2) that the service life is limited and, (3) that continued monitoring per BWRVIP recomrnendations will be performed.
Result: This evaluation determined that an unreviewed safety question did not exist.
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- l 10 CFR 50.59 Quarter: 1998-03 Sapty Evaluation _ Summary Report _
. Safety Evaluation Number: 1998-02125H Type of Safety Evaluation: Set Point Changes Evaluation Reference Number SPC 002 98-085
Title:
Setpoint Change for Feedwater Temperature Transmitter Scaling
Description:
Feedwater D Heater Outlet Header Temperature Transmoters TT 2-0260-10C and TT-2-0260-12C which feed Computer points A2696, F280 and A2695, F279 respectively are currently calibrated at 280-430 Deg F as installed per Modification E12-2 98-205 during 02R15. This range spans the normal operating Feedwater temperature The Power Plex computer ,
program utilizes the Feedwater temperature from the process computer points F279 and F280. Without the lower feedwater temperature range (110-280 deg F), the input value in the Power Plex program must be entered manually. A new calibration range of 110-410 Deg F has been requested by the Nuclear Engineer and will be established to allow computer point !
readings over the entire Feedwater Temperature range. The new calibration range is analyzed in calculation NED-I-EIC-0301 and accuracy of the temperature loop is not changed. Transmitters will be recalibrated with the new values. Computer points will be modified to reflect revised transmitter range. No hardware changes or drawing changes are #
required for this Setpoint Change. !
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02-129 Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E12-3-98-211
Title:
Off Gas System
Description:
Dresden Unit 3 Off Gas System has two redundant trains of Steam Jet Air Ejectors (SJAE) and Recombiners. These trains are crosstied by a 6" pipe line,3-5465-6"-DX. The crosstie did not have an isolation valve. The proposed modification will cut and cap this crosstie line so that the two trains will be completely independent of each other. The train 3B will retain the recombiner bypass line. i Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02 131 Type of Safety Evaluation: Exempt Change Evaluation Reference Number E12-0-98-203,-204,2-98-206,3-
Title:
Safe Shutdown Lights
Description:
The subject plant modifications (E12-0-98-203, E12-0-98-204, E12 2-96-206, E12-3-98-209) are identical in scope and will install safe shutdown lighting units in areas containing +
equipment required to achieve and maintain safe shutdown. These battery powered
. emergency lights are the same type of lights currently installed at Dresden Station to provide e emergency lighting requirements. These units are capable of supplying power to three 21 watt light heads for a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. These units have 120 VAC input, therefore transformers are used to step down voltage from 227 VAC to 120 VAC. These units are UL listed and meet or exceed NEC and OSHA illumination standards.
- These modifications are classified as regulatory-r. slated. The circuits which win power these err,ergency lighting units will be fed from regular (non-essential) lighting cabinets. The battery pack. remote lights, and associated wiring and conduit are regulatory-related and the power feed to the battery pack, transformer and associated conduit and winng is non-safety related seismic. These emergency lighting units will be seismically mounted to walls or steel support .
beams. Mounting in this manner ensures the emergency lighting units will not shake loose and damage this or other equipment during a seismic event.
Result: This evaluation determined that an unreviewad safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03 SaQEvaluation Summary Report __ _ _ _ _ _ _ _ _
Safety Evaluation Number: 1998-02-136 Type of Safety Evaluation: Temporay Alteration Evaluation Reference Number: Temp Alt 111-06-98 0
Title:
RPS Monitoring All Channels
Description:
Double-lug a fused lead from the high and low side posts of each RPS scram parameter input contact and connect each lead to optically isolated ASTROMED recorder input for each independent RPS logic channel while ensunng RPS channel electncal separation is ,
, maintained. The connections to the RPS system will effectively add a 1 M-ohm resistor across each scram parameter input contact so that when that contact opens, the ASTROMED '
recorder will sense a change in the contact's voltage potential. The high value of the resistor will ensure that the RPS system has no significant change in system power, voltage, or .
current parameters. The 31.25 ma fuses ensure that the monitoring leads will be !
disconnected from the circuit if the 1 M-ohm resistor is degraded. DAP 03-20, Restraint of Portable Equipment, restrains the recorders for seismic concems.
Result. This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number- 1998-02-144 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-022
Title:
UFSAR Package for Post LOCA Rx Bldg. Temps
Description:
Revise UFSAR Section 3.11 tables to reflect the recently developed analysis of post-LOCA ,
temperatures in the affected areas of the Reactor Building. Also, revise these tables as necessary to reflect the latest approved set of EQ parameters as presented in Calculation DRE98-0091.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02 145 Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-05-027
Title:
Special Procedure To inspect & Clean U1 Fuel Basket
Description:
The proposed activity is to perform an inspection of an empty fuel basket that is currently located in the Fuel Basket Carrier in the Unit 1 Fuel Transfer Tunnel. This activity will be performed per Special Procedure 98-05-027. In general, the following steps will be performed for the proposed activity:
- 1. Transfer the Fuel Basket Carrier, (with the empty Fuel Basket located inside). by using the '
cart drive assembly, into the Fuel Transfer Pool where it can be accessed by the Fuel '
Building Overhead Crane.
- 2. Using the Overhead Crane Aux. hook, the empty Fuel Basket will be lifted out of the carrier and moved to the open area in the West side of the Fuel Transfer Pool to perform an inspection of the Fuel Basket structure.
- 3. The basket will then be cleaned using the existing fuel cleaning equipment that has previously been used to clean the other fuel baskets and fuel.
- 4. The Unit i dummy fuel assembly will be used to clearance check all 16 fuel assembly locations.
- 5. When the inspection, cleaning and clearance testing are completed, the empty basket will be lifted and moved to an empty basket support in the Fuel Transfer Pool or placed back into ths Fuel Buket Carrier, as required.
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03 Sahtyfyaluation Summary Report . _ _ . .. _ _ _ _ _ _ _ _ _ ___
Safety Evaluation Number: 1998-02-148 Type of Safety Evaluation: Procedure Esaluation Reference Number: SPl 98-05-026
Title:
. Main Power Transformer (MPT) 3 & Unit Aux Transformer (UAT) 31
Description:
1 he subject special procedure will be a post modification test of Main Power Transformer (MPT) 3 and Unit Auxiliary Transformer (UAT) 31 protective relaying due to the replacement of the transformers per modification M12-3-97-008 to ensure that the existing and modified relay protection systems are capable of performing as designed wthout spurious operation.
The protective relays provide a fault detection and protection scheme for the MPT and the UAT.
The testing will be performed in the AEER at Panels 903-29 and 903-60 and in the switchyard. The testing will be performed with the MPT supplying sufficient load to the grid and the UAT supplying sufficient load to the 4kV SWGR in order to adequately excite the cts '
feeding the applicable portions of the protective relaying.
Result. This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02 153 Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-05-0 t
Title:
HPCI Steamline Drain Valve to Torus, HPCI Turbine Exhaust Drain Pot
Description:
This is a special test procedure which will change the configuration of the 2301-28 valve dunng HPCI standby from a normally closed - fail open valve to a normally open valve which would still fail open. The test configuration will exist for a two week test period. The valve would be controlled in this position from the control room and could be readily returned to its pretest configuration.
- Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02-159 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: Decommission Program Plan Up
Title:
Biennial Update of Unit 1 Decommissioning Plan / DSAR
Description:
The 244nonth update of the Decommissioning Program Plan is being performed Format and content changes are being made to the Decommissioning Program Plan The changes l include relocation of information from the Decommissioning Prograre Plan to the DSAR, '
addition of technicalinformation, revision of technicalinformation, and deletion of extraneous or redundant information currently contained in the Decommissioning Program Plan.
Result. . This evaluation determined that an unreviewed safety question did not exist.
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d 10 CFR 50.59 Quarter: 1998-03 ;
} . Safetyfpyayon Summary Report. . _ _ . _ _ _____ .
Safety Evaluation Number: 1998-02-165 Type of Safety Evaluation: Miscellaneous
.J Evaluation Reference Number: Amendment 11
Title:
Fire Protection Report Update
Description:
Amendment 11 of the Fire Protection Report (FPR) and the Fire Protection Program ,
Documentation Package (FPPDP) incorporates the following:
- 1. Operations Authorized Plant Design Changes (DCPs) and Record Drawing Changes J (DCRs) between September 1,1994 and July 1,19%.
l 2. Design inputs and editorial changes that onginated after the 1994 FPR update (Amendment 10).
- 3. Combustible loading changes per NTS Item 237-315-96-1510101," Issue Revised FPR to
- i. Resolve Combustible Loading Discrepancies".
- 4. Char:ges to the Fire Hazards Analysis per NTS item 249-20b98-2601," Revise Fire Hazards Analysis to Resolve Editorial Discrepancy".
- 5. Changes to the Safe Shutdown Analysis per NTS Item 237-201-97-80701, " Revise Safe Shutdown Analysis to Resolve Editorial Discrepancy", '
Result: This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number: 1998-02-166 Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: DATR 3/4.16, Rev.1
Title:
Add Drywell Pressure indicators
Description:
This revision to DATR 3/416 adds drywell pressure indicators 2(3)-2540-09A & D to the Drywell and Torus Pressure parameters. Indicators Pt 2(3)-1640-4(5) are being removed ;
from the DATR. Indicators 2(3)-640-25A and 25B are being removed from the DATR as j indication available for Reactor Pressure ;
1 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02-170H Type of Safety Evaluation: FSAR Change I
Evaluation Reference Number: UFSAR Section 6.4 1
Title:
UFSAR Section 6.4, incorporate Auto Action per M12-0-96-001 Desenption: Revise UFSAR Sections 6.4.2 and 6.4.4.3 to incorporate the automatic actuation of the control room HVAC train "A" smoke purge mode and racirculation mode restored per Modification M12-0-96-001. This Modification corrected discrepancies in the control room HVAC train "A" air circulation control logic.
Validation of previous safety evaluation 1996-03-168 for M12-0-96-001
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Result: This evaluation determined that a .inreviewed safety question did not exist.
Safety Evaluation Number: 1998-02-171 Type of Safety Evaluation: Procedure Evaluation Reference Number: DOA 0010-01, DOS 0010-01
Title:
Stop Logs at Cribhouse
Description:
Revise DOA 0010-01 to increase the water level required in the suction bay for the CCSW and Unit 2/3 fire pump (Bay 13) to 505' following a Dresden dam failure. Also. revise DOS 0010-01 to require a water level in Bay 13 to 505' during surveillance testing.
Resutt: This evaluation determined that an unreviewed safety question did not exist.
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q 10 CFR 50,59 Quarter: 1998-03 pafetgvaluation. Summary _ Report _ _ _ . _ _ _ . _ . _ _ _ _ _
Safety Evaluation Number: 1998-02175H Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-02 017, rev. 3
Title:
Completion of Radwaste Clean-Up Project, Rev. 3
Description:
This activity involves the removal, processing and packaging for disposal of residual wastes and sperd resins currently contained within the Dresden Unit 1 Radwaste Facility's below ground tanks, sumps, and tank vaults. This will be accomplished by pumping, slurrying, filtering and dewatering through disposal liners. All process liquid wastes will be stored in the Radwaste Tanks untilit can be transferred to Unit 2/3 for additional processing. An additional drying step may be performed in order to concentrate the remaining waste into a smaller disposal volume. The project will be performed by a processor vendor (NUKEM) utilizing Station approved vendor procedures and equipment.
Validation of previous safety evaluation 1997 03-161 Rev.-02 Result: This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number, 1998-02-176 Type of Safety Evaluation: Procedure 1
Evaluation Reference Number: DAP 21 10
Title:
UFSAR 3.11 Change Revision Desenption: Revise DAP 21 10 Component Classification Control and Maintenance of the Master Equipment List (MEL) and Component Classification Binders (CCBS), to improve Component classification process which addresses all"inprocessa and clean-up activities.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number 1998-02 177 Type of Safety Evaluation: Procedure Evaluation Reference Number: DIS 05004)6
Title:
Condenser Low Vacuum Pressure Switches
Description:
' Revise DIS 0500-06 to include provisions for jumpenng the HFA Relay TRIP SYSTEM contacts with an indicating jumper (RPS test box) during performance of this procedure which will prevent th6 initiation of a 1/2 scram condition. The RPS test box provides a current path 1 around the trip device contacts being tested which includes a lamp that indicates when the contacts open and close.
Result: This evaluation determined that an unreviewed safety question did not axist.
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'10 CFR 50.59 Quarter: 1998-03 i SafettEvaluation Summary Report _ ___ _ _
Safety Evaluation Number: 19984 2-178 Type of Safety Evaluation: Procedure Evaluation Reference Number DlS 0500-08, DOS 0500-09
Title:
EHC Low Oil Pressure / Turbine Control Valve Fast Closure Scram Switches
Description:
Revise DIS 0500-08 and DOS 0500-09 to include provisions for jumpering the HFA Relay Trip System contacts with an int!;ating jumper (RPS test box) during performance of these procedures which will prevent the initiation of a 1/2 scram condition. The RPS test box provides a current path around the trip device contacts being tested which includes a lamp that indicates when the contacts open and close.
The trip signal for EHC Low Oil Pressure and Turbine Control Valve Fast Closure combine in i the field providing a common trip signal to the RPS Scram Logic Subchannel Therefore, I during performance of either DIS 0500-08 or DOS 0500--09, two sensors (EHC Low Oil Pressure and Turbine Control Valve Fast Closure) will be bypassed.
In addition, DOS 0500-09 added HFA relay configuration diagrams to aid in the performance .
of this surveillance.
Result: This evaluation determined that an unreviewed safety question did not exist. I
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Safety Evaluation Number: 1998-02-182 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: Section 6.2.4.3.2
Title:
Primary Containment Seals
Description:
Revise UFSAR Section 6.2.4.3 2 to rtrflect as installed condition for Pnmary containment seals for manways in supression chamber, drywell equipment access hatch, CRD equipment l hatch, shear lug inspection ports, drywell head, drywell personnel access airlocks. Change name of containment penetration seal material from a manufacturer's name "Nordel" to more general" elastomer".
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-02185H Type of Safety Evaluation: Miscellaneous Evaluation Reference Number: D3C15 COLR
Title:
03C15n COLR to Support Operation with increased Steam Flow Desenption: The D3C15 COLR is being revised due to changes to the D3C15 reload licensing documents. The changes to the COLR include referencing and attaching the new Plant i fransient Analysis and the new Reload Analysis for D3C15 in the refe-rences section and adding a clanfying footnote to the MCPR Operating Limit section. No thermal limits are being revised in the COLR, therefore, all changes are editorial in nature. The analysis was modified to utilize bounding parameters for steam flow, feedwater flow, and feedwater temperature.
The values were based on variations in plant configurations which could give higher than 1- nominal parameters.
Validation of previous safety evaluation NFM BSS.98-069 Result; This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03
' Safety Evaluation Summary Report Safety Evaluation Number: 1998-03-187H .. Type of Safety Evaluation: ~ Procedure Evaluation Reference Number: DOP $65013
Title:
~ EHC System isolation for Maintenance at Power i
Description:
Create a new Operating Procedure for EHC System isolation to allow for maintenance at power. l Validation of previous safety evaluation 1997-04-228.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-192 Type of Safety Evaluation: Procedure Evaluation Reference Number: DIS 0250-01
Title:
Main Steam Line Heh Flow isolation Switch Calibration
Description:
Revise DlS 0250-01 to include provisions for jumpering the sensor tnp relay (HFA Relay, 595- i 102) output contacts in the trip logic subchannel for three of the four channel functional /
calibration tests in each MSL High Flow Group l Isolation channel. Jumpering the Trip logic subchannelinput contacts dJring performance of this procedure would prevent the initiation of a 1/2 Group i isolation from the MSL HiCh Flow trip channel under test.
Result: This evaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number 1998-03-193 Type of Safety Evaluation: Procedure Evaluation Reference Nurnber: DIS 0250-02
Title:
Main Steam Line Low Pressure isolation Switch Calibration
Description:
Revise DIS 0250-02 to remove the steps necessary to perform the calibration and functional tests with the reactor mode switch not in 'RUN'. These steps will be incorporated into a separate procedure.
Result: This evaluation determined that an unreviewed safety question did not exist.
' Safety Evaluation Number: 1998-03-195 Type of Safety Evaluation: Technical Specification Change Evaluation Reference Number:- T.S. 3/4.10.A
Title:
. . Tech Spec Bases 3/4.10.A Change -
Desenption: The proposed activity is a change to an administrative action desenbed in the SAR. i Technical Specification Bases 3/4.10 A is being revised to remove the discussion regarding GSEP action in relation to the Fuel Storage Pool Water level. GSEP action is currently initiated at the Technical Specification Water level limit of 18' Accordingly, the d:scussion of the GSEP action level is no longer germane to the Technical Specification Bases and is being removed.
' Result: This evaluation determined that an unroviewed SOf ety question did not exist.
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1 10 CFR 50.59 Quarter: 1998-03 ;
S_afety Eyaluation Summary Report _ _ _ _ _ _ _ _ .
l Safety Evaluation Number:- 1998-03-196 Type of Safety Evaluation: Exempt Change Evaluation Reference Number E12-0-96-209
Title:
Replacement of Gasoline Tank with Above Ground Storage Unit
Description:
The proposed activity is to install a 550 gallon, above ground gasoline storage tank to be located west of the CM Warehouse. Eco Vault Company manufactures this tank. The intemal steel cylindrical vessel is 3/16" thick, 49-1/2" in diameter, 66-1/2" long, and is enclosed in a 6" thick precast concrete vault. The tank will be anchored on a 10" thick,11 1/2' x 14-1/2' reinforced concrete pad surrounded by concrete filled guard posts. The tank will be used for maintaining gasoline for refueling vehicles that service the site Result: This evaluation determined that an unreviewed safety question did not exist.
j Safety Evaluation Number; 1998-03-198H Type of Safety Evaluation: Procedure Evaluation Reference Number: SPI 98-05-027
Title:
Unit 1 Empty Fuel Basket inspection
Description:
The purpose of this Unit 1 Special Procedure is to perform a cleaning and inspection of the j empty fuel basket located in the basket carrier in the Fuel Transfer Pool Fuel Carrier. l Validation of previous safety evaluation 1998-02-145 Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number; 1998-03-200H Type of Safety Evaluation: Procedure I Evaluation Reference Number: SPl 98-02-017, Rev,4
Title:
Unit i Radwaste Cleanup
Description:
This activity involves the removal, processing and packaging for disposal of residual wastei and spent resins currently contained within the Dresden Unit 1 Radwaste Facility's below ground tanks, sumps, and tank vaults. This will be accomplished by pumping, slurrying, filtering and dewatering through disposal liners. All process liquid wastes will be stored in the
. Radwate Tanks until it can be transferred to Unit 2/3 for additional processing. An additional drying step may be performed in order to concentrate the remaining waste into a smaller disposal volume. The project will be performed by a Processor Vendor (NUKEM) utilizing .
Station approved Vendor Procedures and equipment.
Validation of previous safety evaluation 1997-03-161, Rev. 02 Result: This evaluation determined that an unreviewed safety question did not exist.
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- 10 CFR 50.59 Quarter: 1998-03 I Sa@tyyyaluation_ Summary Report _ _ _
Safety Evaluation Number: - 1998-03-202 Type of Safety Evaluation: Procedure Evaluation Reference Number Siemens Procedure EMF-2061
Title:
- U3 Failed Fuel Assembly inspection
Description:
This fuel inspection plan will perform a remote underwater inspection of fuel assembly "A3W-034"(9x9-2 fuel design), which failed after one cycle of operation, stored in the Unit 3 Spent Fuel Pool. The spent fuel assembly will be transported to the Fuel Preparation Machine, de-channeled, upper tie plate removed, individual rods removed in order to view the failed fuel rod H42 using video inspection cameras. This inspection will be performed by Siemens Power Corporation personnel with station approved Siemens Procedures for bundle disassembly and underwater video equipment. The fuel assembly will then be reassembled and taken back to its original storage location in the Spent Fuel Storage racks. i The Unit 2(3) Fuel Handling Equipment will be used to transport the fuel. Siemens Power Corporation tools will be utilized to remove various fuel components.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-205' Type of Safety Evaluation: Miscellaneous Evaluation Reference Number. 0ATR 3/4.19
Title:
Relocate Certain Provisions of the Tech Specs to Administrative Control
Description:
Tech Spec Amendment 146/140 removed the Condensate Pump Room Flood protection requirements (3/4.5.M), the Lock and Dam surveillance (4.5 F.1) and LPCI corner room door control (3/4.5.A,7) from Tech Specs and allows licensee control via the provisions of 10 CFR 50.59. DATR 3/4.19 represents the desired control mechanism.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-214 Type of Safety Evaluation: Nuclear Work Request Evaluation Reference Number: WR 980080919-02
Title:
Moisture Separator Contingency Plan
Description:
This evaluation supports a controlled temporary lift of the lead which connects the 2(3)-3541-54A,B.C,&D ' Moisture Separator Hi-Hi Lever Trip Contacts to (GE # KID 33)' Moisture Separator Hi-Hi Lever Trip 10 Second Time Delay Relay. This will prevent a turbine trip from
. automatically occurring during trouble shooting to investigate a problem with the D Moisture Separator Hi-Hi Level switch. During the short term related to the trouble shooting, the automatic turbine safety function will be replaced with a dedicated operator.
Result: This evaluation determined that an unreviewed safety question did not exist.
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- 10 CFR 50.59 Quarter: 1998-03
_ Safety Evaluation _ Summary Report __
' Safety Evaluation Number: 1998-03-219 Type of Safety Evaluation: Procedure Evaluation Reference Numbet DIS 0500-05 & 0500-10 Title.- Scram Discharge Volume Level Sensor Calibration & Functional Tests
Description:
Revise DIS 0500-05 and DlS 0500-10 to include provisions for jumpering the HFA Relay Trip a
System contacts with an indicating jumper (RPS test box) during performance of these procedures. This will prevent the initiation of a half scram condition in the channel under test. The RPS test box provides a current path around the trip relay contacts in the RPS logic subchannel being tested, and includes a lamp that indicates when the contacts open and close.
The Scram Discharge Volume channel consists of three inputs from two sensors that are combined to actuate a trip relay The trip relay output is combined with other signals in a RPS trip logic subchannel inttallation of this RPS test box prevents a half scram from occumng due to a trip signal from the channel under test. End of channelis venfied by a e combination of visualinspection of relay contact position and the indicating light on the RPS test box.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-220 Type of Safety Evaluation: FSAR Change Evaluation Reference Numbet DFL 98-038
Title:
Electrical Penetration Assembly
Description:
Revise Table 3.8-3, Electrical Penetration Environmental Design Conditions, to call it historical data, and add a footnote to direct a reader to Tables 3.11 1,3.11-2, and 3.113.
Reference to Table 3.8-3 in Section 3.8.2.1 will be changed to referenceTables 3.11 1,3.11-2, and 3.11-3.
Result: This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-227H Type of Safety Evaluation: Procedure Evaluation Reference Number: DES 4153-02, &-04 DATR 3/4.2
Title:
DATR & Procedure Changes
Description:
The proposed DATR (3/4.2) and procedure revisions ( DES 4153 02, and DES 4153-04) are required due to Modifications E12-0-98-203, E12-0-98-204, E12-2-98-206 and E12-3-98-209 which installed additional safe shutdown hghting in accordance with the requirements of 10 CFR 50 Appendix R. In order to adequately control the subject safe shutdown lighting and required surveillance activity, the proposed revisions will incorporate the applicable lights.
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. Vandation of previous Safety Evaluation 1998-02-131.
Result: This evaluation determined that an unreviewed safefy question did not exist.
Safety Evaluation Number' 1998-03-228 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-042 Titte: 10 CFR 20.2108 Records of Waste Disposal
Description:
Change record retention for Radioactive Material shipments in UFSAR Table 13.7-1 from 5 years to Life of Plant as detailed in 10 CFR 20.2108.
Result: This evaluation determined that an unreviewed safety question did not exist.
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10 CFR 50.59 Quarter: 1998-03 Safety Eva[uation Summary Report Safety Evaluation Number: 1998-03-231 Type of Safety Evaluation: Procedure Evaluation Reference Number: DDP 05 Rev. 2
Title:
Control of Decommissioned Plant Equipment for Unit 1
Description:
Procedure DDP 05 is being revised to facilitate future Structures, Systems and Components (SSC) changes for Dresden Unit 1 commensurate with the importance of the SSC. The procedure defines a new term Required Equipment Status (RES), and provides a methodology for evaluating SSCS to determine the appropriate RES designation. RES designations define the necessary level of operability or functionality for an SSC. T he RES designations are Controlled, Functional, and Not Required. Controlled SSCs are required to remain fully operational and are important to the safe storage and handling of irradiated fuel, satisfy license requirements or support Unit 2/3 power generation. Functional SSCs remain operational to support general site requirements. Not Required SSCs are no longer required to fulfill or support any operating functions.
Result: This ovaluation determined that an unreviewed safety question did not exist.
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Safety Evaluation Number: 1998-03-235 Type of Safety Evaluation: FSAR Change Evaluation Reference Number: DFL 98-044
Title:
UFSAR Section 9 5.2.2
Description:
Change the word " Prime"in section 9.5.2.2 of the UFSAR to " station minicomputer % The reason is to clanfy any possible Configuration Controlissues. Specify a Generic name rather than a specific vendor. This GSEP software was transferred to another minicomputer. The
" Prime" computer is no longer required.
Result'. This evaluation determined that an unreviewed safety question did not exist.
Safety Evaluation Number: 1998-03-236 Type of Safety Evaluation: Exempt Change Evaluation Reference Number: E12-3-98-209, DCP 9800162
Title:
Safe Shutdown Battery Packs
Description:
The subject modification will install an emergency lighting unit (Safe Shutdown Light #460) on the Unit 3 Reactor Building first floor elevation 517' column M-45 for MCC 38-4 cubicle E5.
Result: This evaluation determined that an unreviewed safety question did not exist.
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End of Report
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