ML20198T406
| ML20198T406 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/30/1997 |
| From: | Ritzman R Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20198T350 | List: |
| References | |
| NUDOCS 9801270050 | |
| Download: ML20198T406 (7) | |
Text
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F DOCKET NO. :. 50-354 UNIT: Hope Creek ,
DATE: 12/11/97 COMPLETED BY: R. Ritzman TELEPHONE:. (609) 339-1445 h
SUMMARY
OW "HAEGES, TESTS, AND EXPERIMENTS EQR TH1. , sura; CREEK GENERATING STATION MONTH NOVEMBER.1997.
The_following items completed during November 1997 have been evaluated to determine:
.1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety '
previour'r evaluated in the safety analysis report may be increasea; or
- 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
- 3. If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50.59 Safety Evaluations showed that these items-did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Desian Chances Summary of Safety Evaluations
-4EC-3458, Pkgs. 1 and 2, Recirculation Pump Shaft Piping Upgrades Pump Seal Cartridge Vent Addition. This design change adds two 1 inch vent valves to the recirculation pump shaft seal cartridge
-piping. This design change also replaces a section of pipe with a section of pipe;that contains vent valves. The purpose of this design change is to improve the venting _ capability of the pump-seals.
'9901270050 980115 I PDR ADOCK 05000354 R. PDR;
1The operation off the recirculation-pump is not impacted by this s
1 design = modification:in any'way other than to increase the-pump.
shaft' seal
- life and.to decrease >the frequency.of failures-by permitting better seal-venting. _This. design-change:did not increase the probability'or consequences of a malfunction of equipment important1tol safety, create the possibility ofLan- '
accident or malfunction of a different type than previously _
evalcated in the SAR, or reduce the_ margin of safety for_any Technical Specifications. Therefore, there are no unreviewed safety-questions associated with this design change.
4EC-3458, Pkgs. 3 and 4, Recirculation Pump Shaft-Piping Upgrade: -
Pump Seal Leak-Off Line Rerouting. This design change reroutes the Recirculation Pump Mechanical-Seal Leak-Off line, which runs frcm the seal flange to the Drywell Equipment. Drain Sump. -The-original routing of_this lineidid not provide a continuous- .
Edownward slope and prevented the line and associated flow switch from passing any flow. The line now routes seal leak-off flow through a flow switch to'the sump.
The operation of the recirculation pump is not impacted by this design modification in any way other than to increase the pump shaft seal life and to decrease the frequency of-failures by -
permitting better seal venting.. This design change did not increase the probability or consequences of.a-malfunction of equipment important to safety, create the possibility of an .
accidSnt or malfunction of a different type than previously evaluated in'the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this design change.
4EC-3523, Pkg. 1, Class 1E Oscillation Power Range Monitor. This design change installs the Oscillation Power Range Monitor (OPRM) in'the Power Range Neutron !!onitoring System Cabinet for
-detection and. suppression of reactor core thermal'b.draulic instability events.. For this operating' cycle, the system will
- provide monitoring functions only.
The'OPRM equipment is-installed as a Class 1E system and is appropriately separated in accordance with Reactor Protection System and Neutron Monitoring system separation schemes. The i OPRM1 installation does not affect the existing APRM protective functions. This design change did not increase the probability
- or1 consequences of a malfunction of' equipment-important to
. safety,-1 create the possibility of an' accident or malfunction of a
=different type than previously evaluated in the.SAR, or reduce-
,the marginLoffsafety for any Technical-Specifications.
LTherefore,-there are no unreviewed safety questions associated
-with.thisidesign-change.
i 4EC-3638, Pkg. 1 - 8, Motor Operated Valve' Modification (Information Notice 92-18) . Information Notice 92-18 ideistified-ta-concern.that a-fireuthat' forces evacuation of the Control. Room could also cause. hot short circuits between control wiring and power _-sources-for motor operated valves _(MOVs) required to shut down the reactor cnd/or maintain _it in a safe shutdown condition.
As a-result of this design change, MOV control circuits for 51 valves have been modified so their torque / limit switches.are not -
bypassed for a postulated hot short. This modification was accomplished by internal wiring changes in motor control centers and DC panels. This design change also disabled thermal overload trip functions.
This-design change did not increase the probability or [
consequences of a malfunction of equipment important to safety,
-create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce i
. the margin of safety for any Technical Specifications. ,
_Therefore, there are no unreviewed eafety questions associated
.with this design change.
4EC-3640, Pkg. 1, Tornado Missile Barrier for Control / Diesel Electrical Room in the Auxiliary Building. This. design change removed a non-safety related and non-fire protection door from the-Control / Diesel Electrical Room in the Auxiliary Building.
After the door was removed, the opening waa filled with concrete.
The door did not provide adequate tornado and tornado missile protection for the electric conduits associated with the "A" Control Room Emergency Filtration system, which are located in this room. An access ladder was also added as a result of this
. design change.
This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a
'different type'than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications.
Therefore, there are no unreviewed safety questions associated with this design change.
4EC-3656, Pkg. 1, Overpressurization Related Mcdifications. This-design change installed relief valves in various piping segment inside the containment. The addition of these relief valves provides:a method to relieve the overpressure condition that could_ occur-due to-the heatingsof trapped water during a Loss of Coolant Accident.
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This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the' possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications.
Therefore, there are no unreviewad safety questions associated with this design change.
4EC-3602, Pkgs. 1 - 5, Addition of a Backup Air Supply to the Control Area chiller Safety huxiliaries cooling System control valves. This design change modified the instrument air supply lines for the chiller Safety Auxiliaries cooling System (SACS)
Outlet Control Valves by adding a safety related backup air supply. This backup system will supply air / nitrogen via two air / nitrogen bottles.
This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications.
Therefore, there are no unreviewed safety questions associated with this design change.
4EC-3663, Pkgs. 1 and 2, Reroute Station Service Water Vacuum Piping to a Clean Post-Accident Air Source. This design change rerouted the Station Service Water vent piping at the "A" and "B" Safety Auxiliaries Cooling System (SACS) Heat Exchangers' effluent. The new routing pipes a segment of new /ent line from downstream of the vacuum breakers to the respective loop overboard discharge piping downstream of the rupture disks and isolation valves. By rerouting the vent piping, the air drawn into the Service Water System via a f ailed open vacuum breake. is clean outside air.
This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the FAR, or reduce the margin of safety for any Technical Specifications.
Therefore, there are no ireviewed safety questions associated with this design change.
4EC-3664, Pkg. 1, Core Spray Reactor Pressuro Vessel NSB Nozzle Weld overlay. This design change addresses the repair mechod used to restore core spray piping integrity. The method includes a reinforced structural weld overlay around the entire circumference of the affected core spray nozzle to safe end weld region.
The repair of the core spray nozzle maintains the original design requirements for core spray piping integrity. The weld overlay has also bben shown to prevent further flaw growth in deposited weld material. The repair has no impact on the required core spray system functions. This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Theretore, there are no unreviewed safety questions associated with this design change.
4EC-3665, 7kgs. 1 and 2, Filtration, Recirculation, and Ventilation System Standby Exhaust Fan Start Time Delay Setpoint Change. This design change reduced the t.me d delay interval of the Filtration, Recirculation, and Ventilation System (FRVS) Vent Fan start. The timer setting was changed to resolve a discrepancy pertaining to the Secondary Containment drawdown time.
This design change did not increase the probability or consequences of a realf unction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or redLce the margin of safety for any Technical Specifications.
Therefore, there are no unreviewed safety questions associated with this design change.
4HE-0003, Pkg. 5, Installation of Vent Valves on Selected Locations of the Residual Heat Removal Headers. This design change installed vent valves on a Residual Heat Removal (RHR) line. The vent valves are intended to be used to support the draining of this RHR line.
The operation of the RHR system will not be affected by these vent valves. This design change did not increase the probability or consequences of a malfunctior of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specificatiot.s.
Therefore, there are no unreviewed safety questions associated with this design change.
4HE-0300, Pkg. 50, Rework Closed Motor Operated Valve Position Indication on the Fecdwater Heater 6A Outlet Isolation Vilve.
This design change provided a jumper to bypass a torque switch during normal plant operations. The jumper is necessary to allow the resetting of an open indication limit switch. Resetting the limit switch provides position indication by maintaining the illumination _of the valve open light until the valve reaches the full closed position.
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. 1 The affected limit switch is not a control element and the .
elimination of the opening torque feature will not prevent the l val */e*from' performing its intended functions. This design change did not increase the probability or consequences of a malfunction ,
of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously .
evaluated in the SAR, or reduce the margin of safety for any l Technical Specifications. Therefore, there are no unreviewed ;
safety questions associated with this design change. :
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- 4HE-0300, Pkg.H51, Rework Closed Motor Operated Valve Position
. Indication on the Feedwater Heater 6B Outlet Isolation Valve.
This design change provided a jumper to bypass a torque switch -t during normal plant operations. The jumper is necessary to allow -
the resetting of an open indication limit switch. Rosetting-the limit switch provides position indication by maintaining the !
illumination of the valve open light until the valve reaches the full closed position.
The affected limit switch is not a contr 1 alement and the elimination of the opening torque featut _1 not prevent the valve from performing its intended funct. ..). This design change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an
- accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this design change.
i 4HE-0300, Pkg. 52, Rework Closed Motor Operated Valve Position Indication on the Fewdwater Heater 6C Outlet Isolaticn Valve.
This design change provided a jumper to bypr9s a torque switch during normal planc operations. The jumper is necessary to allow the resetting of an open indication limit switch. Resetting the limit switch provides position indication by maintaining the illumination of the valve open light until the valve reaches the full closed position.
The~affected limit switch is not a control element and the ,
elimination of the opening torque feature will not prevent the valve from performing its intended functions. This-design change ,
- did not increase.the probability ort consequences of a malfunction of equipment.important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR,;or_ reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions-acaociated with this design change. -
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4ME-0362, Pkgs. 1 and 2, Steam Jet Air Ejector Low Flow Switch Interlock Logic change. This design changes modified the logic for the Cchdenser Air Removal System. The flow switch downstream of the main steam feed valve to the Steam Jet Air Ejectors (SJAE) closed the main steam feed valve on a 30 second time delay when steam flow was Icss than the setpoint. This design change modified the logic so that this interlock is defeated when the ;
condenser la isolated from the SJAE train.
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This design change does not degrade the performance of any system ;
structure or component. This design change did not increase the i probability or consequences of a ' function of equipment important to safety, create the possibility of an accident or ;
malfunction of a different type than previously evaluated in the
- SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety !
questions associated with this design change. ;
Ipapprary Modifications Summary qf Safety Evaluations i No changes for these categories are being reported for November l 1997.
Procedur_ts Summary of Safety Evaluations No changes for these categories are being reported for November 1997.
VIEAR Chancre Notices S_Ummer_y_pf Safety EvaluR119D1 No changes for these categories are being reported for November 1997.
Deficiency.Recorts Summary of Safety Evaluations No changes for these categories are being reported for November 1997.
Other Summary of Safety realuation No changes for these categories are being reported for November 1997. ,
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