ML20213C810
| ML20213C810 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/01/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8611100290 | |
| Download: ML20213C810 (8) | |
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i DUKE POWER COMPANY P.O. HOx 33180 CHARLOTTE, N.C. 28242
- 'AI*yO HAL B. TUCKER run.mp, sown j,a (704)373-453:
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July 1, 1986 l
Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Conunission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30302
Subject:
McGuire Nuclear Station Docket No. 50-369, 50-370 h
Dear Dr. Grace:
Please find attached descriptions:ofTalL facilityIchanges which were completed under the provisions of 10 CFR 50.59 between January 1, 1985 and
-December 31, 1985. This is submitted pursuant to the requirements of.10 CFR 50.59 (b).
Very truly yours,
<e-c -
Hal B. Tucker JBD/j gm Attachment 8611100290 860701
- U I
DR ADOCK 05000369 i
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'McGuire Nuclear Station
-Facility Changes Completed Under the Provisions of 10CFR50.59 During 1985 NSM (Nuclear Station Modification)
'MGl-184 This modification installed a sonar seasol detector on the vent condenser vent ~ header for the boron recycle and liquid waste. recycle system evaporators to detect and alarm flooding in the vent condenser vent header.
Safety Evaluation Summary: This modificatir,n does not impact upon any safety system and is strictly to improve evaporator availability.
by the early detection of drain line back up.
MG1-560- This modification installed a water hammer arrestor in the.make-up demineralized water system due to water hammer in the line severe enough to break a flow gauge in that line.
Safety Evaluation Summary: This modification was installed to increase system reliability by preventing water hammer damage' in the system.
MG1-663 This modification upgraded the fire protection system by relocating the Fire Detection Processing Control Center into.the control room, connecting a printer to assure that any alarm or trouble is annunciated, and grounding shielded cables.
Safety Evaluation Summary: This modification improves plant safety.
by enhancing operator response to fire detection alarms by relocating the alarm panel into the control room, simplifying operator response to an alarm, and assuring that the operator receives all alarms.
MGI-752 This modificationt changed out victaulic tees on the discharge of each instrument air compressor to elbows due to vendor recommendation.
Safety Evaluation Summary: This modification enhances plant safety by enhancing instrument air compressor reliability; excessive backpressure was contributing to high maintenance.
MGI-856 This modification added a tee on the outlet of the tell tale valve-(INV329) to install a pressure gauge and tygon tubing or a sight glass.
Safety Evaluation Summary: This modification does not affect plant safety but will allow viewing of reactor coolant filter IA drainwater and pressure monitoring to verify that the filter housing is.no longer pressurized.
-MG1-892 This change reclassified the liquid waste recycle, boron recycle, liquid' waste monitor and disposal, and the nuclear solid waste disposal systems to non-nuclear safety related and to non-ASME code status in order to expedite modifications and the deletion of unnecessary support / restraints.
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,-ss Safety Evaluation Summary: -This change does not affect plant safety as no functional changes were made and an extensive review of-the system reclassification concluded that failure of these systems will not violate offsite release limits. No unreviewed safety questions are' created by this modification.
' MGI-956 This modification enabled the protective relaying of the diesel MG2-064
- generator regarding time overcurrent protection and instantaneous overcurrent protection. These trips, protect the diesels and
-associated switchgear.
' Safety Evaluation Summary: This modification enhances plant safety by protecting the diesel generator. This modification required NRC approval, reference license amendments numbers 38 (NPF-9, Unit 1).
.and 19 (NPF-17, Unit 2).
MG1-962 This modification re-routed the overflow of the Unit I reactor MG2-033'
-make-up water storage tank, the Unit 1 boric acid tank, and the Unit 2 boric. acid tank from the Waste Evaporator Feed Tank (WEFT) to the Recycle Holdup Tanks to avoid WEFT overflow through the WEFT vent and the resulting contamination.
Safety' Evaluation Summary: This change does not impact plant safety as it only affects the disposition of excess liquid in these tanks.
The prevention of contamination is consistent with ALARA considerations.
MG1-1016 This modification installed a permanent station air connection to the washing machine in the decontamination laundry area of the contaminated parts warehouse. This permanent modification replaces a temporary hose connection.
' Safety Evaluation Summary: This modification has no impact upon plant safety and ensures the availability of decontamination
' facilities by establishing a permanent connection rather than'a temporary hose connection.
MGl-1106 This modification provided the capability of pumping the turbine building sump waste into the condenser cooling water discharge. This change will prevent any contamination of the conventional waste water treatment system. The previous alignments were not practical due to the low level of activity versus volume and chemicals in the sump.
Safety Evaluation Summary: The new alignment assures proper operation of the turbine building sump. The discharge is monitored such that the probability (or volume) of a radioactive release is unaffected. The potential chemical contaminants (nitrites, ammonia, hydrazine, and boron) are diluted as to be well below established safe concentrations at discharge.
MG1-1112 This modification tied the lab drains in the conventional sampling system lab into the turbine building sump (treated water) and.the respective condensate storage tank (untreated water). This is to prevent possible cross contamination of units in the event of a primary to secondary leak.
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Safety Evaluation Summary: This modification enhances plant safety by providing, in the case of a primary to secondary leak, the capability of aligning the drains to the Unit having the leak,.thus keeping radioattive contamination from the other unit.
MG1-1305 'This modification replaced twelve ITT General Controls damper actuators with redundant backdraft dampers in the control room area ventilation system to maintain environmental qualification.
' Safety-Evaluation Summary: This modification enhances plant safety by maintaining the environmental qualification of the equipment thus ensuring operability.
MGI-1312 This modification installed a breathing air system'line to the new decontamination facility in the contaminated parts storage warehouse due to the high probability of needing air supplied respiratory equipment'in this area.
Safety Evaluation Summary: This rodification does not affect any safety system and is for the protection of personnel working in this area.
MG1-1346 This modification added T-cold instrumentation to the SSF by replacing' single element RTD's with dual element RTD's.
One element feeds the process control system and the other element feeds the SSF readout.
Safety Evaluation Summary: This modification is in response to an NRC requirement.
MG1-1425
.This modification added an additional vent and prime valve to the residual heat removal system suction line. The new valve is in the auxiliary building to provide a more accessible environment in which to vent the line. Previously, the only vent was inside containment.
Safety Evaluation Summary: The new valve is manually operated and was installed for personnel accessibility. No functional changes
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were'made to any system to cause any degradation. The valve is manually operated thus no~ inadvertent opening can occur.
MGl-1433 This modification deleted several valves in the steam generator blowdown system that no longer served a useful function (and were a maintenance problem) and to upgrade the system piping class.
Safety-Evaluation Summary: This modification enhances plant safety by eliminating several non-functional valves that have become a maintenance problem. The piping upgrade has no effect on plant safety as no functional changes are involved.
MG1-1436 This modification installed a low range flow meter on each condensate steam air' ejector air discharge line to reliably measure air flow below approximately 10 SCFM which was not previously possible. Air inleakage has generally been in the 6 to 15 SCFM range.
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kj Safety Evaluation Summary: This modification enhances plant reliability by allowing the accurate measure of low air flow in the condensate systems to. allow better chemistry control thus reducing maintenance.
MG1-1442 This modification replaced the copper-nickel tubes in the reheat sections of the moisture separator reheaters with stainless steel tubes to remove copper from the secondary system and to slightly reduce the plant heat rate.
Safety Evaluation Summary: This change will enhance equipment reliability by removing the main source of copper in the secondary system, thus reducing corrosion.
MG1-1501 This modification installed a fire protection sprinkler system MG2-0369
-in the equipment decontamination room.
Safety Evaluation Summary: This modification enhances plant safety by providing automatic fire supression in an area where combustibles are stored.
MG1-1511 This modification added steam generator level lead / lag circuitry MG2-0395 to avoid inadvertent trips on low-low steam generator level.
Safety Evaluation Summary: This modification enhances plant safety by preventing inadvertent reactor trips on low-low steam generator level and the resultant challenges to safety systems and plant transients.
MG1-1523 This modification added the diesel generator (D/G) panel alarm information to the operator aid computer (0AC). This will allow operators to find out specifically what is wrong with the D/G using the OAC. This change is in response to a human engineering discrepancy (HED).
Safety Evaluation Summary: This modification does not affect any safety system and improves the availability of information to the operators.
MG1-1529 This modification replaced a damaged one-inch gate valve in the moisture separator-reheater bleed steam system with a more efficient (in terms of availability and reliability) one-inch globe valve.
Safety Evaluation Summary: This modification caused no functional changes to any system and enhances plant efficiency by improving the availability / reliability of the moisture separator reheater bleed steam system.
MG1-1660 This modification installed a sprinkler system in the mechanical equipment room in the administration building.
Safety Evaluation Summary: This modification enhances plant safety by expanding the fire protection system.
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v MG1-1669 This modification replaced the internals of two valves in the residual heat removal system to convert them to a packed configura-tion. This was to prevent valve hammering which was experienced in the previous configuration.
Safety Evaluation Summary: This modification should enhance plant safety by enhancing the operability of existing systems by preventing valve hammering. The vibration from this valve hammering had caused cracking of some welds in the system which this modification will prevent.
MG1-1706 This modification installed temperature sensors upstream of eight MG2-0551 auxiliary feedwater check valves to detect back leakage of feedwater into the system, potentially overpressurizing the auxiliary feedwater suction piping.
Safety Evaluation Summary: This modification enhances plant safety by detecting check valve leakage thus aiding in the prevention of system overpressurization and. steam binding of the auxiliary feedwater pumps.
MG1-1719 This modification removed two valves in the Upper Head Injection System check valve test header and replaced them with blank couplings to reduce leakage from'the UHI accumulator to the refueling water storage tank.
-Safety Evaluation Summary: This change improves system reliability by decreasing system leakage. The piping and valves in the check valve test header have been determined to be unnecessary.
MG1-1744 This modification disconnected the resin batching tank vent overflow line from the auxiliary building ventilation system main header and rerouted the overflow to vent locally.
Safety Evaluation Summary: This modification enhances plant safety by precluding the possibility of resin overflow being pushed into the ventilation system and being released to the environment.
MG1-1772 This modification installed thermocouples on the RTD bypass scoop pipe to monitor temperature streaming in the reactor coolant system hot legs to gather data for justification of RTD bypass manifold system removal in favor of a thermowell type RTD system.
Safety Evaluation Summary: This modification caused no functional changes. The thermocouples strap-on thus no cutting of the pipes was involved which may have led to leakage. The modification is for l
passive monito:$ng of the system.
I MG1-1833 This modification installed two new drain lines on the inlet and outlet nuclear service water lines to the containment spray heat exchanger to aid in the cleaning of the heat exchanger.
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)I Safety Evaluation Summary: This modification enhances plant safety by supporting cleaning of the heat exchanger which will assure heat exchanger operability.
MG2-0076~ This modification involved the installation of the Reactor Vessel
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Level. Indication System (RVLIS).
I Safety Evaluation Summary: This modification was due to a Regulatory Commitment, Reg. Guide 1.97, and will enhance plant safety by providing operators with an indication of water level within the RCS.
MG2-0208 This modification installed six igniters in the hydrogen mitigation system and modified controls and indication such that activation and system status indication is in the control room.
Safety Evaluation Summary: This change enhances plant safety by augmenting the hydrogen mitigation system and was a license condition for McGuire.
MG2-0241 This change installed a manual isolation valve upstream of a turbine flow meter (2NVFE5450) to allow isolation of the meter for maintenance without isolating a boric acid addition path.
Safety Evaluation Summary: This change enhances plant safety by allowing the flow meter to be isolated without interruption of the boric acid flow path.
Exempt Changes ME-VN-95 This modification installed a Kerotest seal cap on valve INC64 to seal a leak. This modification rendered the valve inoperable in the full open position.
Safety Evaluation Summary: Valve function is not necessary for safety, therefore sealing the leak enhances plant safety as this is a source of primary coolant leakage.
ME-VN-144 This modification deleted the internals from a valve in the station air system to assure backup for the station air compressors.
l Safety Evaluation Summary: This change enhances plant safety by l
assuring a backup supply of air to the station air system.
ME-VN-190 This modification replaced the containment spray heat exchanger vent valve with a tufline plug valve due to the original valve being corroded and inoperable, i
Safety Evaluation Summary: This change causes no functional changes to the system and enhances safety by allowing inspection of the containment spray heat exchanger.
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NPR1-785A This change added propeller meters between several makeup demineralized water system valve and their associated liquid waste j
monitor and disposal system valves to detect leakage before it F
reaches and fills the floor drain tank.
i Safety Evaluation Summary: This change has no effect on plant safety and is to reduce the volume of liquid that may have to be treated as radioactive waste.
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