ML20246E758
| ML20246E758 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1988 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20246E756 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8907120378 | |
| Download: ML20246E758 (59) | |
Text
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CATAWBA NUCLEAR STATION
SUMMARY
OF NUCLEAR STATION MODIFICATIONS REPORTABLE UNDER 10 CFR 50.59 DURING 1988.
.. CN-10005.-
==
Description:==
.This. modification - replaced flow switches on
.affected radiation monitors with flow switches less susceptible a
~
- to material buildup and clogging.
This modification affects e
FSAR Figures' in Sections 9.2, 9.3, and 11.2.
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Safety Evaluation:.This modification reduces maintenance cost and-improves equipment performance.
This change does not l.-involve any' functional change to any system. ~No safety system is affected.. The new flow switches have a larger, more open d
- interior design which has proven less susceptible to clogging problems.at other stations.~ No unreviewed safety question is created by this modification.
I CN-00010'.
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Description:==
This modification-involves changes to the Mixing
+
and Settling Tank (MST)- and the Liquid Waste Recycle. System so that. operation of the MST complies with the FSAR.
The
' modification J1) reroutes a section of' the MST pump suction line, 2) 'provides an interlock with 1WL883, 0WLLT5190, MST Pump-and MST Sludge Pump,.3) reroutes overflow' lines for Radwaste Batching Tank and Ultrasonic Cleaning Tanks to remove loop seals, 4) adds a crossover' discharge line, valves,.and Makeup Demineralized Water System seal water to the MST pump, and 5) adds'a Johnson Screen to-the Radwaste Batching Tank vent to
-atmosphere.
This modification; affects FSAR Section 11.2 and Figures 11.2.2-4 and 11.4.2-4.
Safety Evaluation:
These improvements will allow the MST subsystem to be operated. as described in the FSAR.
This modification will 1) provide adequate NPSH for and allow proper operation of the MST pump, 2). bring the Radwaste Batchirg Tank overfhw :line and Ultrasonic Cleaning Tank-drainline into conformance with ALARA exposure guidelines, 3) provide a flush supply for the RBT overflow line, and 4) allow interchangeable use of the MST pump with MST sludge pump to provide redundant -
capability required in FSAR Sections 11.2.1 and 11.2.2.2.
No safety' system will be degraded and no functional change will be made to any system as a result of this modification.
No unreviewed safety question is judged to be created by this modification.
dN-10023.
==
Description:==
This modification replaces affected solenoid valves with manual valves to prevent spurious actuations.
These valves are non-active and have a potential for repositioning as a result of a spurious electrical signal or a seismic event.
This modification affects FSAR Figures 9.3.4-2, 9.3.4-4, 9.3.4-5, 9.3.4-7, 9.3.6-1, 9.3.6-2, 9.3.5-1, 9.3.5-3, 9.3.5-4; 9.3.5-5, 11.2.2-5, 11.2.2-10, 11.3.2-1, 11.3.2-5, 9.2.1-5, and 9.2.1-9.
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. N' safety system will be degradeo by this Safety Evaluation:
o modification.
Replacement ' of the solenoid valves, which I-control.! air supplied to Class 2 -or. 3 pressure boundary
- isolation valves,'. wil.1 greatly reduce the possibility of
. inadvertent. actuation - of: these valves due' to. spurious
'1
, electrical signals or seismic activity affecting the solenoid-valves.
This modification 'does not involve any unreviewed
- safety consideration.
>CN-10183
Description:
. This modification reroutes Condensate System T
resins processing lines to minimize the distance, elevation, and bends. in : the resin discharge piping.
Additionally, necessary. equipment was. providad to allow vendor removal of I
contamina'ted resin from.the Condensate Po11 sher Demineralized
. (CPD) Backwash tank.
A curb was. also installed around the resinL cask.-loading area.
This modification affects FSAR
- Figures;10.4.2-2 and 10.4.7-4, 10.4.7-9 and 10.4.8-2.
Safety Evaluation:
This modification allows for more efficient and ALARA operation of the CM' system.
In the event of a steam generator tube.l ea k, resin in the CpD's would become contaminated.
Each precoat in a CPD has a life of five to six days before it is exhausted ~and the Backwash Tank has a capac'ity of=four (4) backwashes..Thus, the Backwash Tank would haveito be emptied at least once per week.
This would allow very.little' time'.to install the necessary equipment required by Chem-Nuclear-for removal of contaminated resin, Without the modifications described above, situation could arise where there would be contaminated resin in the Backwash Tank without the required means of disposing of it.
This modification' does not adversely affect any equipment important to safety.
This modification does not involve any unreviewed safety
- consideration.
iCN-10184
Description:
This Unit I modification installs piping and p"
valves to allow condensate from the Boron Recycle and Waste Evaporator's condensate return tanks to be discharged to the Uriit 2 ' Condensate Storage Tank (CST).
This modification affects FSAR figure 9.2.6-2.
Safety Evaluation:.This modification is required to minimize the volume of water that must be reprocessed following a Unit 1 or Unit - 2 primary to secondary leak and allows for cross-routing of non-radioactive condensate between units.
This modification does not have any adverse impact on any
. safety or non-safety system.
This modification dose not involve any unreviewed safety question.
i CN-10385
==
Description:==
The general intent of these modifications is to CN-20185 add the capability.to process Ventilation Unit Condensate Drain Tank-(VUCDT) contents through disposable vendor demineralizers provided by a contractor.
The diaphragm in the recycle monitor tanks will be removed to increase usable tank volume.
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. modifications affect FSAR Section 11.2 4 and Figures 11.2.2 _4, l
111.2.2-7,'and 11.2.2-11..
Safety Evaluation:
-The: VUCDT. system ; was designed for the normal discharge path to.be through a. radiation monitor toLthe Turbine Building (TB) sump.
If the monitor's high setpoint is
. reached, the discharge stream is automatically isolated from ithe' TB sump and is realigned by an operator to the liquid radwaste' release path.. Experience at both McGuire and Catawba L
shows that higher levels of activity than were anticipated will.
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. be present.
Use.of vendor demineralizers' will-help expedite h
the processing of.the condensate, which could otherwise require more elaborate processing along the.same pathways as the main liquid waste stream, thereby impeding processing of radwaste p,
The changes to the system. including additional piping -and valves are located in the Auxiliary Building and are designated Dukei Class E,- QA Condition ' 2.
The piping is hung by' construction. hangers and is. non-safety. related.
The pipe t
routing was reviewed for-ALARA concerns and for. pipe rupture concerns.
Fire barrier-integrity reviews for piping are adequate.
Electrical; instrumentation added to the~ control panel h.
70 seismic considerations.
The removal of the Recycle Monitor Tank (RMT) diaphragms will not' introduce any additional offsite release considerations.
However, the venting of these tanks to the room should be reviewed for ALARA concerns.
The probability and consequences-of the radwaste tank accident is not affected by modifications to the RMT due to its intended function and protection afforded by the Auxiliary Building.
This system has no emergency or safety function and is not fire E
protection related.
These modifications do not involve any unreviewed safety considerations.
CN-10421
==
Description:==
This modification provides -for the addition of permanent cables for eddy current testing of the steam generators.
This modification affects FSAR Table and Figure 3.8.2-6.
Safety Evaluations Potential concerns involved with this modification include considerations of the clarity of the eddy current tests due to extra electrical connections.and additional openings to containment.
The. additional electrical connections should not be a concern as.the eddy current testing will be done by computer which will compensate for the extra electrical connections.
This testing is done by way of frequency measurements.
The concern for additional openings in containment reflects the condition that eddy current testing 3
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could not take place during core alteration or movement of fuel in containment.
This condition is reflected by Technical Specification 3/4.9.4.
During normal operation this L
penetration will have blind flanges installed on each end of the penetration.
These flanges will be double sealed.
Based on this.information, there are no potential concerns.
'The modification is not related to the initiation of any new accidents or the. malfunction of any equipment as described in 4
the FSAR.
The modification will not result in the creation of any'new accidents or malfunctions.
The modification will not have any impact on the plant margin of safety as defined in the Technical Specifications.
This modification does not involve any unreviewed safety question.
CN-10593
==
Description:==
These modifications provide an air conditioning CN-20023 system to cool the electrical penetration room during the summer when normal Auxiliary Building Ventilation (VA) system supply air is inadequate.to handle the heating. load.
This modification affects FSAR Section 9.4.3.2.6, Table 8.3.1-1 and Figures 11.2.2-12, 9.4.2-3, and 9.4.3-2.
Safety Evaluation:
These modifications assure adequate cooling of the Reactor Vessel Level Instrumentation System (RVLIS) cabinets.
The modifications improve long-term reliability of the' system.
This modification presents no adverse impact to any safety or non-safety system.
These changes do not involve any unreviewed safety consideration.
CN-10003
==
Description:==
This modification involves adding structural CN-20004 components to the reactor vessel head lifting rig which is left in place (on the head) during normal operation.
Removable shielding is attached to the head lif ting rig to provide radiation shielding for workers during refueling.
This
. shielding will be removed during normal operation but necessary hardware will remain attached to the lead lifting rig always.
No changes have been made to the RCS pressure bounding.
Safety Evaluation:
This modification reduces radiation exposure in the reactor cavity with the use of the shield.
This modification does not affect any equipment important to safety.
This modification does not involve any unreviewed safety question.
CN-10721
==
Description:==
This modification installed an additional desiccant Unit at the VI Header takeoff for three of the
- Groundwater Drainage System Well Level Instruments.
The takeoff is located in the Unit 1 exterior doghouse.
This 4
modification affects FSAR Figure 9.3.1-2.
Safety Evaluation:
This modification is required to prevent malfunction of Groundwater Monitor Wells Level Instrumentation due to potential freezing of moisture in the air heater.
This j
modification does not adversely impact any safety or non-safety
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This modification does not involve any' unreviewed l'
safety consideration.
e CN-10810
Description:
.This modification changes the-Auxiliary Building L
.-Ventilation System (VA); unit vent' and its' associated Liquid Waste' Recycle. System (WL) drain.line to prevent. condensation.
and drainage problems.
This modification.affects FSAR Figures
'9.4.2-3 and 11.2.2-15.
i.
Safety. Evaluation: Addition of a piping tee provides access to clean.out debris-clogging the WL drain line.
Addition.of.a
. sight glass at the' lower end'of'the Unit vent plenum allows for y
early detection of condensation,in the Unit vent so as to prevent overflowing into ventilation systems connecting to the c
stack.
No safety system is degraded as a result of this L,
modification.
'This. modification does not involve any L
unreviewed safety considerations.
CN-10813
==
Description:==
These modifications provide a Makeup Demineral-g CN-20154-izer Water System water source. in the area of the lower personnel hatch.
These changes are required for general cleaning and decontamination purposes in the lower containment area.
These ' modifications affect' FSAR Figures 9.2.3-6, 3
9.5.5-1, 11.2.2-2, and 11.2.2-11.
Safety Evaluation:
Although the - modification is outside containment, no impact on containment integrity will occur.
The sink drain will be routed to a trench discharging into the Residual Heat Removal and Containment Spray Rooms sump which is part of the Liquid Radwaste System (WL). The. sump is adequate-ly sized to handle a comparatively small flow such as can be expected from this source. Additionally, the system is manual-ly-operated locally which should limit excessive-flow to drains i
from spills.
The sump is designed to handle liquids that are l
potentially radioactive.
lhe new pipe is Class' G or H and the meterials and design i.
parameters are compatible with the system requirements.
1 Seismic considerations have been reviewed.
The_ Makeup De-J mineralized Wr.ter System plays no role in initiaMng or miti-i gating design basis accidents.
Based on the above, the proba-bility or consequences of an accident previously. evaluated in the FSAR will not be increased and no new accident different than any already evaluated in the FSAR will be created.
Since
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no equipment is adversely affected, the probability or con-sequences of a malfunction of equipment important to safety previously evaluated in the FSAR will not be increased and.
there is no possibility o'f malfunctions of equipment important to safety different than already evaluated n the FSAR.. No margin of.-safety as defined in the bases to any Technical Specification is reduced.
There are no unreviewed safety questions associated with this. modification.
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nCN-10825i Description':. This modification. involves interlocking the "S/R Hi: Voltage Failure" and "S/R Hi ~ Shutdown Flux Alarm Blocked"-
annunciators :with permissive circuit P-10.
The annunciators would be deactivated above P-10 (10% power):and be reactivated below - P-10; The' modification is accomplished by wiring the=
P-10. interlock, available in the SSPS' Control Board b
. Demultiplexes cabinet, to 'an ' IC cabinet where 'a multiplying..
p, relay 11s added. Contacts.from this relay are then added to the HA annunciator-circuits.
No operator action 1s required..This
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' modification affects FSAR Section 7.2.1.1.3.
Safety Evaluation:
Two potential equipment failure modes exist for;this modification:
- 1) The circuit =could fail to deactivate the annunciators above-m
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P-10.
Since the source range detectors are not required above the 10% power range, this failure mode would not
' result in'any safety concern.
- 2). The circuit could fail to reactivate the annunciators below
.P-10.
'If this failure occurred in the "S/R Hi Voltage.
Failure" Annunciator, the operator would have no indication
.that the S/R detectors'were de-energized.- 'If~this failure occurred: in the "S/R Hi Shutdown Flux Alarm Blocked" annunciator, the operator may erroneously think that' the "S/R Hi ' Flux at Shutdown" alarm was enabled when it 'was
.actually blocked. When the modification functions properly, the ' annunciators will normally alarm when the power. level drops below P-10.
If this failure mode occurred, the operator could potentially recognize a malfunction when the annunciators failed to come on. below P-10.
However, the manual de-energizing and blocking functions associated with these. annunciators are procedurally controlled and verified separately from the annunciators themselves.
These E
administrative controls are not' affected by this N
modification.
The IC cabinet for this modification will meet seismic / environmental requirements.
Appendix R separation criteria are not applicable to this modification.
This modification is not related to the initiation of any accidents or equipment malftuctions analyzed in the FSAR.
The initial conditions 'of the reactor coolant system and core will not be affected by this modification, and the ability to mitigate accidents will be unaffected.
This modification will not have any impact on the plant margin of safety as defined in the bases. to the Technical Specifications.
There are no unreviewed safety questions associated with this modification.
CN-10829
==
Description:==
These modifications interlock each Nuclear CN-20168 Service Water System (RN) Outlet Flow Lo Annunciator from the Component Cooling System (KC) Heat Exchanger with a safety b
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injection: signal.
This: assures the alarm will only be enabled
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.whenithere is a safety injection signal present. Without these modifications the. annunciator is constantly in alarm because of the relatively low heat load, on the KC system during normal' plant operation,.thus creating.a. nuisance alarm.
These modifications affect FSAR Section 9.-2.1.5.3.
' Safety Evaluation:
The : signal. to-the Annunciator is a non-safety non-QA signal. obtained ; from the safety injection
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.' circuit -that fails' open the RN outlet valves of the KCi Heat-Exchangers (RN-291 and RN-351).~ :A digital optical 1'solator is 1
added~in' series with the safety injection signal.
The optical
. isolator. creates ' a non-safety, output signal from a safety signal input without allowing any faults to propagate-back into the safety circuit.- This provides adequate protection of the safety injection circuitry to prevent any new failure modes to safetyi related = equipment from being created by this modi fication.
The relay which activates the "Lo Flow" Annunciator has a 3-5 sec. time delay' to allow' the RN outlet
. valve..of. the KC HX to open before signaling "Lo Flow" coincident with an SS-0 signal.
A KC HX discharge. temperature alarm and RN pump discharge alarm (high and low) are.provided in the control room independent of this modification.
The RN functions of essential auxiliary support to Engineered
- Safety Features, including RN pump minimum flow provided by SS-0 ' signa' to the subject flow control valves, are not impaired by this modification.
The operator's environment is improved by deleting a nuisance alarm.
Failure of the new interlock circuitry will either cause the nuisance alarm to sound without the SS-0 signal (same as present configuration) or prevent.the alarm'when desired given the SS-0 signal and "Lo a
Flow".
This flow indicat!on and annunciator are diagnostic.
They perform no safety ' function, are tiot relied upon for emergency ' procedures and the subject control valves fail open upon. loss of non-sa'ety instrument air.
Therefore, no failure modes related to this NSM will adversely impact any safety functions.
Accordingly, these modif' cations, will have no effect on the f
probability, consequences or " possibility of new" acr.idents evaluated in the FSAR.
Nor will it affect the probe.bility, consequences or possibility of malfunctions of equipment important to sa fety evaluated in the FSAR.
The margin of safety defined in the bases of the Tech. Specs. is unaffected.
These modifications do not involve any unreviewed safety question.
CN-10865
==
Description:==
These modifications provide for the installation
- CN-20247 of improved tube leak detection systems to determine the l
location of condenser tube leaks.
These modifications affect i
FSAR Figure 10.4.2-1.
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Safety Evaluation:
The SF, on-line condenser waterbox leak detection system utilizes sulfur hexaflouride (SF ) as' a tracer gas to detect condenser tube leaks.
SF, is injected into the amertap ball collectors (RA system).
Any tube leakage will be detected by pulling a sample downstream of the condenser steam air ejectors (ZJ system).
This system is totally independent and in no way affects the operation of the amertap system, the condenser steam air ejector system, or any interfaces in between.
SF, is a colorless, odorless, non-flammable and non-toxic gas.
These modifications do not involve any unreviewed safety consideration.
CN-10920
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Description:==
These modifications add high range differential CN-20308 pressure gauges that have extended range required for the Diesel Ger.erator (D/G) Fuel Oil Day Tank (F0DT) and provide adequate indication of level.
These modifications affect FSAR Figures 9.5.4-1 and 9.5.4-2.
Safety Evaluation:
These modifications provide an additional gauge to show level in the D/G Fuel Oil Day Tank.
Testing of these modifications involves calibration of the new gauges and a leak test. The consequences or probability of an accident or malfunction of equipment previously evaluated in the FSAR will neither be increased nor created as a result of the changes.
The margin of safety as defined in the basis to any of the Technical Specifications will not be reduced by the changes.
These modifications do not involve any unreviewed safety question.
CN-10927
==
Description:==
This modification replaces Auxiliary Feedwater (CA) check valves ICA 157,159,161 and 163 with Anchor / Darling carbon steel tilt disc check valves.
The existing valves have experienced operability problems due to the flow conditions at the location of the valves.
The new valves are more suitable for the flow conditions experienced in the main feedwater ten,pering/ bypass lines and should provide more reliable service.
This modification affects FSAR Figure 10.4.9-2.
Safety Evaluation:
The check valves being replaced (1CA157, 159, 161 and 163) are located in the main feedwater tempering / bypass lines, one to each of the four steam generators.
Therefore, no failure modes are postulated which would affect more than one steam generator's feed path.
The design basis of the CA system will not be affected by this modification and the modified system should prove to be more reliable, requiring less maintenance.
The probability of accidents or equipment malfunctions will not be increased by this modification and the ability to mitigate the consequences of accidents may actually be enhanced since the reliability of the CA system will be increased.
No new types of accidents or equipment malfunctions are postulated and
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the margin of safety defined in the bases to Technical l
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g Specifications will not be' reduced. 'Therefore, no unreviewed d
safety ' questions are-created by or. involved with this modification.
CN-10970
Description:
This modification provides for the addition of.
office space to ; allow for close supervision 'of the water -
treatment room.
This modification' involves.FSAR Figure L
9.5.1-7.
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- Safety Evaluation:
This modification is non-QA Condition and' non-safety; related.
Sprinklers are added ' for area and-
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- equipment protection, but are.not required for Appendix R since there: is 'no safety - related equipment in the immediate area.
K' The plant lighting panelboard circuit 1s ncn-safety related and-
- there are no Appendix. R circuit-interaction concerns.
The 4
phone system is also non safety.
This modification does-not tinvolve any unre' viewed safety consideration.
CN-10974
==
Description:==
These modifications are to facilitate access to
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CN-20366 the fuel pool area.
Doors AX635 J and K will be held open with
'a fusible link, which will alleviate problems associated with entering / exiting the Fuel Handling Areas via these doors.
Most air infiltrating through the open door will enter the VF System through two air transfer openings from the' Ventilation
'iquipment room to the Fuel Building.(*) L This infiltration would exceed the capacity of the VF system ~ to maintain' the required.25 inch' negative pressure.
By blocking off one of the two before' mentioned air transfer openings and adding a manual volume damper to the other, the required pressure will be maintained.
These modifications affect FSAR Figure 9.4.2-1.
Safety Evaluation:
Since the Feel Han'dling Area Ventilation
'l (VF) system is not an initiator of any accident previously evaluated in the FSAR, these modifications will not result in ai. : increase in the probability iof such acciderits.
The VF system will still be able to' maintain' the requf red.25 inch negative pressure in the Fuel Pool Area.
Tkerefore, the conscauences of neither a fuel handling e n.fdent nor any accident previously evaluated in the FSAR will be increased.
No possibility of an accident dif ferent from any already identified in the FSAR is created.
The probability of a malfunction of equipment imporcant to safety previously evaluated in the FSAR will not be increased since these modifications do not result in any change in.
parameters for which equipment is designed.
No common mode i
failure involving the VF or any other system is introduced by these modifications.
Therefore, the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR will not be increased.
No possibility of malfunctions of equipment important to safety different from any already evaluated in the FSAR will be created.
The margin of safety as defined in the basis to the Tech Spec will not be reduced.
9 1
No unreviewed Safety Questions are associated with this NSM.
L CN-10975
==
Description:==
These modifications install a forced air cooling CN-20367 system to the 7300 Process Control Cabinets in the control room.
The blowers to be-installed in the safety-related l
cabinets will be QA 1 seismically qualified, and powered by 1E cabinet power.
These cabinets are des-igned to function with convection cooling.
Addition of these blowers will not block the flow of air. for the continuation of the convection' process, however, addition of these. blowers will lower cabinet L
temperatures and extend equipment life.
Safety Evaluation:
This modification will provide extended equipment life for components of the 7300 process control cabinets.
There are 8 cabinets involved with each unit.
Four are safety-related and four are not.
All of the fans are supplied from internal cabinet power through circuit breaker
- 2.
Failure of the fans will not jeopardize cabinet cooling as convection cooling will be maintained through gril'Is located in the cabinet rears and in the center bays.
Fan failures will noc affect the ability of the equipment to function and will be identified by periodic inspection by station personnel.
No equipment relocation will be required for insta11ation'of the blower system.
Since the ability of the equipment to function is not adversely affected, the probability. of an accident or malfunction.of equipment important to safety which was previously evaluated in the FSAR will not be increased.
Addition of the blower system can provide life extension for the internal equipment and does not create any new failure modes except failure of the fan
-itself.
In this event, cabinet cooling is continued by convective airfinw, similar to the existing setup.
Therefore, the possibility of an accident or malfunction of equipment important to safety which is different than any already evaluated in the FSAR will not be created.
The ability of the equipment, within these cabinets, to fulfill their safety-related functions is not degraded, so the consequences of an accident or malfunction of equipment important to safety which were previousl.' evaluated in the FSAR will not be increased..There is no degradation of safety limits or setpoints as a result of this NSM and the reactor vessel core parameters are unaffected.
Equipment reliability has not been degraded, therefore, the margin of safety as defined in the bases to any Technical Specification is not affected.
Based on this discussion, no unreviewed safety questions are judged to be involved with this modification.
CN-10981
==
Description:==
This modification will replace affected RN system CN-10982 valves in order to provide a more reliable design for CN-10994 isolation. The valves to be replaced are:
CN-20371 CN-20372 RN Supply Crossover Isolation Valves (RN47A and RN488)
CN-20385 RN Nonessential Supply Header Isolation Valves (RN49A and RN50B)
RN Supply Header Isolation Valves (RN67A and RN698)
This modification is a one for one replacement which replaces a soft-seat valve with a soft-seat valve.
The valves will have the same operators.
Replacement of Gase valves will require some valve operator changes to provide :orrect direction for valve closure.
Limit switches will be adjusted accordingly.
The valve vendor will supply the new torque settings to account-for the different valve characteristics.
These are QA Condition 1 valves.
RN47A and RN48B separate the RN essential supply header trains in the auxiliary building.
RN49A and RN50B isolate the nonessential supply header from the essential supply header.
RN67A and RN698 isolate the essential supply header in the auxiliary building from the main supply lines.
All of these valves are normally open.
RN47A, RN48B, RN49A, and RN50B close on containment high high pressure signal.
I RN67A and RN69B receive a signal to open upon initiation of safety injection.
The function of these valves will not be impacted by these NSMs.
The valve closure times and fail-t:fe positions remain the same.
These changes do not impact t; piping analysis.
These valves are being replaced by more reliable soft-seat valves because the currently installed soft-seat valves are experiencing leakage problems.
Safety Evaluation:
Replacement of these valves by this modification represents no change to the' reliability of these valves to operate as designed.
In fact, these valve replacements provide a more reliable design against leakage.
Since the RN system is a mitigating system and not an accident initiator, this modification does not increase the probability of any accidents as evaluated in the FSAR.
Some valve operator changes will be made and limit switches will be adjusted accordingly, but these changes will not create any new failure modes for these valves.
Since no new failure modes will be created, this modification will not increase the probability of any malfunction of equipment important to safety which was previously evaluated in the FSAR.
The modification will not create the possibility of any new accidents or malfunctions of equipment important to safety by the minor changes to be made.
No changes were made to the function of the valves during accident sequences, therefore the consequences of an accident or malfunction of equipment important to safety will not be increased.
Since the function of the valves will not be impacted, this modification will not reduce the margin of safety as addressed in the Technical Specifications.
The FSAR has been reviewed and is not impacted.
Based on these considerations, no unreviewed safety questions are judged to be involved or created by these modifications.
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s CN-11004 Descr.iption s:
These modifications' provide for_the addition of f
CN-20395 drains tol give the, Nuclear Service Water System (RN) return y
L LCN-050393 headers sufficient draining capacity to support valve replacements within 72 : hour- (Technical Specification)' time 1 windows.
This modification affects FSAR Figure 9.2.1-3.
Safety Evaluation: ' The..added' drains will be only. used during maintenance activities and will not affect the operation'of the-l RN system.
The consequences or p obability' of an accident E
previously evaluated in the FSAR are not increased.
Nothing.
new to the system'is added that would create the possibility of.
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an accident which is.different than.any already~ evaluated in-the : FSAR.
No qualified equipment has been degraded and no common mode ' failures have been introduced.
Therefore, no possibility of malfunction' of equipment important to safety different. than any already evaluated. in. the FSAR has been created.
This modification' does -not involve any unreviewed -
safety' considerations.
CN-11018
Description:
This modification upgrades instrumentation:for shell side. nuclear service water (RN) flow through the-containment spray (NS) heat exchangers.
Alarms will be add &d in the control room for.high and. low flow, and indicators will be ~a'dded to provide operators with information' to dr:termine when ' adequate flow exists.
This use code 9 instrumentation will use existing flow elements.
The information-provided by this instrumentation will insure that these NS heat exchangers are able to fulfill their function ' by preventing the RN -flow rate from becoming great
- enough to create ' tube vibration' and damaging the NS heat exchanger tubes.
This instrumentation will be provided with IE power.
Safety Evaluation:
This modification will insure the. ability of the RN/NS heat exchangers to fulfi1T their function by supplying.the operators with morei reliable information.
The accuracy of the instrumentation was considered in the determination of the setpoints involved.
These setpoints are consistent with the plant accident analysis.
The low flow alarm is interlocked with the downstream EMO valve (RN148A and RN229B) in order to prevent nuisance alarms since no flow is the normal condition of this piping.
A potential failure mode due to tube vibration will be addressed by this modification.
' A seismic review of the control board has been conducted and Appendix R is considered.
The old non-safety flow instrumentation will be removed and optical isolators will prevent the-non-safety control room annunciators from faulting the safety-related inst rumentation.
Since the function of the heat exchanger -is not affected and the ' reliability of the information supplied by the instrumentation is increased, the probability and consequences of an accident or malfunction of equipment which was previously evaluated in the FSAR will not be increased.
Because the addition of this instrumentation 12
a p
Twill remove a potential failure mode and because the additional-instrumentation is ' more. reliable, the-possibility of an-accident-or malfunction of-equipment important to safety different than any already evaluated in the FSAR.will not. be.
?
c re a ted.-
This modification. will not affect the setpoints,
. safety limits,-or reactor core parameters, therefore the margin of. safety as defined. in the bases of the-technical specifications-will not be reduced.
Based on this discussion, L
no unreviewed-safety questions.are, Involved with this-
. modification.
u CN-11019.
==
Description:==
_The purpose of the modifications is to' downgrade CN-20409 the diesel generator sump pump from ASME Section III, class 3, to noncoded components.
The equipment' manufacturer involved with these components -has failed ' to renew their..N-stamp certification which has created a problem with procuring replacement items.
There are two pumps in the sump for each diesel generator.. These modifications affect FSAR Section 9.5.9.3.-
Safety Evaluation:
Th'e purpose of the' diesel generator room sump pump system.is to prevent : flooding 'of the diesel
. generators and remove normal drainage and leakage from equipment in that room.
It has been determined by. design engineering that it is not necessary for sump pumps in these rooms to. meet code requirements.
Removal of the code requirements will not impact.the reliability of the pumps because ~this equipment will -still be subject to.the-same testing and inspection criteria.
Electrically, no changes have been made to the system.
Because the function of the' pumps is not adversely affected and the pumps are subject to the same.
. testing'and inspection criteria, the probability of an accident or malfunction of ' equipment important to safety which was-previously evaluated in the FSAR will not be increased.
No new failure modes have been created therefore, the possibility of an accident or malfunction of equipment. important to safety
~
which is different than any already evaluated in the FSAR will not be created.. These sump pumps do not perform an accident mitigating function, therefore the consequences of an accident nr malfunction of equipment important to safety previously evaluated in the FSAR will not be increased.
There are no changes in setpoints or the reactor vessel core parameters:and no degradation of safety limits.
Equipment reliability will not be degraded so the margin of safety as defined in the bases to any technical specification'is not affected.
Based on thi discussion, no unreviewed safety questions are judged to be involved with this modification.
CN-11026
==
Description:==
These modifications provide flanges to existing CN-20416 spare Reactor Building mechanical penetrations M-234 and M-452 for both. units.
Each penetration involves a welded capped penetration in the RB wall and in the containment wall.
Flanges are to be added to both sides of the containment penetrations and to the annulus side of the Reactor Building 6B+
7, L
7
' t,:;'
L; < '
.(
penetrations. Also, a threaded' access hole is to be installed-on the3 annulus 1 side-'of the-containment penetrations for 34 pressure leak detection.
The flanged openings are to provide-access for outage Lactivities, such as steam generator shot
~
peening or sludge lancing.
These modifications affect FSAR Sections 3.8.2.1, 6.2.I', 6.2.3'and 6.2.6.
3
' Safety Evaluation:
This modification is QA Condition l' and -
safety related.
The affected penetrations are - existing
' penetrations that have pipe caps welded on them.
The.
b modification will add pipe flanges and a blind flange will be bolted to each pipe flange.
The access hole will be plugged during plant' operation. 'The containment penetrations will be g
pressure tested using the threaded access hole.
The y
modification. to these penetrations will not degrade the integrity of containment so the LOCA or fuel handling accident consequences will not be increased (Sections 15.6.5 and
'15.7.4).
This. modification does not initiate. any FSAR accidents and e
therefore will not increase the likelihood of any accidents previously evaluated in the FSAR or different than previously -
o evaluated in the FSAR.
Containment integrity will be maintained, ' therefore the consequences of any accidents will n_ot be increased.
Since..no new failure modes are postulated
.tne probability or consequence of a malfunction of equipment important to sa.'ety will also not be increased.
Since any leakage will exhaust thru the annulus ventilation ' system, no margins of safety as. defined in the Technical Specifications will be reduced.
There are no unreviewed safety questions associated with these y
modifications.
- CN-11042
==
Description:==
This modification replaces Component Cooling (KC) system BIF valves with a valve which has more reliable' design for isolation.
The valves to be replaced are 1KC50A and 1KC538.
These are the auxiliary building ncn-essential header isolation valves.
Both valves close on receipt of a high-high containment pressure signal or low-low refueling water storage tank levels following a safety injection signal.
The modification also adds a two inch drain line between the valves to facilitate leak testing and maintenance.
This modification affects FSAR Figure 9.2.2-1.
Safety Evaluation:
Replacement of these valves by this modification does not lessen the reliability of these valves to operate as designed.
These replacement valves provide a more reliable design against leakage.
Some valve operator changes will be made and limit switches will be adjusted accordingly, but these changes will not create any new failure modes for these valves.
Since no new failure modes are created, this modification will not create the possibility of any new accidents or malfunctions of equipment important to safety 14
which are different_ than any already evaluated in the FSAR.
Because these valves are at least as reliable as the previous valves, the probability of an accident or malfunction of equipment important to safety previously evaluated in the FSAR will not ' be' increased.
The function of these valves will remain the same, therefore the margin of safety as defined in the bases of the Technical Specifications will not be reduced.
The -function of. the valves during accident conditions will remain the same, so the consequences of an accident or malfunction of equipment important to safety which was previously evaluated in the FSAR will not be increased.
Based on these considerations, no unreviewed safety questions are judged to be involved or created by these modifications.
CN-11061
==
Description:==
These Unit 1 and Unit 2 modifications installed CN-20445 permanent branch connections on Spent Fuel Pool Cooling System (KF) piping.
The branch connections will allow the
' installation of temporary crossover piping.
These modifications allowed for cooling of the Unit 1 Fuel Pool during implementation of Nuclear Station Modifications CN-10639-and CN-11042.
These modifications affect FSAR Figure 9.1.3-1 and 9.2.2-3 and 9.2.3-1.
Safety Evaluation:
These changes are minor in nature and will not affect' the ability of the system to perform its ' intended function.
Stress Analysis has reviewed the piping changes.
Because the system will function in the same manner, the l
probability or consequences of an accident, or malfunction of equipment'previously evaluated in the FSAR will not be created and the margin of safety as defined in the plant's Technical Specifications is not affected by this modification.
There is no impact to the FSAR because of these changes.
Based on these considerations, no unreviewed safeoy questions are judged to be involved or created by these modifications.
CN-11071
==
Description:==
These modifications involve the installation of CN-20453 proximity probes on the main feedwater pumps and turbines, provision of a local cabinet to house proximitors, and replacement of associated control room monitors.
Proximity probes are installed outside the tilt pad bearings to monitor vibration and eccentricity and near each end of the shaft to monitor thrust position.
Connectors are also provided at each tilt pad bearing for new thermocouple.
Safety Evaluation:
These modifications involve a non-safety instrumentation system.
These modifications enhance the ability to monitor the condition of the main feedwater pumps l
and associated turbines, which are also non-safety.
Since it is strictly for monitoring purposes, the modification does not introduce any failure modes which would affect the operability of the pumps and turbines and is intended to improve their reliability by improving surveillance capabilities.
1 15
R' c
WW K
3The probabilityTof previously evaluated a:cidents: involving increases and decreases in secondary system.heaturemoval: is _not -
. increased j by the < modification '.because it' cannot cause Ea-
[i reduction-in the > :feedwater temperature, an - increase in
'feedwater flow, or' al1nss of feedwater..No other accident analyses are'affected by the modification and no.different type of accident is.possible.
L The modification does not ' affect : the design basis ~ of any-structure, system or component..Therefore, the modification does not increase the consequences of'any accident or equipment.
~
-malfunction and does.not' reduce the margin.of safety as defined-in the bases to any Technical Specifications.
These-modifications do not involve any unreviewed' safety:
. considerations.
CN-11114
==
Description:==
CN-11114 is a ' drawing change only to delete two requirements on the installation.of Rdf Model 21205 RTDs.
The requirements are:
- 1) that the braided stainless-steel jacket b
of the-RTD be covered in flexible metal conduit and 2).'that the, cable be supported within 15 inches of the RTD.
Safety Evaluation:- This modification does not increase the probability.of a malfunction of equipment or of an accident as d
' described-in the FSAR.
Margins of safety are not affected.
L The safety' function of the-RTD and its operation. are not
.affected.
This modification L does not involve any unreviewed safety considerations.
CN-11134 Desc.iption:
This change modified the first root valve of-the Reactor Coolant System (NC) loop B flow instrumentation (INCFT 5050L) so that a leak repair process can be performed.
This allows for repair of a body to bonnet joint leak..This modification affects FSAR Section E4.12 and 7.2.1.12.
Safety Evaluation:
An evaluation has determined that the hole drilled into the valve bonnet will not adversely affect the pressure boundary integrity of the root valve (Ref 4).
The sealant will be injected into a void around the body to bonnet joint, therefore no sealant should enter the reactor coolant system.
Operability of the flow instrumentation will be verified by the plant following completion of the leak repair.
The weight of the clamp assembly, which will remain after the injection process, has been considered and judged to have negligible impact on pipe stress analysis.
No new failure modes have been identified, therefore the probability of. any new accidents or new malfunction of equipment important to safety have not been increased.
The consequences of any accidents previously evaluated will not be increased since no accident mitigating systems have been adversely affected.
Since the flow instrumentation will be proven operable, the margin of safety as defined in the Technical Specifications will not be reduced.
This 11
a.
1
+
u,
$u k>
modification. doesi not involve any.unreviewed safety
. consideration.
L s~
CN-11143L
Description:
.These. modifications insta11 a tee in the line-1CN-2052L between the Nuclear Service Water (RN) and Spent Fuel, Cooling (KF) systems.
This connection from the RN to the KF systemLis the assured make-up; to 'the spent fuel pool.
A blind flange
.will be installed on the branch linesor the tee.
Removal.of the flange will' allow the branch line to1be used in RN system flushing for removal of clams' These modifications affect FSAR lF
. Figures 9.2.1-5 and 9.2.1-9.
Safety Evaluation:
Inst'a11ation of this tee in ' the assured '
make-upilinesito the spent fuel pool:will not_ degrade system flow.
Completion of this modification will provide a location t
to access piping for RN system flushin'g.
This. tee will be.
I insta11ed' between a normally closed' RN system valve and a locked - closed 'KFc system ~ valve.
This ' location will not functionally impact the RN or KF systems.
The stress analysis group has analyzed the addition of the branch line 'to insure -
the piping will fulfill:its function under seismic' conditions.
Since the function of the assured make-up line to the spent fuel pool will not be adversely affected, the probability orf
- consequences of an accident or malfunction off equipment
.important to safety, which 'was previously evaluated in the v
FSAR,'will not be increased. sThe possibility:of an accident or.
malfunction of equipment important to safety which-is different than ' any already evaluated in-the FSAR will' not be' created because no new failure modes are created.
The safety limits, set points, and reactor vessel core parameters are unaffected.
-by this modification, therefore the margin of safety as defined.
-in z the baser, to any technical specification is not reduced.
Based on this discussion,. no unreviewed safety questions.are judged to be_. involved with.these modifications.
CN-11151
==
Description:==
This modification adds nitrogen bottles, including a manifold regulating valve with an integral relief valve, tubing and a cabinet mounted shuttle? valve to the 1A Diesel Generator Starting Air System (VG).
The nitrogen serves as the non-assured primary source for the engine control panel 1A pneumatic instrumentation.
The VG system is still available as prior to implementation of the changes.
This modification I
affects FSAR Figures 9.5.6-1 and 9.5.6-2.
Safety Evaluation:
Diesel Generator 1A control air for the pneumatic shutdown logic system has been of poor quality due to its moisture content.
Use of nitrogen as the primary source of control air eliminates moisture and reduces pneumatic component failures.
The VG system is still available to provide control
' air.
The regulating valve and nitrogen bottles are seismically qualified.
This modification does not introduce any unreviewed safety consideration.
1Z
4 Q
(.
+
3..
P lCN-20017
==
Description:==
This modification concerns the addition of two:
n complete trains of.. neutron : flux instrumentation.
This
[~
instrumentation is known' as the Boron. Dilution Mitigation System (BDMS).
L r
u[
Main Control Boards, the SSF, and the ASP.
All of. this This instrumentation will provide outputs for displays on;the r equipment, with' the exception of the SSF loop, will' be QA1 and L
fully qualified for PAMS use. Also, Appendix R separation will.
p be maintained between Trains for' the. equipment 'and cabling-from L'
the detectors to-the signal processing electronics /and between the~ cable to the SSF and any train B equipment or cables. -This' H,,
modification'affects FSAR Section 7.6-24.
Safety Evaluation:
This instrumentation will be. Independent of the existing neutron flux instrumentation ~and will not affect o
,the existing system in any way. The BDMS'will not increase the initiation. frequency of any accidents described in the FSAR.
Plant operation should be more reliable, particularly.in the modes where the BDMS provides automatic protection (Modes 3-6),
The RCS should actually have a decreased probabil_ity of a boron
' dilution ' event / accident ever reaching criticality because of the increased reliability of a redundant. safety. grade automatic system compared to a dependence-of " human interaction" to detect and stop the flow of diluted borated water into the RCS.
l
.The consequences of accidents previously evaluated in the FSAR are not increased.
There are no new accidents which can be identified different than'those already eva'luated in the FSAR.
.No new malfunctions of equipment can be identified.
The margin of safety will not be' reduced by installing this system,' nor is-it necessarily dependent on the operability of this system.
There are no unreviewed safety questions resulting from the implementation of this modification.
CN-20019
==
Description:==
Current design of the Component Cooling System (KC)- system non-essential header for the auxiliary building provides isolation of this header on receipt of an Ss signal.
This modification alters the control circuitry of isolation valves ~ 2KCIA, 2KC2B, 2KC50A and 2KC53B such that their automatic close operation will be initiated on an Sp signal or an Ss signal coincident with a low-low FWST level.
Monttoring lights on 2MD4 for these four valves are being regrouped within j
the same panel to the Sp operated group instead of the Ss g roup.-
t:
Safety Evaluation:
The modification is needed in order to make the units similar.
This modification decreases the probability 18
(I
'f i
1 Il -
g^
)
Lof-KC;pumpLrunout..No unreviewed. safety questions are judged
-to be' created ~or involved as a result-of this modification.
LCN-20119-
==
Description:==
.This modification changes Main Steam Bypass to T
condenser. valve,15B29, to pipec specification 900.4 Class G.
- This' change ; allows valve ISB29 tof be blind flanged when disconnected. from ~ the Condenser. Steam Air Ejector Vacuum System.- This modification _affects FSAR Figure-10.4.2-1.
Safety Evaluation:. A constant' flow 'of steam and condensate
. leaks byivalve ISB29.
This modification corrects a personnel l safety hazard.
The_ change does not. adversely impact any safety or. non-sa fety ' system; This modification does.not involve any unreviewed safety question.
CN-20125-
==
Description:==
-This Unit 2 modification to the Solid State Protection-System manually reset the Main Steam Isolation-Signal due to low 'steamline pressure or Hi-Hi containment-pressure while signal is still present.
This will enable the D
, plant to cooldown by remote operation from the control room by either steaming to the condenser or to the atmosphere following
.c
.a small-break loss of coolant accident'or main steam line' break-
. inside containment, This modification affects FSAR Figures.
.7.2.1-1,.10.3.2-1 and 10.3.2-4.
-)
Safety Evaluation:
If a second valid signal appears after the finitiating. signal clears, this modification would not prevent a main steam isolation ~ from occurring..This modification has been determined:
- 1) Not to increase the initiating frequencies o
1 of any accident previously evaluated in the FSAR; and 2) Not to increase the consequences of any accident previously evaluated
.in: the FSAR; and 3) Not to incre'ase the probability or consequences of malfunction of equipment important to safety previously evaluated in' the FSAR; and 4) Not to.. reduce the margin of safety as" defined in the FSAR.
This modification
-does.not pose any unreviewed safety question.
CN-20180
==
Description:==
This Unit 2 modification provided for the installation of a permanent sight glass to the Reactor Coolant (NC) System.
The sight glass allows for the level measurements between the RVLIS connection. on NC hot leg 2C and the low pressure tap for 2 NCLT6450.
This sight glass is to be valved into the. NC piping only during draining operations on the NC system.
This modification affects FSAR Figures 5.1-1 and 5.1-2.
Safety Evaluation:
Lack of a_ arate and reliable level indication on the NC System for determining level while draining below 12% level has caused loss of suction on both trains of the residual heat removal system, rendering them inoperable and creating a Technical Specification violation.
There are no failure modes for this modification which could
]
l-result in the degradation of any equipment important to safety.
j 19 m_2.m__
____h.______.
4'
.This modification :will not increase the initiation-of any (accident or equipment malfunctions analyzed ~ 1n the. FSAR,- and 4
will. not result cin the' creation of any new accidents.
The I
initial conditions of the' reactor coolant system and core will.
- not be affected by this NSM, and the ability to. mitigate accidents will; be -unaffected.
This modification' will not
. reduce.the plant margin of safety as defined in the bases to Le 1
the Technical: Specifications.
4
'This modification does not involve any ' unreviewed safety w
question.
lCN-20208
-Description:
This modification.provides for the reinforcement-
.of supports 'and elongation of bolt holes for thermal expansion of Starting Air Manifold piping.
Safety '. Evaluation:
This modification provides for the validation of. the design review for the Starting Air manifold piping, Component No. 02-441-A.
This modification does not U
adversely impact any safety system This modification does not involve'any unreviewed' safety consideration.
CN-20265
Description:
_This modification revises the Unit-2 Boric Acid Tank level instrument. scheme by utilizing a reference leg-type installation which. indicates. properly under pressurized' conditions.
This modification affects FSAR Figure 9.3.4-5.
Safety Evaluation:
.This ' modification allows ' for accurate indication of 'the Boric Acid Tank level.
This modification does not' involve.any changes'to the process control cabinets.
' This modification does not. involve any unreviewed. safety
' question.
.CN-20303'
==
Description:==
' This modification installs temporary level instrumentation off-of alternate steam generator level taps on one SG to monitor indicated level response at these alternate taps.
This ' data will be' used to determine if a level tap change can improve steam generator level control.
l 1:
Safety Evaluation:
The modification involves the temporary installation of level instrumentation on one'of the four steam l'..
generators (S/Gs) of Catawba Unit 2.
The installation utilizes L
existing level taps which are presently plugged.
The instrumentation will serve no control function, no safety function, and will not be used by the control room as an l
alternate S/G 1evel indication. The data which is provided by ll the new instruments was used only as comparative data to-determine whether use of the lower level taps will actually improve S/G 1evel control.
The temporary level instrumentation interfaces with the steam generator at the existing lower taps and with the plant computer, with the capability to record data on the transient monitor.
It ties into existing impulse lines L
coming off the upper tap locations but there is no functional interface with or modification 'or existing S/G 1evel
_20
l instrumentation.
Neither will there be any interface with l
engineered safeguards nor any other control or protection systems.
No accidents or equipment malfunctions will be affected or created, and no margins of safety will be affected.
This modification does not involve cny unreviewed safety question.
CN-20316
==
Description:==
This Unit 2 modification involved the installation of temperature elements upstream of check valves 2CA37.and 2CA65 to provide computer indication and alarms on increasing temperature indicating backleakage through the check valves.
This modification affects FSAR Table 10.4.9-4.
Safety Evaluation:
2CA37 and 2CA65 are in the discharge lines from the turbine-driven auxiliary feedwater pump (TDCAP) to S/Gs D and A, respectively.
The thermocouple are of the strap-on type.
These thermocouple involve no pressure
. boundary penetrations and are not in contact with the flowing-water.
Therefore, the integrity or performance of the system is unaffected by this modification.
Since there is no interaction with the CA system and no adverse interactions with other systems, the probability of previously analyzed accidents and malfunctions of equipment important to safety is not increased and the possibility of new accidents and equipment malfunctions is not created.
The modification does not affect the performance or operational characteristics of any system and so does not reduce the margin of safety as defined in the bases to. technical specifications.
The strap-cn thermocouple provide a safety and reliable method for determining whether check valve backleakage is occurring and thus can help to prevent subsequent damage to equipment, This assures that equipment will be able to perform as designed when called upon to do so, and the modification is designed such that single failures affect only one train of auxiliary feedwater.
Therefore, the consequences of accidents and malfunctions of equipment important to safety are not increased.
This modification does not involve any unreviewed safety question.
CN-20328
==
Description:==
This change modifies control circuit wiring on 2NI-9A, 108, 1008, 1830, 162A, 173A, 1788, 184B, 185A, 2NV-89A, 91B, 188A, 189B, 252A, 253B, 312A, and 314B to provide " limit actuated" torque switch bypass contacts which can be adjusted independent of indication or interlocks.
Safety Evaluation: This modification is being implemented as a result of the findings in NRC IEB 85-03, "MOV Common Mode Failures During Plant Transients Due to Improper Switch Settings".
The subject valve operators have " limit switch" actuated
" torque bypass switch" contacts.
To assure that these valves open fully, the " torque bypass switch" will defeat the torque switch for a much longer opening stroke travel ~ 0 to 25% open.
21
l
~In:this manner,,the' maximum motor torque-will unseat and open the. valve against full flow and Ap without allowing the torque switch to operate until the-valve is ~ 25% open.. Then, if for-
- some reason an unusually high~ torque is measured,. the torque -
switch could trip off the motor, protecting the valve but not
. leaving it closed when it should be open.. The torque switch protects the valve when opening by tripping the motor when the 4
back seat'is. reached due-to. increased torque. (resistance).
Functionally these valves will operate. identically to the' way they-presently operate.
With the new control' circuit wiring and"" torque bypass switch" setting,'the valves should be more celiable in attaining-the desired positions witho't letting the u
torque. switch protection device interfere.
Also, other indications and interlocks associated with valve operation, 4
position etc., will not be affected by these changes.
- Accordingly, this modification will have no effect on the probability, consequences or " possibility of new" accidents evaluated. in the FSAR.
Nor will it affect the probability, consequences s or possibility oi malfunctions of equipment important to safety evaluated in the' FSAR.
The margin of safety definedLin the bases.of the Tech. Specs. is unaffected.
This modification does not involve any unreviewed safety
. question.
CN-20457
Description:
This modification removes vendor. supplied pressure gauges from the present locations on-Lube' 011 Filters -
2A and. 2B and' Pre-Lube 011 Filters 2A and 28.
It specifies instrumentation, piping,. test tees, isolation valves, and Duke supplied pressure.. gauges. to be installed next to filters.
Present pressure. gauge location on Lube Oil Filter requires draining-oil, from filter to service the pressure gauge.
New configuration will facilitate calibration and maintenance 'of pressure gauges without draining the oil.
Safety Evaluation:
No safety system will be degraded as.a result of this modification.
No changes or impact to FSAR or Technical Specifications will result from the implementation of this modification.
Therefore, no unreviewed safety questions are created or involved as a result of this modification.
CN-20494
==
Description:==
This modification replaces 2NCRD5850 and 2NCRD5870 which are reactor coolant wide range resistance temperature detectors.
These detectors supply signals to wide range temperature recorders located in the control room.
This
]
information is used by the operators to control the coolant temperature during startup, shutdown and Condition II, III and L.
IV Events.
These Conax detectors will replace the RDF
]
E detectors which are presently used at Catawba Nuclear Station.
The change in manufacturer is due solely to supply problems.
Safety' Evaluation:
Since the reactor coolant system and the function of the RTD's are not adversely affected by this 1
22
)
_ _ _ _ = _ - - _ = _ - - _ - ____-
__--__N
lh W
replacement the probability or: consequence of an.. accident
(~
- previously evaluated in the FSAR is not' increased nor is the probability
- or consequence 'of a L malfunction. of equipment important. to: safety-previously evaluated in -the FSAR increased.
The nature of these RTD's as' measuring devices and. the fact-that the reactor coolant ~ system. is not'. adversely affected g
preclude.their-potential role as event initiators.
Therefore, the possibility of an unanalyzed accident is not created by'the
-replacement of 2NCRD5850 and 2NCRD5870.
This'NSM'will have no adverse impact on the'thermowell or any other ' piece of equipment; therefore, it does not create the possibility of an'unanalyzed malfunction of equipment important to-safety..
~
Operating parameters, safety limits and set points will remain the same-following the implementation of this NSM as' they were prior to'its implementation.-
Therefore, the margin of. safety-as defined-in the bases to any Technical Specification is not reduced by'this NSM.
Based on the above analysis there are no unreviewed safety questions involved with this modification.
LCN-20503
==
Description:==
This modification injects sealant r.;aterial in the gasket area of the' steam generator manway for steam generator 2A.
This is done by drilling. holes circumferential1y around
.the manway cover-and injecting the sealant material at these.
locations.
These sealant material injections should stop steam
' leaks 'around the manway cover. gasket.
~~
- Safety Evaluation:
This modification only affects the steam generators shell and. does not create any new failure modes.
The ' probability and consequences of any malfunction are not increased.
This modification does not involve 'any unreviewed safety considerations.
'CN-50016
==
Description:==
This change involves the addition of a Makeup Demineralized Water System (YM) supply pump recirculation path through the YM demineralizers.
This recirculation path must be provided through the demineralizers to prevent either a bed channeling problem during periods of low flow or high conductivity alarm on YM af ter the bed has been in a no flow situation.. This recirculation path is to assure that the minimum flow through the YM demineralized will be no less than 125 gpm. -This modification involves FSAR Figures 9.2.3-1 and 9.2.3-4.
Safety Evaluation:
The YM system is not required for maintenance of plant safety in the event of an accident.
Only the containment isolation valves and the piping connecting the valves are safety class.
This modification does not affect the safety class portion of the YM system.
The affected parts are 23 e
m 3
x J
h E
located ~ entirely..within the Service ~ Building which isLa 'non-QA p
structure.
This' modification does not adversely Laffect any.
- sa fe ty ' system. LThis change does not' involve any unreviewed -
c safety consideration CN-50025
==
Description:==
This modification provides for the construction
- of 'a temporary waste' storage facility.
This allows for~the J
temporary storage 'of waste ' that ' cannot be disposed of
'immediately.
This modification'affects FSAR-Sect 1on-9.5.1-6.
Safety Evaluation:'- This building is being. erected to store m
. hazardous waste safety until it can be shipped off site.
It is a non-QA structure.
Adequate fire protection is provided by a
.non-QA sprinkler system and any wall penetrations are' sealed with RTV foam.
Concrete curbing will.contain any spillage and a' sloped. floor ~ will direct it to a trench which drains to a sump.
Any possihie releases of chemicals or smoke will not affect control ooom habitability.
This structure performs no safety.-- functica.nor will 'it' affect any safety related structures.. system or components.
This modification does not involve any unreviewed safety consideration.
CN-50055
Description:
This modification provides Makeup Demineralized
- Water System (YM) supply lines to the Auxiliary Building decontamination ' sinks such that Demineralized Water is s
available for both sink use and. local ' header supply.
This modification affects FSAR Figures 9.2.3-2, and 9.2.3-6.
Safety Evaluation:
Makeup Demineralized Water (system YM) is currently supplied at the decontamination sinks in each Aux.
Building for both sink use and local use (for example filling janitorial buckets).
A hose is used for directing water where needed.
This modification would add a permanent 3/4" line and.
manual' isolation valve for local use, particularly filling roli-around Janitorial buckets at 14 decon. sinks.
The YM-supply header in each case is capable of' isolation such that the installation of this change can be made at any time.
The new piping and valves have ' design parameters compatible with
.the'YM supply to the sinks.
The system is manually operated locally which should limit excessive flow to drains from spills.
Auxiliary Building floor drains are part of the Floor Drain Tank (FD1) Subsystem of the Liquid Radwaste System (WL).
Liquids are potentially radioactive, but are generally suit-able for discharge without treatment.
Floor drain headers are routed to the various tanks and sumps of the WL system in a manner designed to minimize the liquid and gaseous radioactive releases.
The Makeup Demineralized ' Water System is not required for maintenance of plant safety in the event of an accident and plays' no role in initiating or mitigating design basis accidents.
Seismic initiated flooding is not a concern because the new lines are short runs of 3/4" pipe.
Based on the above, the probability or consequences of an accident previously
evaluated in the FSAR will not be increased and no new accident different than any already evaluated in the FSAR will be created.
Since no equipment is adversely affected, the pro-bability or consequences of a malfunction of equipment impor-tant to safety previously evaluated in the FSAR will not be increased and there is no possibility of malfunctions of equipment important to safety different than already evaluated in the FSAR.
No margin of-safety as defined in the bases to any Technical Specification is reduced.
There are no un-reviewed safety questions associated with this NSM.
CN-50062
==
Description:==
This change modifies temporary pressure test connections and provides for the installation of an annubar and flow gauges on the low pressure service water (RL) system side of the Administration Building and Computer Room Chilled Water Systems Chillers.
This modification affects FSAR Figure 9.2.8-4.
Safety Evaluation:
Instruments added per this modification are to be used to gather data to determine the friction and fouling characteristics of raw water pipe.
Computer modeling codes for the Nuclear Service Water System will be improved based in this data.
This modification does not affect any QA condition structures, systems or components.
This modification does not involve any unreviewed safety consideration.
CN-50065
==
Description:==
This modification provides for the construction of a performance calibration lab and storage area in the Service Building.
This modification affects FSAR Figures 9.2.3-1 and 9.3.1-1.
Safety Evaluation:
This modification is necessary to allow for proper calibration of performance and secondary side instruments.
No safety system will be degraded and no functional change will occur due to this modification.
This modification does not involve any unreviewed safety consideration.
CN-50110
==
Description:==
This modificat. ion adds level instrumentation upstream of waste gas headed drain valves 1WG339, 340, 345, thru 351 to detect the presence of liquid in the drain lines.
This modification affects FSAR Figure 11.3.2-4.
Safety Evaluation:
No safety system will be degraded by implementation of this modification.
No functional changes to any systems are to be made.
This modification will allow the drain header to function more efficiently.
No unreviewed safety question is judged to be created or involved as a result of this modification.
CN-50175
==
Description:==
This change modifies the radwaste transfer pump so that it will operate under the bead resin load.
This modification affects FSAR Figures 11.4.2-4 and 9.2.3-2.
25 l
t Safety Evaluation:
This modification provides additional flexibility and resolves problems discovered during u
preoperational testing of Catawba's Solid Radwaste System.
No safety systems are degraded as a result of this change.
This modification does not involve.any unreviewed safety considerations.
CN-50178
==
Description:==
This modification replaces the Process Equipment stainless steel tank with a process Equipment fiberglass tank.
Stainless still' tubing is also replaced with plastic tubing.
Stainless steel valves are also replaced with brass or PVC valves.
This modification affects FSAR Figure 9.4.4-2.
Safety Evaluation:
The subject NSM is to change out materials in the Filtered Water System (YF) coagulant process equipment including the coagulant mixing and storage tank, piping, and val ve s..
In compliance with public health standards, a back flow.
preventer is provided between the Drinking Water System supply and the filtered water supply to other station equipment.
The Filtered and Drinking Water Systems do not perform any safety function.
The only interconnections between the Fiitered and Drinking Water Systems and other systems having the potential for containing any radioactive material occur in the Makeup Demineralized Water System.
A reduced pressure-principal backflow preventer installed between the filtered water tank riser and the Makeup Demineralized Water System supply line prevents any'possible backflow.
This portion of the YF system does not have a QA condition associated with it; piping is class G or H.
No equipment important to safety will be degraded during design basis events as a result of this change.
Therefore, the modification has no safety significance.
This modification does not involve an unreviewed safety consideration.
CN-50180
==
Description:==
These modifications provide for the construction CN-50292 and tie-in of the Monitor Tank System.
The Monitor Tank System is designed to provide additional processing capability to the Liquid Waste (WL) System and the Steam Generator Drain Tanks.
It also provides condensate powdex processing capability and additional monitor tank capability.
These modifications affect FSAR Sections 11.2 and 11.6, Table 11.6.2-1, and Figures 2.4.1.1-4, 9.2.3.-1, 9.2.3-6, 9.2.4-3, 9.3.1-1, 9.3.1-7, 10.4.7-8, 10.4.7-9, 11.2.2-9A, 11.2.2-12, 11.2.2-16, 11.2.2-19, and 11.6.2-1 thru 11.6.2-3.
Safety Evaluation:
as an extension of the WL System, the Monitor Tank Building (MTB) and its associated equipment and components are not related to any FSAR accident analysis except those dealing with radioactive releases due to liquid tank failures.
The consequences of a Liquid tank failure within the MTB are much less severe than the consequences of the Refueling Water Storage Tank failure already evaluated in the FSAR.
26
gn ;...
l 1
Therefore,n the probability and : consequences of an accident
. previously evaluated in the FSAR will.not be' increased.
Since-the only accidents-postulated for the MTB are a system leak or:
tank failure, the possibility of an accident of a different typeLthen - any previously evaluated in the FSAR will not be-
= created. 'The MTB-and-its associated equipment and components are not related to any margin of safety and will not: affect any parameter associated with any margin of. safety..
The MTB does not involve any-unreviewed safety considerations.
CN-50194
==
Description:==
1This modification provides for the replacement of the existing chilled water coil in Counting Room HVAC with a DX Coil-and. air cooled condensing' unit. -Blackout power supply is provided to the equipment.
Control modifications separateLthe Counting ' Room HVAC from other Auxiliary Building Ventilation Systems. This modification affects FSAR Section 9.4.3.2-5.
Safety Evaluation:
This modification improves the~ reliability of the' Counting Room HVAC by eliminating-its dependency-in the L_ '
. Radwaste Area Chilled Water System. This modification does not adversely affect any safety system.
The system is not safety related and y the possibility for indirect and secondary interaction does not exist. This modification does not involve
- any unreviewed safety considerations.
CN-50208 '
==
Description:==
This modification provided for the installation of a centrifugal type air compressor to provide Instrument Air (VI) and Station Air (VS).
The older reciprocal compressors are. to' be~ used as back-ups.
This. modification affects' FSAR Section 9.3.1, FSAR Table 9.3.1-1, and Figures 9.3.1-1 thru 9.3.1-8.
Safety Evaluation:
Based on experience at Lother Duke power plants including McGuire, centrifugal air compressors are more
- reliable than reciprocating compressors requiring significantly less' maintenance.and' downtime.
The compressor will be located in the Service Building and is non-safety related.
The centrifugal compressor will operate as base load to supply the normal requirements of the VI and VS systems with the presently installed VI and VS' compressors utilized for standby.
This will increase compressed air capacity as well as provide greater flexibility for necessary maintenance.
If the system demand exceeds the centrifugal compressor capacity, low VI header pressure will initiate a signal to start additional standby compressors as demand dictates.
If the VI pressure drops below a low set pressure, a self-contained back pressure k
control valve will close to terminate air supply to the VS system in order to maintain air supply to the VI system.
Overpressure protection has been considered.
The addition of added capacity and reliability will decrease the possibility of creation of an accident which is different than any already evaluated in the FSAR.
This is due to the 21 4
_m
's 4
1
. compressed air. system's ; higher probability of operating. as -
_g
' designed.
W
. The probability or consequences of a malfunction.of equipment
~
~important to-safety' previously evaluated in the FSAR will not -
be: increased.
Since no newl failure modes have been identified, m
z the' possibility of a malfunction of-equipment important'.to safety different than any'already evaluated in the FSAR~ will not be; created.
Based on: the compressed air system functioning the same as before and more reliably, the margin of,' safety as 3
3 defined 11n the-bases to any Technical' Specification'will not be reduced.
This modification does not involve any unreviewed
-safety. question.
CN-50226
==
Description:==
- An~ overflow line was provided on the Spent Resin
. Storage Tank (SRST) AJvent line.
It. ties off of the vent-line
. upstream of IWS11 which remains normally closed.
The overflow ties in to the line'1eading to WEFT Sump B upstream of valve IWS39..This' valve'will become normally'open and serve as-the vent path for;the tank.
r A similar overflow setup is 'provided for SRST B.
The tie-off on the. vent fline occurs upstream of IWS32.
The overflow.
ties-in upstream of IWS46 which will change to.normally 'open -
operation' and serve as a vent path for the tank.
This modification affects FSAR Figures 11.4.2-1,
- 11. 4'. 2-2 a nd -
11.2.2-4.
+
. Safety Evaluation:. The modification reduces the possibility of tank' overflow entering the VA system ductwork, and still allows the tanks to be charged with nitrogen:in a similar manner as before.
When charging the tanks with nitrogen to loosen compacted resin,' the valves 1WS39 and '1WS46 will be closed.
Valves 1WS11 and 1WS32 will be opened to vent off excess nitrogen..The modification does not affect the operation of the VA system during normal operation except as mentioned above.
1 No accident scenario in Chapter 15:of the FSAR involves the SRST's or the WEFT sump; therefore, the probability or consequences of an accident previously evaluated in the FSAR is not increased.
The function of the SRST's is not changed, the Auxiliary Building Ventilation (VA) system operates as before, and the WEFT sumps are sized and qualified to handle the contaminated liquids expected from -these overflows.
The possibility of an accident different than any already evaluated 4
in the FSAR will not be created.
The SRST is not adversely affected and in fact the SRST and associated systems should operate better since the instrumentation readings will fluctuate less.
The WEFT sump pump and WEFT are designed for these types of flows.
No other equipment is affected and therefore the probability or consequences of a malfunction of equipment important to safety previously evaluated in the FSAR will not be increased.
No other equipment is affected, so the 28 a
l possibility of malfunction of equipment important to safety
+
i different than-any already evaluated in the FSAR will not be created.
No setpoints, operating parameters or safety limits are changed; therefore no margin of safety as defined in any Technical Specification is impacted or reduced.
i There are no unreviewed safety questions associated with this NSM.
I CN-50305
Description:
This modification provides for the upgrade of the Station Telephone System.
This modification affects FSAR Section 9.5.2.
Safety Evaluation:
This modification is not related to the cause of mitigation of any accident previously evaluated in the FSAR.
No equipment important to safety is involved.
Cable routes have been reviewed for Appendix R fire interaction U
concerns.
This modification does not -involve an unreviewed safety question.
CN-50334
==
Description:==
This modification provides a more reliable method of monitoring waste gas releases at the station.
The relocation of valve IWG160 downstream of radiation monitor EMF-50 prevents the release of radioactive gases detected by the monitor as appropriate.
A nitrogen purge was added L
upstream of IWG160 so that the discharge header can be purged back into the Waste Gas (WG) System.
A loop seal was added to the discharge line to prevent water from entering the WG system via the unit vent.
The WG system relief header was rerouted from upstream of EMF 50 to downstream of the new location of 1WG160.
The discharge flow gauge (0WGP5940) and the flow totalizer (0WGMT5940) were moved to a point where it can be seen from the WG system control panel.
All Waste Gas Decay Tank releases will be made from Tank "C".
This requires additional pipe routing from all tanks to Tank "C".
Dedicated sample lines'run from each tank for sampling.
A visual type flow meter was added to allow inspection for water in the sample header.
Rotameter OWGFS6170 was removed from the in line flow and replaced with a dif ferent type of instrumentation switch that performs the same function.
This modification affects FSAR Figures 11.3.2-2, 11.3.2-3, and 11.3.2-5.
Safety Evaluation:
A seismic interaction study was done for affected piping and it has been determined that no seismic interactions exist.
The racks containing the nitrogen bottles are seismically anchored.
The replacement switch for the rotameter is still controlled by EMF 50.
A high radiation signal on EMF 50 will terminate flow.
This modification is an operational enhancement.
The design bases of the system is not impacted even though the design of the system has been changed.
29
[w 1
[
ThisL modification has _QA Condition ~ 1_~ portions because of the flg a.
addition of new (redundant)1 isolation valves.
The rest of the modification is QA Condition 2.
No new release paths-have been created.
No new failure modes; have been created.
Adequate I"
tisolation 'of. the waste gas ; tanks has. between maintained..
Although ~the new method.of'_ release will be through Tanki"C",
l>
after the' gas to be released has transferred to' Tank "C" the tanks will again_be isolated and then the.re. lease,from Tank "C"
~
will be made.
At no time wil_1:the rupture of one tank' allow the release.of more than one tank's contents.
As such the FSAR p"
Chapter-15' accident analysis _for a waste. gas.tankirupture will
-not be impacted.
Waste. gas. plays no: role in any other Chapter-
_15. accident mitigation.
This modification does not involve an unreviewed safety question.
. CN-50346 '-
This modification replaces : the coagulant controllers and Streaming' Current. Detectors (SCD) in the Filtered Water System (YF) system.. With the'in" 11ation of_' Ultrasonic Cleaners for the.SCD's.were also instai,ed.
This modification also updates the YF. instruction 1 manual to as-built' condition.
This'
. modification.affects'FSAR Figure 9.2.4-1.
Safety Evaluation:
The new SCD's and ultrasonic cleaner will
. provide a more reliable reading to the. coagulant controller.
The : installation. of this modification _'will not. change the function or operation of the:YF system.
It will provide a more reliable and superior control of the coagulant 1in the YF
'sy stem.-
This ' modification involves ' no' unreviewed safety questions, h
I I
4 z
I 1
I
y 3
k i
CATAWBA NUCLEAR STATION' 7
..?,
SUMMARY
.OF EXEMPT VARIATION NOTICES COMPLETED UNDER 10 CFR 50.59 DURING 1988 n
'CE-0718
==
Description:==
'This change adds a Makeup Demineralized Water.
System (YM) supply to the Unit'2 S/G sodium analyzer to allow for proper calibration.
This change. affects FSAR Figures 1*
9.3.2-7 and 9.3.2-10.
- Safety Evaluation: 'This change will allow more accurate sodium 1 analyzer calibration which ~ will improve CT Lab operation.. and overall plant reliability...This change does not increase the probability or consequences.oflan' accident.previously evaluated h
.in the' FSAR 'nor does.it Lincrease the probability or consequences of L a malfunction of safety-related eq'uipment' as previously' evaluated in'the FSAR.
This change does not create any new accident scenarios or any new possibilities'of safety
-related, equipment malfunction different than those evaluated in the FSAR.
This change'will not reduce the margin of safety as defined' in any. Technical Specification bases.
This.
modification.does' not '-involve.any unreviewed safety consideration.
CE-0789?
-Description:
This modification replaces all limit switches on Containment Purge valves IVP7, 11, 17, and 20 with new Namco limit switches with date codes later than 02/06/80.
The actual date codes for the-limit switches ~ installed will be forwarded
~to DesignLEngineering to update the Environmental Qualification Reference Index after switches have been installed.;
iSafety Evaluation:
The. limit switches on' valves IVP7, IVP11, and IVP20 are'being replaced to comply with.10CFR50.49.
This will' ensure the equipment will perform as Jrequired when subjected to the environmental conditions present at the time it must function.
No. changes to~ the FSAR or Technical
. Specifications.
The. possibility,. probability, or consequences l-of accident or equipment' malfunction will not be increased.
This change does nct involve any unreviewed safety questions.
CE-0821
==
Description:==
This modification specifies a standard size bottle. and. expansion coils at the tubing connections, to eliminate problems' with variations in N2 tank sizes and to i
allow for seismic movements of N2 tanks.
l i.
Safety Evaluation:
This modification has.no effect on any l'
system structure or component important to safety.
This modification improves system operation.
This modification does H
not involve any unreviewed safety question.
j-CE-0940 Desc'iption:
This change revises the nameplates on the Standby Shutdoven Facility (SSF) that cobid possibly lead to an operator 11 w
w
- - - - - - - - - - = - - - - -
T f
1 u
error.
These-revision's will better define the function of the 4
L associated devices.
Safety = Evaluation:
The'. revision of nameplates on OCNSL0001' will. not create an unreviewed safety question or require a
]
_ change to'the Technical. Specifications.
^
l CE-1003:
==
Description:==
This modification involves the release ' of' il specifications. to'.the Station regarding usage of flexible o
-blanket type insulation.inside containment,
.l i
L
. Safety Evaluation:
The insulation system inside containment has'a:very passive role in plant operation and the performance:
of blanket: insulation is essentially, identical to that of the mirror ' insulation it replaces.
Blanket insulation - does not
' increase'the probability of previously evaluated accidents.
During normal' ' operation, blanket insulation is at least equivalent :to mirror insulation in heat retention capability and performs much better in areas where insulation removal and reinstallation has-taken place.
So blanket insulation does not.
present unnecessary challenges to equipment required for containment heat removal.
Following a LOCA, blanket insulation debris. has been shown to have a high probability of remaining within'the crane wall and thus not affecting the performance of ECCS equipment.
The blanket insulation will have no. adverse impact on any l
operating parameters and no effect on any safety limits or setpoints..It1 serves no role in. accident mitigation and will have no adverse impact on the performance of ECCS components,.
.since the impact on ' the NFSH margin has been evaluated and -
found to.be acceptably low.
Therefore, the margin of safety as-defined in' the bases to' any Technical Specifications is not reduced by replacing mirror insulation with blanket insulation.
- This modification does not involve any unreviewed safety consideration.
CE-1017
==
Description:==
This change adds trash catch screens to the bottom half of the Unit 1 and 2 cooling tower primary outlet screens.
Safety Evaluation:
This modification will prevent refuse caught on the screens from falling into the outlet when the screens are. removed. The modification will have no appreciable ef fect on Condenser Cooling Water System (RC) flow and will not increase Lthe probability of occurrence or severity of. con-sequences of' any accident or malfunction.
The modification creates no unreviewed safety questions and. requires no revision to Technical Specifications.
This change does not involve any unreviewed safety question.
CE-1075
==
Description:==
This variation notice was initiated to install a pressure gauge in the 1" vent line off the RMWST downstream of I
_3 2_
1 1
b 1
I p
valve'1NB248.
This gauge will be monitored periodically by ~
a Operations to provide indication of the tank - pressure
=
condition.
This change affects FSAR Figure 9.3.5-7.
4 Safety Evaluation:
This change does. not increase the probability or consequences of an accident previously evaluated in FSAR nor does it increase the probability or consequences of a - malfunction of safety related equipment as previously evaluated in the FSAR.
This change does not create any new accident scenarios or any new possibilities of safety related equipment malfunction different than those evaluated in FSAR.
This change will not reduce the margin of safety as defined in an Technical Specification bases.
This modification does not involve any unreviewed safety consideration.
CE-1152 Description.
This modification provides for' the deletion of piping downstream of valves 1KD29, 14, 31, 32, 1RN234, and 294.
Drain lines downstream of these valves otherwise have to be cut when the Diesel Generator engine jacket water coolers or oil coolers are disassembled.
This modification affects FSAR Figure 9.5.5-1.
Safety Evaluation:
This change is necessary to prevent cutting and rewelding piping.
This change does not affect safety related structures, systems, or components and no safety system will be degraded.
Deletion of piping downstream of drain valves 1RN234, IRN294, 1KD14,1KD29,1KD31, and 1KD32 will not create an unreviewed safety question or require a change to the Technical Specifications;
- likewise, elimination of drain header downstream of 1KD11 and 1KD26.
This change is being made to simplify disassembly of the D.G. lube oil cooler and the jacket water cooler.
CE-1308
==
Description:==
The old torque switch setting sheets are being superseded in response to NRC Bulletin 85-03.
The purpose of the new sheets is to ensure that switch settings on certain safety-related motor-operated valves are selected, set and maintained correctly to accommodate the maximum differential pressures expected on these valves during both normal and abnormal events within the design basis.
The new torque switch setting sheets ensure the valve will operate during normal and abnormal events by setting limitations on Total Thrust, Delta Thrust and packing Load.
These values are verified by the use of MOVAT's testing.
Safety Evaluation:
The probability or consequences of an accident previously evaluated, or different than already evaluated, will not be increased by this modification.
Nor will the probability of consequences of any equipment malfunction previously evaluated, or different than any already evaluated, in the FSAR be increased due to this modification.
3_3
b r
4 v
i.h r
- '.?.;G '
,1 i
N
~
The, margin:of-safety as_ defined in the basis to any Technical 1/
. Specification will.not be reduced by the~use of the new! torque
~ switch setting. sheets..The new torque switch settings' ensure adequate _' thrust output of the_ motor operators.
.This modification does not involve any unreviewed safety question.
CE-1316:
==
Description:==
This modificationnincreases the11ength of the
. trace < heat cable for a. section of piping from-the Boric Acid -
transfer pump to the Volume Control ' tank to include 1HV234-
?7 which directs flow for. Emergency Boration Flow line into-the l
Chemical and_ Volume Control System.
Valve INV234 is not. trace
-heated and Boron Crystal 11zation'causes frequent maintenance to open: Emergency Boration Flowpath.
This modification affects -
lFSAR Figure 9.3.4-8, Safety Evaluation: _ Changing the trace heat cables' for this-loop will not create an unreviewed. safety question or degrade 7the system innany manner.
The consequences'or probability of an accident or malfunction.of equipment previously evaluated in
.the FSAR'will'neither be increased or created.
The margin of safety as_ defined in the basis to Technical Specification will not be. reduced. 1This ' modification - does_ not involve any unreviewed safety consideration.
CE-1326
==
Description:==
This modification adds a drain to' the junct' ion boxes on e the MFWIV Actuators.
There has been a history of -
water'getting into the boxes'through cable connections to them ons the = top and sides.
This leakage'is due to damage' to the sealed cable entrances caused by persons using the cables as a
- climbing step.
The boxes, as is the entire valve' actuator, are EQ.
Safety Evaluation:
Because the only damaged seals are at_ the top of the' box, there is no means for the water to escape,.
which causes the water to accumulate and results in severe corrosion.
This corrosion and the water's presence:could cause the valve to close spuriously.
The drain will allow-any water that gets into the box to escape, thus eliminating the long term accumulation and most of its corrosive damage.
The drain
-is designed in such a way as '.o prevent steam leaks from blowing straight into the boxe;.
Also, because these boxes are not located in a LOCA environment and would not be exposed to excess pressure conditions, the drain does not degrade the Environmental Qualification of the actuator.
The drain design i ~
was reviewed and approved by the actuator's manufacturer for
?^-
installation.
By stopping the water's a.cumulation and L
corrosion, the valves' - reliability and proper operation are l
enhanced.
Thus, the consequences or probability of an accident l-or malfunction: of equipment previously evaluated in the FSAR will neither be increased nor created.
The margin of safety as
- defined in the basis to any of the Technical Specifications will not be reduced.
This modification does not involve any unreviewed safety question.
33 l.
u, m
.I ;
n
~CE-1340
==
Description:==
Instrument ICAFT5120 provides Aux. Feedwater flow to S/G D indica. tion to -the Control Room.
The present model,-
' ~
= Barton.764, has failed with no available replacements.
The l:
replacement is a Rosemount Model:1153DB5PA.
This-transmitter is a ' class < IE. transmitter. and -is ~ qualified to the. same standards'as the Barton 764.
Safety - Evaluation:
EQ considerations have not been reduced.
The: input and output characteristics of the Rosemount.
transmitter are the same as thel Barton' being replaced and H'
- therefore will function'without any, other system modifications being.needed..Thus, the consequences or probability of an accident or malfunction of-equipment' previously ' evaluated in the FSAR will neither be increased nor created.
The margin of safety as defined in the basis to any.of the Technical Specifications will not.be reduced.
This modification does not involve lany:unreviewed safety considerations.
CE-1369
==
Description:==
This modification removes valves with Item #
6J-238.and replace with 1" ITT Grinnel Item # CMV-269 valves.
Revise valve cross reference -to show both valves 2LD 116 and 2LD:118 with Item # CMV-269.
This modification-.affects FSAR.
i; Figure 9.5.7-2.
Safety Evaluation:
Replacing Globe Valves 2LD116 and 2LD118 (Item # 6J-238) with Ball Valves (Item #.CMV-269) will provide valves that-are capable of being disassembled and reassembled without the removal-and' replacement of a seal weld.
This will
- reduce the possibility of : damage to the valves during maintenance activities.
The' existing valves are Class G Non-Safety related, and were installed a's construction drains.
The replacement valves.will provide adequate isolation of the drain piping and will not affect'.-system operational requirements..Since these drain valves do not perform a safety function, the possibility of an accident will not be created, the probability or consequences of an accident be increased, nor will the' probability or consequences of a malfunction of equipment important to safety be increased by the addition of ball valves.
CE-1371 CE-1372
==
Description:==
These changes will allow the ENB Source and Intermediate Range detectors to have adequate space for water drainage within the housings.
The present detectors will be replaced with detectors having modified housings.
Safety Evaluation:
The detectors, inside the housings, will remain unaffected.
This ~ change is a result of a new Westinghouse design for the detector housings.
All detectors replacements will be QA-1 qualified and serve the same functions as the existing detectors.
Changes made by this VN will not degrade the excore detectors.
Materials, of the replacements, will be QA-1.
This modification does not involve any unreviewed safety question.
E
s if s
h E
'CE-1378
==
Description:==
This modification defeats the trips of the-hotwelll pumps on condenser hotwell emergency low level.
This
^
trip signal is initiated by-level. switches 1CMLS5460, ICMLS6960, and ICMLS6970.
Safety Evaluation:
These switches do not perform a safety related function and are not QA Condition.
The deletion of the trip will prevent spurious ' trips 'which have occurred at the other Duke plants and throughout the. industry.
These trips C
resulted. in significant damage to the feedwater and related systems.
The tripping of the hotwell pumps on emergency low level will now be a manual trip by the control, room operators.
However, this does not create a safety concern as per the FSAR, "any failure in the non safety class portions of the Condensate and Feedwater systems does not prevent safe shutdown of the w
reactor."
The worse case accident would be an operator's failure to trip the hotwell pump on emergency low level which would result in. damage to the pump.
However the course of events'that would lead.to-an emergency hotwell low level should have, lead the_ operators to trip the pumps ' and the unit via-operating procedures.
No new safety concerns are created and there are no unreviewed safety questions. The consequences and' probability of an accident or malfunction of equipment important to safety and previous.y evaluated in the FSAR will u
neither be increased nor created.
The margin of safety as defined in the basis to any of the Technical Specifications will - not be reduced.
This modification does not involve an unreviewed safety question.
CE-1379
==
Description:==
This modification defeats the trips of the hotwell emergency low level.
This trip signal is initiated by level switches 2CMLS5460, 2CMLS6960, and 2CMLS6970.
Safety Evaluation:
These switches do not perform a safety related function and are not QA Condition. The deletion of the trip will prevent spurious trips which have occurred at other Duke plants and throughout the industry.
These trips resulted in significant damage to the feedwater and related systems.
The tripping of the hotwell pumps on emergency lov level will now be a manual trip by the control room operators. However, this does not create a safety concern as per the FSAR, "any failure in the non-safety class portions of the condensate and feedwater systems does not prevent safe shutdown of the reactor."
The worse case accident would be an operator's 1
failure to trip the hotwell pump on emergency low level which would result in damage to the pump.
However, the course of events that would lead to an emergency hotwell low level should have lead the operators to trip the pumps and the unit via i
operating procedures.
No new safety concerns are created and
+
there are no unreviewed safety questions. The consequences and probability of an accident or malfunction of equipment 1
l important to safety and previously evaluated in the FSAR will
-j l
neither be increased nor created.
The margin of safety as defined in the basis to any of the Technical Specifications h
will not be reduced.
This modification does not involve an unreviewed safety question.
CE-1496
==
Description:==
This change depositions the operating elevation of the fully. withdrawn RCCA's from 228 steps to 230 steps so that the interfacing surfaces between the parked rods and the guide cards is shifted.
'RCCA overlap was adjusted from 113 to 114 steps.
Saf ty Evaluation:
Modifying the operating elevation of the parked RCCAs from 228 to 230 steps withdrawn does not pose any unreviewed safety questions or require and Technical Specifi-cation changes.
Operation of the fully withdrawn RCCAs at 231 steps does not create an unreviewed safety question or require a technical specification change provided that the mechanical withdrawal limit of all the RCCAs is verified to be 231 at 557 F.
The probability and consequences of the accidents and safety related equipment malfunctions that are evaluated in the existing FSAR are not increased.
In addition, the possibility of an accident or equipment malfunction which is different than-any previously evaluated in the FSAR is not created. Also, the margins of safety which are defined in the bases of the Tech-nical Specifications are not reduced.
Therefore, implementa-tion of RCCA axial repositioning by the thumbwheel and indivi-dual manual' adjustment methods is acceptable.
CE-1510
==
Description:==
This modification relocates 2RNTE5000 and 2RNTE5010 upstream of Tee branching to the NS Heat Exchangers.
This mod 1fication will allow daily monitoring of the RN Header temperature during the months of July, August, and September.
Safety Evaluation:
This relora 9:n will have a minimal affect on the flow in the RN Header due to the large diameter, 30 inches, of the pipe.
Accordingly, this modification will not increase the probability or consequences of an accident previously evaluated, or different than any already evaluated, in the FSAR.
Nor will it increase the probability or consequences on l
an equipment malfunction, previously evaluated, or different l
than any already evaluated, in the FSAR.
The margin of safety I
de ined in the bases of the Technical Specifications is f
unaffected.
An unreviewed safety question does not exist.
CE-1518
==
Description:==
This change replaces the pressurizer p0RV's existing die formed graphite packing with braided packing.
l Safety Evaluation:
This change does affect the function of the valves.
The change allows the valves to operate more smoothly.
This modification will not increase the probability or consequences of an accident, create the possibility of an accident, or increase the probability or consequences of a malfunction of equipment important to safety.
No unreviewed safety question is created by this modification.
32
p.
CE-1523-CE-1524
==
Description:==
These changes replaces the P3 shuttle valve in the D/G control panel, with a base mounted OR gate.
The y
pnuematic shuttle valve has proven to be unreliable and has caused numerous trips of the D/G.
This has been attributed to poor workmanship in its manufacture and material, and to poor design.
Safety Evaluation:
The base mounted OR gate is presently used l
in other applications in the D/G pnuematic controls and has proved to be reliable..It has been tested in the application of the P3 shuttle valve and has exhibited no pressure drop during signal transfer as was seen in the P3 shuttle valve.
The base mounted OR gate is approved by the vendor for use in this application, and is a Nuclear Safety qualified part.
The base, on which the OR gate mounts, has been recommended and Nuclear Safety qualified by IMO Delaval.
IMO Delaval also has approved the installation location and mounting of the base and OR gate.
See the attached IMO Delaval letter and drawing showing the mounting of.this.
The base has been qualified and provided by IMO Delaval.
The consequences or probability of an accident or malfunction of equipment previously evaluated in the FSAR will neither be increased nor created.
The margin of safety as defined in the basis to any of the Technical Specifications will not be reduced.
This change does not involve any unreviewed safety question.
CE-1580 CE-1581
==
Description:==
These changes will remove unqualified terminal blocks from Limitorque Actuators NIO54A, NIO658, NIO76A and NIO88B.
The motor power terminal block is unqualified in these valves and must be replaced with a qualified Raychem splice.
Safety Evaluation:
The probability or consequences of an accident previously evaluated, or different than already evaluated, will not be increased by this modification.
Nor will the probability or consequences of any equipment malfunction previously evaluated, or different than any already evaluated, in-the FSAR be increased due to this modification.
The margin of safety as defined in the basis to any Technical Specification will not be reduced by replacing the terminal block with a qualified Raychem splice.
The Raychem splice is qualified for in-containment use and the terminal block being removed is not.
This change does not involve any unreviewed safety question.
CE-1602 CE-1607
==
Description:==
These modifications change the type oil used in the CA turbine driven pump and the alarm setpoint for the bearing temperatures.
These changes have resulted from 1
constant high bearing temperature alarms which are caused by a l
l l-higher than expected ambient temperature at the pump.
This o
conclusion and the recommended changes were made by the pump manuN turer.
Safety Evaluation:
The new oil will withstand the higher temperature and provide adequate equipment protection.
The l
alarm setpoint change will be to 220 which is 10 below the manufacturer's recommended shutdown temperature.
Per the manufacturer's recommendation, these _ modifications are to be joint change.
Adequate work controls will be given to ensure that neither change is performed without the other.
The consequences or probability of an accident or malfunction of-equipment previously evaluated in the FSAR will neither be increased nor created.
The margin of safety as defined in the basis to any of the Technical Specifications will not be reduced.
This change will not create any unreviewed safety question.
CE-1622
==
Description:==
This modification changes the time delay associated with tripping the Condensate Booster Pumps on low suction pressure.
This is to allow the system more time to respond to transients that occur.
The current setting,' 5 sec.,
causes a premature trip of the pump which hinders the system's ability to correct disturbances.
CM disturbances of short duration can cause an unnecessary unit trip.
Safety Evaluation:
This change does not affect any safety related equipment or circuits.
This change does not create a safety concern as per the FSAR "any failure in the non-safety l
class portions of the Condensate and Feedwater system does not prevent safe shutdown of the reactor."
The consequences or probability of an accident or malfunction of equipment l
previously evaluated in the FSAR will neither be increased nor created.
The margin of safety as defined in the basis to any i
of the Technical Specifications will not be reduced.
This l
modification will not create an unreviewed safety question.
CE-1629
==
Description:==
This change will fill the termination enclosures l
for the flC system wide range hot and cold leg aux. shutdown panel indication loops and PAM indication loops RTD, with Scotchcast 9 Epoxy.
The enclosures involved are not environmentally qualified to prevent introduction of moisture 1
and radiation into the enclosures subsequently producing excessive errors on RTD signals.
Safety Evaluation:
The sealing of these enclosures will not increase the possibility or probability of an accident or j
consequences of an accident previously evaluated in the FSAR.
l The possibility of an accident different than any already l
evaluated in the FSAR will not be created.
The consequences or 1
probability of a malfunction of equipment previously evaluated I
in the FSAR will neither be increased nor created.
The margin of safety as defined in the basis to any of the Technical Specifications will not be reduced.
I 1
i b
' The sealing of these enclosures with the Scotchcast 9 Epoxy will ensure that these temperature loops will operate as o
designed by not allowing moisture or radiation to enter and degrading the involved RTD's.
This change does not involve any unreviewed safety questions.
CE-1643
==
Description:==
Due to interferences that prevented replacement of Pressurizer Heaters 47, 48, and 72, these penetrations will be plugged.
Heaters will be shortened to approximately 16 inches, inserted into the penetration and welded per standard heater installation procedure.
Heater 21 will be wired into the delta bank of group B along with 71 and 41 to ensure that a maximum number of heaters in group B are energized.
Safety Evaluation:
This modification will not affect the Pressurizer pressure boundary.
Implementation of this modifi-cation will not effect any FSAR evaluation.
Therefore, the probability or consequences of an accident previously evaluated in the F5AR will not be increased since this modification will not affect the function or integrity of the Pressurizer.
The probability or consequences of a malfunction of equipment important to safety previously evaluated in the FSAR will not be increased since the application of this modification will not affect the function of any equipment or systems addressed in the FSAR.
For the same reason, the possibility of an accident or malfunction of equipment important to safety which is different than already evaluated in the FSAR will not be created.
This modification does not involve any unreviewed safety consideration.
CE-1659
==
Description:==
This change removes the condensate drain plugs on the drive end of HSF-2A and HSF-2B to ensure the motor will have a means to breathe, equalize pressure, and drain condensate.
The Environmental Qualification of the fan motor is not affected by removing the plug.
Safety Evaluation:
The probability or consequences of an accident previously evaluated, or different than already evaluated, will not be increased by this modification.
Nor will the probability of consequences of any equipment malfunction previously evaluated, or different than any already evaluated, in the FSAR be increased due to this modification.
The margin of safety as defined in the basis to any Technical Specification will not be reduced by removing the drain plug.
Removing the plug will better ensure the fan motor will be able to breathe, drain condensate, and equalize pressure.
Thus by making this change, the intended operation of the affected equipment will not change.
This modification does not involve any unreviewed safety question.
CE-1806
==
Description:==
This modification will revise flow diagram CN-1574-1.0 by removing the note that indicates 1RN36A and 40
i L
l 1RN378 close. on Emergency Low Level in either RN pump pit.
i This change affects FSAR Figure 9.2.1-1.
I Safety Evaluation:
The current 1RN36A and 1RN37B interlocks do not jeopardize RN operability, but the overall RN logic is not clean.
It cannot be said, for example, that RN completely j
separates into its redundant. trains upon emergency low level, for a 4" crossover line could be open.
This modification will not increase the probability or consequences of an accident previously evaluated, or different than any already evaluated, in the FSAR.
Nor will it increase the probability or consequences on an equipment malfunction, l
previously evaluated, or.different than any already evaluated, l
in the FSAR.
The margin of safety as definedfin the bases of I
the Technical Specifications is unaffected.
An unreviewed safety question does not exist.
CE-1888
==
Description:==
This exempt change will replace the containment side flanges and bolting material for penetrations M234 and M452.
The penetration drawings,will also be revised to correct any errors and improve the general readability.
Safety Evaluation:
This modification will not have any effect on the probability, consequences, or possibility of new accidents evaluated in the FSAR.
This exempt change will also not affect the probability, consequences, or possibility of malfunctions of equipment important to safety evaluated in the FSAR.
Any leakage will still be handled by the VE system, therefore, the margin of safety defined in the bases of the Tech. Specs. will not be reduced.
This modification does not involve an unreviewed safety question.
CE-1950:
==
Description:==
This modification revises the affected drawings associated in downgrading the WN Sump Pumps to non-coded components.
NSM's CN-11019 and CN-20409 were written to accomplish this modification.
However, several drawings were not included in the revision.
This VN will revise those drawings which were overlooked.
This modification affects FSAR Figure 9.5.9-1.
Safety Evaluation:
A Safety Evaluation is already provided for NSM's CN-11019 and CN-20409.
This modification will not require any work in the field to be performed.
CE-2007
==
Description:==
This change revises I/M CNM-1205.00-1997 to include all the NRC Bulletin 85-03 valves which have been identified.
The old Torque Switch settings sheets for the affected valves will be deleted and all the information included in the I/M.
Thrust, Packing and Differential Pressure values have been included in the I/M for valves which MOVATS testing has been completed.
The remaining torque switch setting values will be deleted and MOVATS data added by exempt change VN's as the valves are scheduled to be tested.
4_1
i I
- Safety Evaluation:
The probability or consequences of an.
accident previously ' evaluated, to different than already evaluated, will not _ be increased by - this modification.
Nor will1 the probability or consequences of any equipment i.
malfunction previously evaluated, or different than~any already evaluated, in.the FSAR be' increased due to this modification-.
F
.The. margin of: safety as defined.in the basis to any Technical-
'~
Specification' will not be reduced by this Exempt Change'.. No field work will be completed per this Exempt Change.
This.
Exempt Change only takes existing information from various drawings-and includes it in'I/M CNM-1205.00-1997.
This change does not involve any unreviewed safety considerations.
CE-2030
==
Description:==
. This modification revises the EQRI Manual to
~
include ' a. note concerning eight (8). Barton 763. and 764 4
' Transmitters, identifiable by unique serial number.
The note recuires that these specific transmitters have their internal-L piri connectors soldered per CNM-1399.60-0031 (Westinghouse FCN J'
DCPM-10575) prior to being ' installed in a plant system.
- Modification.of any of these transmitters after December 1,
,1988 will. requirethe origination of an exempt change variation notice for-documentation.
- Safety Evaluation:
The location of these (8)' transmitters is unknown but all model 763 and 764 Barton Transmitters installed in the plant have'been-looked at and verified not.to be any of the (8) serial numbers involved with CE-2030.
The probability or consequences of an accident previously.
' evaluated,, or different than already evaluated in the FSAR, will-not-be increased by this modification.
Nor will the probability or-consequences of any ~ equipment malfunction previously evaluated, in the FSAR be increased due to this modification.
The' margin of safety as defined in the basis of any Technical
. Specification. will not be reduced by this change.
This modification will not cause any unreviewed safety questions.
4_2
_ =.
J,
!T '
CATAWBA NUCLEAR STATION.
Summary of Procedure Changes, Tests, and Experiments Completed Under 10CFR50.59 for 1988 CP/0/A/8800/05 Chemistry Procedure for Recording and Management of Data:
This change deleted the requirements for sampling horon concentration and dissolved gas in the UHI (Upper Head Injection) system.
This change was made'after the determination by Westinghouse, and approved by the NRC, that the UHI system was not t
required as part of the ECCS.
No Unreviewed Safety Question (henceforth USQ) was deemed to exist.
OP/1/A/6350/02 Diesel Generator Operation:
This changed a verifica-tion of' control pressure to account for the addition of a nitrogen supply to the Diesel Generator Starting Air System, serving as a non-assured primary source for the engine control panel pneumatic instrumentation.
The Safety Related Starting Air System is available as before, and the Nitrogen System is separated from the Starting Air System by a check valve which will allow the Starting Air System to assume its role if the nitrogen supply pressure falls below the starting air supply pressure.
No USQ was deemed to exist.
PT/1/A/4350/02A Diesel Generator A Operability Test:
Exactly the same as above change for OP/1/A/6350/02.
OP/0/B/6400/03 Low Pressure Service Water System:
This change adds instructions for the operation of valve IRL-497, which was added to the system per a modification to provide isolation capability for deleted piping to the station machine shop.
No USQ was deemed to exist.
OP/0/A/6500/18 Operating Procedure for the Release of Waste Gas Decay Tank C:
This change adds instructions for the opera-tion of two manual valves, 1WS-140 and 1WG-309, to reduce gas pressure in lieu of a pressure reducing valve.
This change in release mode operation was made to accommodate a modification which changed the release path.
No USQ was deemed to exist.
PT/2/A/4150/22 Total Core Reloading:
This was an initial procedure issue used to reload the core in a safe and orderly manner in agreement with the Catawba Unit 2 Core Loading Plan Cycle 2.
This procedure meets all the pertinent criteria as outlined in the FSAR, and intro-duces no new failures or accidents.
This procedure is more conservative than the FSAR in that it requires SFP insert identification numbers to be checked along with the fuel assembly identification numbers prior to re-load.
No USQ was deemed to exist.
i3
4 p
/
1 PT/P/A/4150/11B Control Rod Worth Measurement By Rod Swap:
This change incorporated a test methodology concerning the use of alternate rod banks to swap with rod banks being mea-sured.
Before, the reference bank was used exclusively to perform this swapping.
The rod worth measurement is still performed the same way. The only.significant change is the use of the previously measured rod bank to swap with the next bank being measured instead of the reference bank.
Adoption of the new rod swap meth-odology will minimize the use of Tech Spec Special. Test Exception 3.10.3.
Overall safety will be enhanced.
This new test methodology has been reviewed by the NRC per an SER.
No USQ was deemed to exist.
.TC/0/B/9400/06 Radwaste Chemistry Procedure for the Determination of Recirculation Requirements for Representative Auxiliary Monitor Tank Sampling:
This was an initial procedure issue control testing of the recirculation time required to obtain a representative sample from the Auxiliary Monitor Tanks, added to the Liquid Waste System per a modification.
These. tanks are a response to NRC concerns requiring the station to show that samples were representative of tank contents for, release from the station.
This procedure will enhance safety by ensuring that liquids released are within governmental requirements for dose.
No USQ was deemed to exist.
B&W 1151373-Al Recirculating Steam Generator Manual Removal of Ribbed Mechanical Plugs:
This procedure is an initial issue and implements the S/G tube plugging process, which is described in 5.4.2.1.3 of the FSAR.
This section describes tube plugging as an acceptable method for repairing S/G tubes.
All potential failure modes have been addressed in the FSAR.
No new failure modes are created.
No USQ was deemed to exist.
B&W 1155135-A2 Recirculating Steam Generator.750 and.875 Tube Plugging with Ribbed Mechanical Plugs:
Same as above.
No USQ was deemed to exist.
B&W 1157321-A2 Ribbed Plug Lubrication:
Same as above.
No USQ was deemed to exist.
B&W 1157922-A3 RSG Rolled Plug Pull Removal Tool Operating Instruc-tions for.750 Roll Plug:
Same as above.
No USQ was deemed to exist.
B&W 1158085-Al Field Procedure for Recirculating Steam Generator
. Manual Removal of.750 Roll Plugs:
Same as above.
No USQ was deemed to exist.
l I
di
m-
.p h'..
]
7 j
'B&W 1169608-A3-Operating Instruction for the Air Driven Roger Roll l
i
' Expansion' Tool and the Manual Roll Expansion Tool:
Same^as above.
No USQ was deemed to exist.
i l
B&W 1369615-A3-Field Procedure / Operating Instructions for' Steam Generator Tube.End Repair:
Same as above. -No USQ is.
deemed to exist.
B&W 1169652-A2 Field Procedure for Recirculating Steam Generator Tube Plugging with Mechanical Roll Plugs:
Same as above.
No USQ was deemed to exist.
L B&W 1169898-Al Manual and Remote Marking of Tube Locations:
Same as above.
No.USQ was deemed to exist.
B&W 1170119-A0 Open Systems tog for Steam Generator Activities:.Same as above.
No USQ was deemed to exist.
.B&W 1170155-A2..
~ Operating Instruction for Ribbed Plug Installation Tool
'(Center Pull. Type): Same as above.
No USQ was deemed
.to exist.'
CP/0/A/8700/01' Chemistry Procedure for Sampling Local Primary Sample
~ Points:.Same as discussed in CP/0/A/8800/05 above,.
i.e., the UHI System.was deleted and is no longer part of the ECCS.
This change deleted sampling of the UHI System from the. procedure.
No USQ was deemed to exist..
Hp/0/8/1004/04
. Radioactive Liquid Waste Release:
This change incor-porates use.of.the new Monitor Tank Building and associated components.
The Monitor Tank Building System and. components will increase process flow rates and ensure proper segregation of the various liquid-waste. streams.
This system does not affect any safety.
related portion of the Liquid. Waste System, and does not' introduce any new failure mode. - The consequences of failure of the Monitor Tank Building is less than
.that previously evaluated for-the Refueling Water Storage Tank.
No USQ was deemed to exist.
HP/0/B/1009/11 EHF (Radiation Monitor) Loss:
This change incorporates the EMF for the Monitor Tank Building into the proce-dure for instructions of compensatory measures re -
quired.
Same as above.
No USQ was deemed to exist.
IP/1/B/3610/02A System Calibration Procedure Diesel Generator IA Engine Cooling System (KD):
This change deletes calibration of a Diesel Engine Cooling Water System temperature transmitter.
A new procedure has been created contain-ing calibration of this same transmitter.
This new procedure will provide for specific Calcon related instrument related corrosion inspections and calibra-tions.
No USQ was deemed to exist.
l 41
IP/1/B/3610/02B System Calibration Procedure Diesel Generator IB Engine Cooling System (KD): 'This change deletes calibration of a Diesel Engine Cooling Water System temperature transmitter.
This transmitter is now calibrated per another procedure.
Same as.above.
No USQ was deemed to exist.
IP/2/B/3610/02B System Calibration Procedure Diesel Generator 2B Engine Cooling System (KD):
Same as above for Unit 2 KD System transmitter.
No USQ was deemed to exist.
IP/1/8/3620/02A Calibration Procedure Diesel Generator IA Lube Oil System (LD):
Same as above for six Unit 1 LD System transmitters.
No USQ was deemed to exist.
IP/2/B/3610/02A System Calibration Procedure Diesel Generator 2A Engine Cooling System (KD):
Same as above for Unit 2 KD System transmitter.
No USQ was deemed to exist.
IP/2/B/3620/02A Calibration Procedure Diesel Generator 2A Lube Oil System (LD):
Same as above for six Unit 2 LD System transmitters.
No USQ was deemed to exist.
IP/1/B/3620/028 Calibration Procciure Diesel. Generator IB Lube Oil Svstem (LD):
Same as above for six Unit 1 LD System transmitters.
No USQ was deemed to exist.
IP/2/B/3620/02B Calibration Procedure Diesel Generator 2B Lube Oil System (LD):
Same as above for six Unit 2 LD System LD transmitters.
No USQ was deemed to exist.
IP/1/B/3680/01 Diesel Generator Control and Monitoring Equipment (EQC)
Calibration Procedure:
Same as above for two EQC System pressure transmitters.
No USQ was deemed to exist.
IP/2/B/3680/01A Calibration Procedure Diesel Generator Control and Monitoring Equipment (EQC):
Same as above for a Unit 2 EQC System pressure transmitter.
No USQ was deemed to exist.
IP/2/B/3680/OlR Calibration Procedure Diesel Generator Control and Monitoring Equipment (EQC):
Same as above for a Unit 2 EQC System pressure transmitter.
No USQ was deemed to exist.
IP/1/0/3681/01A Calibration Procedure for Diesel Generator IA Calcon Instrumentation:
This was an initial procedure issue for the specific purpose of incorporating all Unit 1 D/G Calcon instrumentation calibration / inspection into one procedure.
Specific instruments have been taken out of the above stated procedures.
This procedure will ensure that the instruments included perform in ik i
)
accordance with Design Engineering specifications.
No USQ was deemed to exist.
IP/2/B/3681/01A.
Calibration Procedure for Diesel Generator 2A Calcon-Instrumentation:
Same as above for.0/G 2A, No USQ was deemed to exist.
MP/0/A/7150/21 Centrifugal Charging Pump Auxiliary Lube Oil Pump Corrective Maintenance:
No significant change.to procedure. The procedure was updated to include correct information and procedure format. The pump will be returned to as-designed, as-built conditions.
No USQ was deemed to exist.
MP/0/A/7650/69 Installation and Repair of Mechanical-P.iping and Cable Penetration Firestops:
No significant change to proce-dure. This change added precautionary information related to the use of passive fire protection material.
No USQ was deemed to exist.
MP/0/A/7650/85 Visual Inspection of Snubbers and Corrective Maint-enance: This was an initial procedure issue.
The inspections and corrective maintenance are designed to ensure that snubbers are kept in the as-designed, as-built condition.
Performance of this procedure does not make any snubbers inoperable, but is intended to detect and repair inoperable snubbers.
No USQ was deemed to exist.
OP/1/A/6100/07A Annunciator Response for Panel 1AD-20:
The changes made in this procedure retype make the required re-sponse for the "KC (Component Cooling) Supply Header Flow to Reactor Coolant Pump Boarings Low" annunciator (KC system pressure switch KCPS9170) compatible with directions given in the loss of Component Cooling Abnormal Procedure.
This retype will allow a smooth transition from the annunciator response to the ab-normal procedure and the actions contained agree with the information in the FSAR, Section 9.2.2.
No action taken in this procedure can adversely impact system operability.
No USQ was deemed to exist.
OP/1/A/6100/078 Annunciator Response for Panel 1AD-21:. Same as above for component cooling pressure switch KCPS9180.
No USQ was deemad to exist.
OP/2/A/6100/07A Annunciator Response for Panel 2AD-20:
Same as above for Unit 2 Component Cooling System pressure switch KCPS9170.
No USQ was deemed to exist.
OP/2/A/6100/07B Annunciator Response for Panel 2AD-21:
Same as above for Unit 2 Component Cooling System pressure switch KCPS9180.
No USQ was deemed to exist.
u
- - _ _ _ _ - _ _ _ _ _ _ _ - ___--____-_- - -__ m
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' 0P/1/A/6450/17.
Contain' ment Air Release and Addi-tion System:
This-change.was made to enable containment air releases without: recirculation.
The original reason for re-a circulation was to give the operator time to determine-if the containment pressure increase was due to a. loss-of coolant or-a steam line break accident'and to ensure that containment air chemistry had'been determined.
The' pressure increase due^to:a LOCA or-SLBA would be?
much: larger than normal pressure increases and would be recognized prior to starting the release.
Containment--
air chemistry is checked daily-(and 'is also cmtinuous-ly' monitored by radiation monitors) and;is fo' warded to
~
Operations via a Gas _ Waste Release Package.. It is not
.necessary to' recirculate containment prior to release.
The safety related containment isolation portion of this system is not affected by this change.
No USQ was deemed to exist, y
0P/2/A/6450/17-Containment Air Release and Addition System:
Same as
.above for Unit 2.
No USQ was deemed to exist.
- OP/1/A/6500/14 Operations Control. led Liquid Waste Systems:
This
' change was made to incorporate the operation.of valves added (per a modification) to sample the condensate from several Air Handling Units.
This change wJil have-no affect on the proper cperation of the safety related-portions of the Liquid Waste System.
No USQ was deemed
.to exist.
OP/0/B/6500/33 Operating Procedure for the Liquid Waste Recycle (WL)
System Floor C ain Tank (FDT) Subsystem: This change
.was made to a) incorporate previously approved changes into a retype, b) revise the procedure format, and c) provide _ operating instructions for portions of the system added or altered by a modification. The modi-fication performed on the WL System comprises the new Waste Monitor Tank building system as discussed pre-viously in this report.
No USQ was deemed to exist.
OP/0/0/6500/34 Oparating Procedure for Liquid Waste Recycle System Laundry and Hot Shower Tank:
Same as above.
No USQ was_ deemed to exist.
OP/1/B/6500/13 Turbine Building Sump System: -This change was ini-iated to allow discharge from the Turbine Building Sump (which receives ventilation unit condensate drain-potentially radioactive) to the new Waste Monitor Tank Building, added per a modification as previously dis-cussed in this report.
This change will not affect any safety related portion of the Liquid Waste System.
This change will allow for more efficient processing of effluent paths.
No USQ was deemed to exist.
_48 L.L_L.-~.__w---_._._____-__._-_ - _. _ _ _ _. - _.. - _ _ _ -
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0P/2/B/6500/13'
. Turbine Building' Sump System:
Same as above for the.
Unit 2 Turbine. Building Sump. No USQ was-' deemed to exist.
p, s
H PT/2/A/4350/13-Venturi. Fouling Correction Test:
This is an initial
. procedure issue which determines the correction' factor for the.feedwater venturi. A. cot'rection' factor is necessary due to the fouling'that can occur over' time.
n-
+
The. feedwater venturi is.-an ASME nozzle used to measure-feedwater flow as an input to the' thermal best estimate power calculation. - Thermal best estimate is used to calibrate the-nuclear instrumentation.
Test measure-ment uncertainty has been analyzed for;its impact on nuclear safety.. 'No change in DNBR 1.imit will resultL Lfrom this procedure.
Secondary thermal-power mea'sure-ment is addressed in the FSAR.
No USQ was deemed to exist.
PT/1/A/4150/22 Total Core Reloading:
This change. incorporates minor
' editorial and format changes._.Several parameter values.
are revised to account for the necessary conservatism due'to uncertainties.
No USQ was deemed to-exist.
PT/1/A/4200/10B
.ND (Residual Heat Removal) Pump IB Performance Test:
This was a temporary change issued to-utilize more.
accurate pressure gauges than required by this proce-ure so that this test procedure may be conducted concurrently with pump head verification procedure (which requires more accurate. test instrumentation).
No USQ was deemed to exist.
PT/1/A/4200/10B ND (Residual Heat Removal) pump 1B Performance Test:
This change established a new set of reference. values
,for the performance testing of.ND Pump 1B.
The pump was changed out during maintenance, and ASME.IWP allows changing the acceptance criteria to the tested per-formance conditions of the.new pump.
The new ND 1B pump'is.a little stronger than the previous pump, and also meets Westinghouse acceptance criteria for ND flows for the FSAR Chapter 6 and 15 analyses.
No USQ was. deemed to exist.
mis.
PT/2/A/4200/01M
'Incore Instrumentation Thermocouple. Penetration Leak Rate Test: This change contitutes a complete rewrite-of the original procedure to incorporate'new testing commitments and methods.
The penetrations will be tested by pressurizing the' penetrations with nitrogen at approximately 15 psig.
The penetrations are designed for-72 psig with no adverse effects.
There-fore, the integrity of the penetrations will not be
~
challenged. Also, the penetration cop removal and replacement and fill valve manipulation are independ-ently verified to ensure that the penetration is 31
_=-___-- _-
m p
returned to the safe condition.
No USQ was deemed to exists.
PT/1/A/4200/0]R M301, M141,.M234, M452 Penetrations Leak Rate Test:
This change was written to allow the use of higher range test. instrumentation.
This higher range has been accounted for in the test acceptance criteria uncer-tainty analysis.
No significant changes to the procedure.
No USQ was deemed to exist.
PT/1/A/4206/01R:
.M301, M141, M234, M452 Penetrations Leak Rate Test:
The purpose.of this test is to measure leakage through.
.each respective penetration.
However, two of the
. penetrations have'had flanges rewelded.
As per ANSI.
. requirements, this change allowed a pressure test of the penetration prior to the leak rate test. Any degradation in the flanges or flange bolts during the pressure test will be apparent during the subsequent leak rate test.'
No USQ.was deemed to exist.
PT/1/A/4350/15A Diesel Generator 1A. Periodic Test:.This change was made to accomodate the modification which installed a nitrogen system.to provide control. gas pressure to
' Diesel Generator IA, as previously discussed in this report (under OP/1/A/6350/02).
1he nitrogen system is separated from the diesel starting air system by a check valve, and this procedure change provides directions for the testing of the check valve.
This test ensures proper operation of the diesel. -No USQ was deemed to exist.
PT/1/A/4400/01 ECCS Flow Balance:
This procedure was originally written to be performed in Mode 6 (Refueling) or no mode. This change will allow performance.of the ND (Cresidual Heat Removal) Pump 1B Head verification in Mode 5 (Cold shutdown).
Boron dilution is not a concern since the pump will be recirculating the water already in the Reactor Coolant System.
The pump will be run in its normal operating alignment, and important pump and motor parameters will be monitored.
No USQ was deemed to exist.
PT/1/A/4400/01 ECCS Flow Balance:
This change was vritten in anticipation of Valve INDGO (Resid%I Heat Removal Heat Excha'ger 1B Outlet) leaking by it. seat enough to not allow the Miniflow valve to open automatically.
If this occurs, the Residual Heat Removal Crossover valve will be closed,' isolating B Train froe A Train, and the Train B Cold Leg Injection valve will be :losed.
Isolating the trains will have no effect on system operation, since Train A will remain in operation during the test on B Train.
No USQ was deemed to exist.
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I l1P/0/8/3220/33 Control Rod Drive System (IRE) Logic Cabinet Pulser / Oscillator Card Setup:
This change involved no significant major revisions..This change contains editorial revisions and provides better direction and will allow safer calibration of the cars.
No USQ was deemed to exist.
IP/1/A/3110/07
' Component Cooling System (KC) Lo~opsL5530, 5531, 5540, 5541, 5630, 5640, 9170;.9180: This change involved.a revision-to the data sheets and calibration method to avoid lifting leads at the level switch, shorting, and, possibly causing unwanted valve acuation. 1No USQ was deemed to exist.
.IP/1/A/3632/01-Diesel Generator Room Ventilation 'ystem (VD):
,T hi s -
S change ad&_: information for the calibration of the.
Temperature Control Controller Instrument Loops without t~
the fans running.
Only editorial, changes were made.
No (ISQ was deemed to exist.
IP/1/B/3181/16 IP/2/B/3181/16 Liguid. Waste (WL) System Calibration Procedure for Reactor Coolant Drain Tank Subsystem: This change involved a minor editorial revision due to a modification which changed the nomenclature of the Reactor. Coolant Drain Tank Level Annunciator Window such-that the annunciator matches the actual alarm.
This change did not affect any setpoints or plant parameters.
No USQ was deemed to exist.
IP/2/A/3140/03C Calibration Procedure Auxiliary Feedwater System (CA):
This change deleted calibration of indicator portion of CA System Pressure Switch 2 CAPS 5141.
This pressure switch functions to automatically close Valve 2CA58A for train isolation in the event of a low CA pump discharge pressure following a CA auto-start signal.
This safety related automatic function will in no way be affected by deletion' of calibration of the Switch Indicator Pointer.
Also, other instrumentation is available to monitor operation of the CA Pumps.
Nc USQ was deemed to exist.
MP/0/A/7150/04 Component Cooling Pump Corrective Maintenance:
This change involved no sigd ficant changes.
Only editorial revisions were made.
h USQ was deemed to exist.
MP/0/A/7150/48 Steam Generator Power Operated Relief Valve Corrective l
Maintenance:
This change corrected a torque value on a-l-
data sheet to agree with the value indicated in the body of the procedure and the manufacturer's drawing.
This was an_ editorial revision.
No significant changes were made.
No USQ was deemed to exist.
MP/0/A/7150/24 Component Cooling Pump Removal and Replacement:
This i
e 4
)
Ib change' involved a procedure' format upgrade and editorial = revisions.- No significant revisions were i
'made.
No USQ'was deemed to exist.
}
MP/0/A/7150/53 Pressurizer Hatch Cover Removal and Replacement:
This change involved only editorial changes. The necessary precautions and instructions.are. included to return the hatch covers and gaskets to.as-designed, as-built conditionc No USQ was deemed to exist.
MP/0/A/7600/12 Walworth and Aloyco Bolted Cover Swing Check Valves Corrective Maintenance:.This~ change involved editorial' revisions.
The procedure will maintain the valves to Tech Spec, FSAR, and manufacturer's requirements..No physical change,is being made to the valve's design or function.
No USQ was deemed to exist.
MP/0/A/7600/26 Pacific Swing Check. Valves Corrective Maintenance:
This change.only involved editorial'and format changes.
.No technical content was changed.. The procedure a.
- maintains the valves to manufacturer's requirements.
No USQ was deemed to exist.
MP/0/A/7600/33 Pressure Relif Valves,, Flanged Type Corrective Maintenance:
This change mainly involved editorial-and-format revisions made during the procedure. upgrade.
process. Also, revisions included a) coating nozzle threads with thread sealant to prevent leakage, b) added guidance for proper venting of a bellows sealed valve bonnet.
This procedure will maintain the valves to original design specs and requirements.
No USQ was o
deemsd to exist.
MP/0/A/7600/47 Fisher-Diaphragm and Manual Actuated Control Valves Types DBQ, DBAQ, and DBQNS and Type.1008 Manual
-Operator Corrective Maintenance:
This change mainly involved editorial and procedure format revisions.
Several other revisions were made to ensure that the valve is returned to the as-found position following maintenance and to ensure proper group communication for the performance of Post-Maintenance Testing.
This procedure maintains the valve to Design and manufacturer's specs.
No USQ was deemed to exist.
MP/0/A/7600/110 Anchor Darling 12" Bolted Bonnet Gate Valve Corrective i
Maintenance:
This is an initial procedure issue.
The i'
procedure will maintain valves to proper design and manufacturer's specs. No USQ was deemed to exist.
MP/0/A/7650/01 Flange Gasket Removal and Replacement:
This change only involved editorial revisions.
This change provides for additional recording of data from f
inspections.
No change to the physical structure is j
involved.
No USQ was deemed to *xist.
]
L2
'MP/0/A/7650/82-Auxiliary Building Hatch Cover Removal and Replacement:
This is a procedure retype which incorporates previ-ously-approved changes.
This procedure provides the l
necessary guidance to ensure that the hatch cover is reinstalled as per design.
No USQ was deemed to exist.
.0P/0/A/6250/16 Operating Procedure for the Condensate Polishing Demineralized Backwash Tank Subsystem: This change involves a procedure _ reissue.
This system is non-safety related, and does not interface with any safety related systems.
The system operation as described in this procedure is consistent with the operation described in the FSAR.
The procedure requires sampling to ensure'that the contents of the Backwash Tank and the Decant Monitor Tank are within r
units of Tech Spec 3/4.11.1.5' prior to discharge to the Conventional Waste Treatment System.
No USQ was deemed to exist.
OP/0/A/6400/06B Nuclear Service Water Pump Structure Ventilation System:
This is a procedure retype which incorporates Operations Management Procedure guidelines and changes the normal alignment of the system.
Presently, the Normal alignment of the system is to have one fan in
" Auto" and running, while the 'other is in "Off."
This retype allows the operator the option of leaving both fans in " Auto" with one fan running.
Interlocks exist such that only one fan will run at a time, thus protecting the ductwork. With both fans in " Auto," on a failure of the running fan, the opposite train fan in the respective compartment will automatically start to provide ventilation.
Therefore, this is an enhancement of nuclear safety.
No USQ was deemed to exist.
i OP/1/A/6350/02 Diesel Generator Operation:
This change involved editorial revisions to support and accomodate a modification to replace and relocate the D/G Starting Air Solenoid Control Cabinets.
The purpose of the modification is to provide a Bill of Materials for the cabinets and relocate them to a less harsh environment.
This mod!fication has a separate 50 59.
No USQ was deemed to exist.
OP/1/A/6700/01 Unit One Data Book:
This change establishes New Core Axial Flux Difference (AFD) Targets and Limitations.
l The Target AFD is updated by the performance of PT/1/A/4150/08, Target Flux Difference Circulation.
The Target AFD is changed to keep Control Bank D at approximately 215 steps withdrawn (at 100% power),
]
while allowing for changes in the natural axial power I
shape that occurs with core burnup.
The targets are set by procedure to be within the operating bounds of M
,' 'D..
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1 i
Tedh Spec 3/4.2.1
'The targets are an operating-
' g' guideline only'to ai.d the Control Room operators in-maintaini.ng AFD within-the'. units of Tech Spec'3/4.2.1.
Y The' targets serve no other purpose. They do not-W provide input to any trip function. 'The. limits that' must be observed in Tech Spec'3/4.2.1lare set by Cycle l
. Specific Analysi.s. 'No USQ was deemed to exist.
- DP/1/A/6700/01-Unit One Data Book
This change replaced the "NC-(Reactor Coolant) Pump No. 1 Seal Safe Operating Range" curve with a new curve. supplied by Westinghouse enti--
tied "NC Pump No.-1 Seal Normal Operating Range." LThe
" Safe Operating Range" plot was'not representative of
~ the' normal range of No. 1 Seal. Leak rates at interme-diate pressures. Therefore.. Westinghouse has redefined-
. the plot of No.1 Seal' Leak Rate vs. Differential l
Pressure.for.RCP operation. With this update, Westing-house has also revised the minimum and maximum seal leak rates for. continuous operation to be 0.8 gpm and-
- 6~.0 gpm respectively.
The normal No. 1 seal leak rates are not referenced in the FSAR~or Tech Specs and are.
not considered in any accident scenario.
No USQ was deemed to exist.
v Op/1/A/6700/01
. Unit One Data Book: This change replaced the Reacti-vity Balance Calculation, Reactivity Anomaly Calcula-tion, ECP Calculation, and Boric Acid / water to alter i
. Boron Concentration Tables in the Unit Data book. All of these new tables were taken from the Catawba 1 Cycle o
- 3 Startup and Operational Report supplied by Nuclear Engineering of the Duke Power Co. Design Engineering Department.
This is a QA Condition 1 Manual.
No USQ was deemed to exist.
OP/1/A/6700/01.
Unit One Data Book:
Update of AFD Targets.- see 50.59 evaluation earlier in.this report on same type change.
No USQ was deemed to exist.
Op/1/A/6700/01 Unit One Data Book:
Same as above.
No USQ was deemed to exist.
OP/0/0/6250/09 Operating Procedure for the Condensate polishing Demineralizers:
This is a procedure' reissue.
This reissue enables manual precoating, backwashing, and Other modes of operation'by the operator in lieu of automatic operation.
The.various steps of operation are the same as for automatic operation as described in the.FSAR.
No USQ was deemed to exist.
OP/2/A/6250/06
- Main Steam Operating procedure:
This change tempo-rarily adds an enclosure to induce a level transient in b-S/G 2C to observe the response of the Temporary Level Instrumentation installed under a modification.
Catawba Unit 2 Steam Generator Narrow Range Level Indi-M
o w
t s
cations.have displaye'd excessive shrink'and' swell-characteristics during low power.' operation.
These
?
fluctuations _have'resulted in numerous reactor trips and ESF actuations. 'In response to this problem, a i
modification was performed to install temporary level L
taps at a-lower tap location on S/Gs..This temporary.
LL 1evel instrumentation is. designed for data recording and testing purposes only, and there is no functional interface with or modification of the current S/G 1evel instrumentation.
All plant. safety systems will remain
~
in their normal mode.' No USQ was' deemed to exist.
.PT/1/A/4150/128 Isothermal Temperature Coefficient of. Reactivity Measurement (EOL):
This change relaxes the restriction on Allowable TAVE-TREF Deviation previously imposed by
- the test's Limits and Precautions Section.
The restric-tion of ~13.0 F is based upon the " Initial Condition" restriction of 14.0 F imposed for analyzed. accidents which are~not DNB Limited, per FSAR Section 15.0.3.2.
. However, FSAR Section 15.0.1.1 allows deviations in plant l parameters in excess of normal operational limits for the purpose of performing tests required by Tech.
Specs.
In this case, the EOL ITC Measurement is
- required to be performed within 7 EFPDs of reaching a Reactor Coolant System Boron Concentration of 300 ppmB per Tech Spec 4.1.1.3.b..
In order to minimize the error associated with this measurement, it is necessary to reduce TAVE an amount greater then 4.0 F below TREF.
This change will not impact FSAR accidents which are DNB limited due to the fact that TAVE is only reduced below TREF.
TAVE is increased by Reactor Coolant System dilution only to recover it to the TREF value (Full. power TREF is 590.8 F).
Per this test method-ology the TAVE limit of 592.5 F specified in Table 4.4.2-1 of the FSAR,.Section 4.4, Thermal.and Hydraulic Design, will not be exceeded at any time.. This test methodology also does not' employ the use of the Chemial and Volume Control System in any but a. normal operating configuration. Therefore, the assumpt. ions made in this analysis and the resulting consequences are bounded by the FSAR Accident Analysis. The margin of safety defined in the Tech Spec Bases will.not be reduced.
Operation within the limits of Tech Spec Figure 2.1-1, Reactor Core Safety Limit - Four Loops'in Operation, will be maintained at all times.
Additional conser-vatism will be assured by observance of the DNB Para-meters in Tech Spec Table 3.2-1.
No USQ'was deemed to exist.
OP/2/A/6700/01 Unit Two Data Book':
This change replaces the Main Feedwater Pump Speed Control Delta-Program.
This change will improve. flow during normal operations and reduce the severity of feedwater transients.
It is desirable to operate the Feed Reg Valves in the con-trolling region which r.epresents the latest 55_
,.+
1.
information on the Pump Speed Control Program obtained.
from IP/2/B/3222/87.
This figure being placed into the Unit Data Book provides no control or interlocks, but is for information only.
No USQ was deemed to exist.
OP/2/A/6700/01 Unit.Two Data Book: This change replaces the " Reactor Coolant Pump No. I Seal. Safe Operating Range" curve with a curve supplied by Westinghouse as. discussed earlier in this. report.
No USQ was deemed to exist.
PT/1/A/4150/118 Control Rod Worth Measurement by Rod Swap:
Same as discussed earlier in this report under PT/2/A/4150/118.'
~No USQ was deemed to exist.
-PT/1/A/4200/01N Reactor. Coolant System Pressure Boundary Valve Leak Rate Test:
.This change allows the testing of more than
-one valve at a time.
This change is written so'that the acceptable leakage from an entire group of valves-tested at the same time is less than 1 gpm.
If leakage from the group exceeds this value, each valve in the.
group will be tested individually, No change was made to the allowable leakage for each valve..No USQ was deemed to exist.
PT/1/A/4200/09A Auxiliary Safeguards Test Cabinet Periodic Test:
This is a reissue of the test procedure.
The appropriate-precautions are taken in this procedure to ensure that-no plant equipment is actuated which will upset the plant during normal operation.
No USQ was deemed to 1
exist.
H PT/1/A/4200/13H NI (Safety Injection) and NV (Chemical and Volume Control) System Check Valve Test: This is a reissue.
This procedure verifies full stroke capability of various check valves in the ECCS.
Performance of this test will take place in either Mode 6-(Refueling) or no mode.
In either case, the Reactor Vessel Head will be removed and full flow through the check valves can be obtained.
In Mode 6 or no mode the ECCS is not required to be operable.
Boron dilution will not be a concern since the pumps will not be a concern since the pumps will be recirculating the water already in the system or injecting water'from the Refueling Water Storage Tank.
The ability of the. Reactor Coolant System to provide Net Positive Suction Head has previously been demonstrated.
PT/1/A/4250/03D RN (Nuclear Service Water) to CA (Auxiliary Feedwater)
Pumps Suction Transfer Periodic fest: This is a procedure reissue.
The' purpose of this procedure is to measure the time required for the CA System to switch to the safety' grade suction source, the RN System.
The suction piping is aligned so as to introduce as little RN Water to the system as possible. This test will be 5g
performed in Modes 4, 5, or 6..The CA System is only required in tiodes 1, 2,, cr 3.
RN System operability will not be affected by this procedure.
The CA Pump Breakers will be racked out during this test, and the valves will not be operated abnormally.
No USQ was deemed to exist.
PT/2/A/4200/19 FD (Diesel Engine Fuel 011) System Valve Inservice Test-Quarterly-Performance:
This change is a procedure writer's guide upgrade of an existing procedure.
T hi s procedure is used to satisfy IWV stroke time require-ments for FD System valves.
No USQ was deemed to exist.
CP/0/B/8150/02 Chemistry Procedure for the Determination of Conductivity:
This change includes the incorporation of previously approved changes and editorial revisions.
It also includes directions for obtaining samples at same points added to the Conventional Sampling System for S/G blowdown and the Main Steam Reheaters.
These new sample points will enhance Unit operation by allowing the Chemistry Staff to better monitor and correct secondary side chemistry problems.
No USQ was deemed to exist.
OP/1/A6200/13 Filling, Draining and Purification of the Refueling Cavity: This change will ensure the procedure steps L
are performed in such an order that the vessel head is not suspended over the vessel while QA personnel are verifying the vessel cleanliness.
There are no technical changes made.
This change ensures personnel safety.
No USQ was deemed to exist.
OP/1/A/6100/20 Operational Guidelines for Achieving Cold Shutdown l '
Following a Fire in the Plant:
This change did not involve any technical revisions.
The intra plant phone numbers were updated to reflect the current plant conditions.
No USQ was deemed to exist.
PT/1/A/4200/02A L
PT/1/A/4200/02B l
PT/1/A/4200/02C Monthly Outside Containment Integrity Verification:
This change was made to delete verification of the UHI System valves because of the removal of the UHI System.
l This change also corrected some minor nomenclature inaccuracies.
No technical changes were made.
No USQ was deemed to exist.
PT/1/A/4200/06A PT/1/A/4600/19C Mode 1 and 3 Periodic Surveillance Items:
This change deleted surveillance requirements related to the UHI System due to the removal of the system and its consequent deletion from Tech Specs.
No USQ was deemed to exist.
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t PT/1/A/4600/028 PT/1/A/4600/02C
' Mode 2 Periodic Surveillance Items:
This change involved editorial revisions. A revision was also included to perform an RL System (low pressure raw water - non safety related) flow channel check for the purpose of verifying'a flow weighted temperature.
No USQ was deemed to exist.
l
.r.
9 I
i l
I b
1 CATAWBA NUCLEAR STATION NUCLEAR STATION MODIFICATIONS COMPLETED IN RESPONSE TO NUREG-0737 l
SUPPLEMENT 1 DURING 1988 j
l l
The following Nuclear Station Modifications were completed during 1988 and corrected Human Engineering Deficiencies (HEDs) identified in NUREG-0737, Supplement 1:
CN-20222 CN-20226 CN-20232 CN-20223 CN-20227 CN-20233 I
CN-202.24 CN-20230 CN-20237 CN-20225 CN-20231 CN-20240
==
Description:==
These modifications corrected all outstanding HED's identified as part of the Control Review Process. The subject modifications meet License Condition 7 to Operating License NPF-52 and fulfill commitments made in Duke Power's response to NUREG-0737, Supplement 1.
Safet.y Evaluation: These modifications were the result of Control Room Review Activities. These changes do not adversely impact any plant system and do not involve any unreviewed safety consideration.
l' l.
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