ML20155G742
| ML20155G742 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 10/12/1988 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8810170419 | |
| Download: ML20155G742 (13) | |
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\ Duke h>utr Contpany ll<i R Tw l , yo gy 33193 b ut FWudent Charlotte. N C 2A:42 Nxtrar 1%:stin
(?vI),173.*ill DUKEPOWER October 12, 1988 l
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l U.S. Nuclear hgulatory Occmission l ATTDirION: Ibcurrent Cbntrol Ttsk i Mahington, DC 20555 ;
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Subject:
McGLiire Ntaclear Station l Docket 14mbers 50-369 and -370 Annual n=mmary of Activities ,
Performed th$er 10 CFR 50.59 '
i Attached are ammary descriptions of changes made to equipment and procedures which are described in the ItGuire Final Safety Analysis & port. 1his report covers clanges inado during the calendar year 1987. '
very truly yours, A
y Hal B. Tucker SXi/143/nnf ;
xc Mr. Darl S. ! bod, Project Manager ;
Office of Naclear Nactor Bogulation '
U.S. Nuclear Ngulatory Connissico i iushingten, DC 20555 l l
Mr. M.L. Frnst ;
l 7cting Ngional Mministrator, Ngion II !
U.S. !bclear Begulatory Om.tission 101 Marietta Street, NW, suite 2900 Atlanta, C(orgia 30323 Mr. W.T. Orders ,
1 Senior Besident Inspector j l McGt; ire !bclear Station '
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3310170419 881012 PDR ADOCK 05000369 e
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Dqcurent (bntrol Ibsk Octcber 12, 1988 Page 2 bxc N. A. %therford R.L. Gill R.O. Sharpo (FNS)
T.L. ft<bnnell (FNS)
R.C. Ebtrell R.C. Tucy 1C-801.01 i
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McGUIRE NUCLEAR STATION Summary of Nuclear Station <
Modifications MG-11627 These NS."s added a neutron flux meter and associated cabling to :
MG-20492 the auxiliary shutdown pcnel for each unit. This modification is in response to Regulatory Suide 1.97. ,
The ASP is safety related although this neutron flux meter and i some other display instruments are non-safety. The meter is i seismically mounted to ensure no adverse interaction with the ;
safety-related switches on the ASP. ,
Accordingly, this modification will have no effect on the proba- t bility, consequences or possibility of new accidents evaluated in the FSAR. Nor will it arfect the probability or consequences of malfunctions of equipment important to safety evaluated in the FSAR. The margin of safety defined in the bases of the Tech. ;
Specs. is unaffected. The answer to each of the 10CFR50.59 unreviewed safety que tions is "no". There are no unreviewed safety questions resulting from this modification.
MG-11724 This NSM replaced an inoperable composite sampler in the Ventilation Unit Condensate Drain Tank (VUCDT). The sampler is located in a 3/4" line of the radioactive liquid waste (WL) system. The VUCDT subsystem collects condensation from the containment and auxiliary building ventilation units. Normally, the activity in this tank is well below permissible levels for discharge. The replacement sampler will improve the sampling capabilities over the present sampler and will not create or increase the probability of any accident.
No consequences of any accident will be increased, because the function of the system is not changed and the ability of detect activity in the ventilation condensate is improved. No margin of safety is affected.
MG-10609 This NSM added a "Hi AP" alarm on the entire outside air pressure filter trains in the control room ventilation (VC) system. The old design had one AP gauge for the prefilter and HEPA filter, and a second for the carbon adsorber. The new design retains the pre /HEPA filter AP gauge, while the second now spans the entire prefilter/HEPA/adsorber train. This modification will not increase or create the probability or consequences of any accident, because failure of the gauge and/or tubing will not initiate any accident, nor will any seismic interaction with the gauge and/or tubing cause additional failures.
MG-11895 These NSMs added test vents in the nuclear service water (RN)
MG-20673 system to allow testing of differential pressure across the diesel generator cooling water (KD) system heat exchanger, for each unit. The vent line has the same pipe material, class, and design considerations as the adjoining pipe.
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These modifications are no*. related to the cause or mitigation of any accident previously evaluated in the FSAR or different than previously evaluated in the FSAR. The initial conditions of the core and reactor coolant system will not be affected by this -
modification. Due to proper design considerations for the vent line, the probability or consequence of a inalfunction of equip- i ment important to safety will not be increased. No margins of safety as defined in the bases to any Technical Specifications are affected.
MG-01678 This N5M adds a rupture dick assembly in the fire protection >
system (RF) piping serving the control room pressurization filter
- trairs. Failure of the non-seismic RF piping could result in an uncontrolled pathway into the control room, possibly resulting in control room doses greater than general design criteria 19 j values. The rupture disk in the RF piping will provide a barrier 1
to air entering the control room via the piping in the event of
- piping failure. The disk will rupture upon pressurization of the RF system. No safety question, according to the criteria stated in 10 CFR 50.92, is created or involved as a result of this NSM.
No safety system has been degraded nor will any functional changes taka place.
! liG-11790 These NSMs changed the setpoints for Refueling Vater Storage Tank Rev. 1 (RWST) level setpoints in accordance with: 1) new emergency MG-20609 procedure switchover sequence; 2) new data on RWST depletion hv. I rate; and 3) current valve stroke time acceptable criteria.
, This modification is not related to the initiation of any i accidents or equipment malfunctions analyzed in the FSAR, and i
! will not result in the creation of any new accidents or !
malfunctions. The initial conditions of the reactor coolant system and core will not be affected by this NSM, and the ability j to mitigate accidents will be unaffected. No failure modes are j
- associated with this mod.
, e The only potential safety concern associated with this l modification is that the new level setpoints for the RWST may i result in a reduction in the margin of safety for plant opera-tion. However, the revised results obtained in the setpoint recalculation indicate that the new level setpoints are adequate for operating requirements and do not compromise any plant j margins of safety. Appropriate technical justification for this modification is fully documented in the recalculation. l l MG-11590 These NSMs add indications to the Auxiliary Shutdown Panels i
MG-20466 (ASPS): reactor coolant system cold leg wide range temperature, neutron flux, letdown temp, letdown pressure, letdown flow, decay heat removal pump discharge temp, and decay 1: eat removal to RCS I cold leg temp.
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1 The subject NSMs represent a major modification to a nuclear-safety-related system. The system is provided to allow operators l l to attain and maintain a hot shutdown condition in the unlikely event that the main control room must be evacuated. Only one ASP is provided for each unit.
, The ASPS are safety-related panels because they contain some ,
energized IE control circuitry; however, the indications, both ,
4 existing and proposed, are non-essential and non-safety and do -
i not involve any controls. The indications are seismically i mounted to prevent interactions with the IE components, but are not required to function during or following a seismic event, i The signals for the new indications indude qualified isolation !
devices to prever t fault propagation ;o the PCS. Therefore, i 1
the probability of acciderts or malfunctions of equipment !
important to safety is not increased and the potential for new !
types of accidents or malfunctions is not created. [
]'l Since the additional indications enhance the ability of the i
operator to perform the necessary actions at the ASP, the chance l l i i'
for operator error is reduced. Therefore, the consequences of ;
accidents or malfunctions of equipment important to safety are {
not increased. !
The margins of safety defined in she bases to the Technical i Specifications are also not reduced by the addition of ronitoring (
instrumentation to the ASP. [
i MG-20468 This NSM provides throttling capability from the Auxiliary MG-Il591 Shutdown Panel to the Letdown Orifice Isolation Valve, Auxiliary Spray Supply to Pressurizer Isolation Valve and the Charging Line !
i Flow Control Valve. Appendix R Review was performed and seismic '
] mounting to the Auxiliary Shutdown Panel was provided. -
l Therefore, the probability of any malfunction of equipment will t not be increased and the possibility of any different malfunction !
] of equipment not previously evaluated in the FSAR will not be !
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created. No margin of safety is affected. This modification 3 resolves several Human Engineering Discrepancies (HED M-1-686, ,
j HED M-1-688 and M-1-694). j 1
l MG-ll380 This NSM replaced a water-cooled condenser unit in the service i
j building with an air-cooled unit. No safety system is affected :
by this modification and no functional changes to any system are l made. Failure of the condensing unit is of p' safet/ signi-l ficance and potential missilet are bounded 'j existing analyses. '
- No unreviewed question is created by this modift
- ation.
- MG-ll274 This NSM provided for the remodeling of existing warehouse space i into office space. This renovation will not adversely impact any i safety systems. The service building was used for warehouse
- space and maintenance, and did not house active safety-related l systems, i
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! MG-20254 This modification provided isolation valves in drain lines of !
I ventilation systems' filter units. The purpose of the modifica- !
l tion is to prevent the drains from backing up and flooding the ,
carbon filters, in the event a float assembly fails in the open positi The float assembly controls the level of a water seal !
in th( rain lines, to prevent air leakage past the filter unit.
These crains are inadequate to remove excess water in the event ;
the deluge fire protection system actuates. Therefore, the value l of the drain system is outweighed by the o:casional failure of l the float assembly, which results in vet (inoperable) carbon filters. The addition of the valvas in the filter drain lines i will not increase or create any accident probability, and will not affect the function of the ventilation filter units. Thus, ,
the consequences of any accident will not be increased.
MG-11707 These modifica* ions added flame arrestors to the diesel generator MG-20114 fuel oil day tutks. The flame arrestors will not affect the operation or reliability of the diesel generators, and will not introduce any new or additional accident or accident consequence i Concerns. l t
MG-11877 This NSM enlarged the overflow pipe of the Reactor Makeup k'ater !
MG-20660 Storage Tank and installed a relief valve on the underdiaphragm vent line. These modifications will prevent overpressurization :
of the tank, therefore decreasing the probability of equipment ;
malfunction. No margin of safety or consequences of accidents t are affected. }
r MG-10914 This modification routed overflow from liquid waste monitor (kh) i l !.anks A and B to a common header and then to floor drain tank l Sump B. Previously, the overflow from the tanks had been free to l
empty into a walkway in the auxiliary building. This inodifica- i tion has no effect on the operation of the kM tanks or the kh system. The additional influent to the TDT sump is not a safety l concern. ;
MG-1374 This modification removed a sodium analyzer from what was originally intended to serve as a liquid waste (k1) evaporator, '
but is now used as a boron recycle (NB) evaporator. A sodium {
l analyzer would serve no purpose in the NB system evaporator. The i 41 evaporator function has been determined to be a less efficient :
means of processing liquid wastes than a be,i resin ion exchanger, (
which is currently being used, i MG-1408 This modification removed an unused auxiliary plant heating ;
boiler. The boiler had been idle since a larger capacity boiler had previously been installed. No safety system has been i degraded and no functional change will be made to any system. i MG-11884 These modificatione involve installation of a stainless steel l MG-11885 spool piece for a flow element in a component cooling (KC) heat l
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exchanger and a nuclear service water (RN) heat exchanger to i alleviate corrosion-induced measurement errors.
The stainless steel spool piece to be fabricated for this modification meets seismic requirements for Class C piping.
- Pressure tap environmental qualifications are specified as Code 8 from the McGuire I&C List. This modification will improve
. reliability of flow measurement readings by eliminating the i
! corrosien problem. Equipment availability will not be affected. t The spool piece will not have any impact on response times or error bands.
This modification does not affect any FSAR accident analyses, and does not latroduce any potential failure modes. No adverse systems interactions will occur as a result of this modification, ,
). and there will not be any impact on the plant margin of safety as ;
j defined in the bases to the Technical Specifications. ;
1 i MG-11880 The purpose of the subject NSMs is to improve the response time !
] MG-20663 and the reliability of the control loops associated with FVP 3 Rectre Control Valves CF76 and CF81. This is accomplished by j J
replacing pneumatic componutts (transmitters, receiver gages, and i valve positions) with electronic components.
$ The control loops affected by this modification are not safety-
, related and the consequences of any new component failures are i 1 bounded by tnose that formerly existed because the feedwater
- system in ultimately not relied upon to perform any safety [
, functions. Th, modification should, in fact, reduce the likeli- i hood for such faildres. Thus, as a consequence of the improved control response and reliability, the probability of occurrence l of design basis feedwater transients is not increased and no ,
{ accidents beyond the design basis are created by the modifica- l
. tion. The modification does not involve a functional change to
! the control loops; the operation of the control valve is rot l l degraded and it still fails open on a loss of signal. l 1 ,
A seirmic review of affected control boards has been performed I
- and the seismic qualification of the boards is not degraded by l j the modification. No other equipment important to safety is ;
j affected, either directly or indirectly, by the modification. ;
Therefore, the probability or consequences of equipment malfunc-i tiont are not increased and no new malfunctions are introduced.
i MG-ll656 Thic modification adds 18 breathing air (VB) connections in the I turbine building. The VB system is not safety-related (with the l exception of the containmet.t isolation valves, which are not i affected by thia modification). No safety system is affected by
} this modification.
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) MG-11917 This NSM replaced pressure transmitters and instrument air pressure switches monitoring the operation of the main steam (SM) l Pcwer Operated p.elief Valves (PORVs). The transmitters and
, s.sitches are replaced by direct process line pressure switches and pressure gauges. T!.e modification has been analyzed to
- ensure that any failure of the replacement switches will not !
create a new accident. The replaccruent switches should reduce .
- the frequency of maloperation of the PORVs caused by pressure i drift in the pressure transmitters.
MG-01864 The modification will downgrade the boron recycle evaporator feed
- pumps from Duke Class C to Duke Class E.
I i i Potential concerns with this modification involve the reclassifi- !
cation of one snubber from QA Condition 1 to QA Condition 4, the i deletion of one snubber, and the reclassification of 27 rigid j
, supports from QA Condition 1 to QA Condition 4. These changes :
- reflect the down grade of the asso-clated piping from Class C to !
Class E. This downgrade can be accomplished since the Boron !
Recycle System dees not affect tt.e safety of station operations. l The Boron Recycle Evaporator Feed Pumps sill be changed from QA Condition 1 to QA Condition 2 equip-ment. This piping, equipment,
,! and support /rentraints do not need to be QA Condition 1 because !
they are not part of the Peactor Coolant System pressure boundary, ,
they are not required for safe shutdown, and they are not neces- !
4 sary to prevent or mitigate the consequences of accidents as l required by 10 CFE Part 100, i This modification is not related to the initiation of any acci-dents or the malfunction of any equipment as described ir. the ;
3 FSAR. The modification will not result in the creation t.,f any i
- new accidents or malfunctions. The modification will not have any !
1 impact on the plant iaargia of safety as defined in the Technical Specifications.
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MG-11524 This modification adds a dual indicating light aid relector '
- switch to IMC5 Control Board to provide Open/ Closed status and j power disconnect for the Pressurizer Auxiliary Spray Control ,
j Valve. Human Engineering Discrepancy HED-M-1-699 is resolved by i 3 this modification. The valve fails close and the NSM was I reviewed fo.' seismic impact to the control board and Appendix R l concerns. Therefore, the probability of any malfunction of '
j equipment will not be lucreased and the possibility of any J different malfunction of equipment not previously evaluated in j the FSAR will not be created. No margin of safety is affected.
J MG-11768 These modifications delete the Upper Head Injection (UHI)
MG-20598 system. The Technical Specification changes associated with UHI removal have been reviewed and approved by NRC; therefore, no unreviewed safety questions exist.
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MG-ll267 This NSM reronted the spent resin sluice pump discharge header :
from t!.e waste evaporator feed' tank gravity header to the kIFT '
pumped header. The ultimate destin: tion remains the hTFT. The 1 l purpose of the modification is to avoid un tecessary contamination ,
l of personnel and equipment through inadvertent spills. More than !
sixty components are connected to the kIFT gravity drain header.
3 There is a possibility that a valve associated with one of tnese
- components, if left open, could result in a radioactive spill.
- Rerouting the discharge to the pumped header will provide more
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j positive control of the sluicing operation. The spent resin
! sluicing operation remains functionally the same. No safety ;
! system is affected by this rodification. l
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MG-;1888 These NSMs replaced carbon steel pipe in the nuclear service i j MG-ll891 water (RN) system with stainless steel pipe, the replacement ;
piping is safety-related and is designed to the same pressute and il temperature parameters as the original. Nothing new is added to j i the system which would create the possibility of a new accident '
{ not previorsly evaluated in the FSAR. l i
The probability and consequer.ces of a malfunction of equipment [
i important to safety previously evaluated in the FSAR will be l decreased since the equipment coolers can perform as designed. !
No possibility cf malfunction of equipment important to safety l
, different than any already evaluated in that FSAR has been {
i it.t roduced . No margin of safety as defined in the bases to any l i Technical Specification is reduced. There are no unreviewed
) safety questions associated with this NSM. l 1 l 1 NG-11743 These NSMs involve the replacement of eight cold leg accumulator l j MG-20575 (CLA) discharge check valves. The valves have had repeated leakage i i problems. Tha leakage has caused reductions in CLA boron concen- l j
tration and difficulty in maintaining RCS leakage within Tech Spec ;
limits.
The new check valves represent essentially one-for-one change- '
outs; the new valves have slightly different flow character-istics. The new valves are fur.ctionally identical to the old i
- valves and introduce no new failure modes. The weight and end-to-end dimensions of the new valves are the same as the old valves, so the stress analysis remains valid. No increase in the probability of previously-analyzed accidents will occur. The discharge orifices have been sized to comper. sate for the slightly
] different hydraulic characteristics. No consequences any acci-i dent will be increased.
j MG-20645 Thim NSM allows 3 spare containment penetrations ta be used for
- various activitias performed during refueling outages. Pipe caps used to seal t,e penetrations have been cut off, and replaced with flange-blind flange assemblies. A valve is included on the flange outside of containment to allow for testing. Flanges, pipes, and valve all comply with ASME Section III requirements.
, No accident probability will increase or be created, because the
- penetrations do not affect any equipment which could initiate an accident. No consequences of any accident will increase, because i
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{ the penetrations are sealed during unit, operation and are open j
, only during shutdown. The penetrations are testable to ensure j i containment integrity. During shutdown, when the penetrations
- are in use (blind flanges removed) the penetrations are filled ,
{ with a foam sealant to inhibit air exchange between containment t and the annulus. No accident which could occur during shutdown !
would result in this foam barrier failing. !
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i McGUIRE NUCLEAR STATION Summary of Procedure Changes, Tests, and Experiments Completed Under 10CFR50.59 for 1987 >
I IP/0/B/3006/18 IP/0/B/3006/18 is the instrument procedute associated with Radiation Monitoring System Data Logger, the data logger ,
replaces a recorder for increased reliability in monito- :
, ring. FSAR Section 11.4.2 needs to be changed to reflect j l this equipment replacement. Since the equipment deals with ;
monitoring functions only, which cannot affect accident probability, the change does not involve an unreviewed ,
safety question. l 1 OP/0/A/6450/11 OP/0/A/6450/11 describes the opersting procedure for the ,
j Control Area Ventilation / Chilled Water System (VC/YC). ,
j This particular change involves steps for the cross-con- l necting of two inoperal,le trains of VC/YC to provide i cooling. This change would not be utilized unless both ;
Trains were already inoperable. This mode of operatiou is ;
- not described in FSAR Section 6.4, but does not involve an j i unreviewed safety question.
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! PT/1/A/4403/07 ?T/1/A/4403/07 describes the procedure for performing the. i Train A Nuclear '*rvice Water (RN) Flow Balance. Change 5 ,
was made af ter encountering dif ficulty in achieving the '
i specified RN flowrate to the Safety Injection Pump 011 l
, Cooler. A re-evaluation by Design Engineering confirmed ,
J that the reduced flowrate, still satisfying vendor i i specifications, was acceptable and did not involve an l
] operability question. A change was necessary to FSAR !
j Table 9.2.2-1 to reflect the lowered flowrate. ;
I OP/0//B/6200/33 OP/0/B/6200/33 describes the procedure for isolating, '
flushing, draining, and returning to service various ;
] components of the Solid Waste (VS) System. Section 13 of i i the procedure refers to the contamirated Oil Storage Tank !
3 (COST), which was previously used as the Binder Storage i
{ Tank for the old soldi n cation process that was never used [
at McGuire. The tank is located outside the solidification l 1 pad and is implanted underground. FSAR Sections 2.4.12 and I
) 15.7.3 address credible accidental releases to the ground i i water and the assumptions made at the time did not include {
{ the use of the Binder Storage Tank as a storage tank for contaminated oil. This procedure revision makes this l l i i aslumption necessary. The evaluation of the risk potential I
! determined that an unreviewed safety question did not J exist.
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IfP/0/B/1003/02 IIP /0/B/1003/02 describes the method of sampling, I l initiating, and documenting a radioactive release from
, various sources, including unwatering of the Condenser Circulating Water piping via the WU System, A change is needed to FSAR Section 9.2.8 to reflect that the WU Systen.
1 is also a potential radioactive source to the Turbine i Building Sump. A unreviewed safety questica does not ,
j exist.
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PT/0/A/4550/28 The "Contrc111ng Procedure for Fuel Clip Installation" is ,
a new procedure provided for the installation of fuel rod i
- clips to p.otect the fuel against the damaging effects of !
- baffle jetting. The addition of the fuel rod clips (to 24 fuel assemblies) is a design change that must be determined !
! that the addition of the fuel rod clips to the fuel assem- !
blies does not involve an unreviewed safety question.
PT/0/B/4600/18 The re-vrite of PT/0/B/4600/18, "Radioactive Liquid I Ef fluer.t Sampling and Analysis Frequency", incorp., rates i
changes 0 through 4. By Facility Operating License i j Amendment 72 (Unit 1) and 53 (Unit 2), a new release point 1 for raficactive liquids was added, thereby permitting the l
- release of liquids containing trace quantities of radio ;
activity directly into the Catawba River, via the Conven- ,
I tional Waste Water Treatment System. The release point was t added because the liquid radwaste system was incapable of
, handling turbi.9 building sump discharge on a continuing !
4 basis as would be required by the tech, spec, if there l l were small steam generator tube leaks. It was determined '
that FSAR Section 9.2.8 needs to be changed to reflect that the Unwatering (WU) System is also a potential radioactive l
- will be changed to include the Catawba River as a release i l point. Although the effluent release path is changed, ,
i neither the dose, quantity nor concentration of radioactive .
] effluent in the river is changed and therefore an unre- !
] viewed safety question does
- not exist. ,
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j OP/0/B/6200/65 The "Radwaste Procedure for the Transfer, Dewatering, and !
i Shipment of .owde:' Resin", addresses a processing optior 1 j not identified in the ESAR, that being to process powdex !
to liners for burial at an approved disposal site. This change does not affect Tech. Specs, and does not involve
- an unreviewed safety question.
I q HP/0/B/1003/08 IfP/0/B/1003/08 describes the method for determining radiation monitor setpoints. With the addition of the f Equipment Staging Building and the associated veutilation
- radiation monitor 2 EMF-59, it was necessary to change 4
Tech. Spec. and FSAR Section 11.4.2.2 to reflect the added 1 monitor. It was determined that an unreviewed safety 4
question did not exist.
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MNS Page 2 of 3 I
! HP/0/B/1009/14 HP/0/B/1009/14 describes Foalth Physics actions for ;
j inoperable gaseous effluent monitoring and flow rate ;
measurement devices. With the addition of the Equipment :
1 Staging Building and the associated ventilation radiation :
monitor 2 EMF-59, it was necessary to change Tech. Spec. i j and FSAR Section 11.4.2.0 to reflect the added monitor. !
It was determined that an unreviewed safety question did l l not exist. j t
PT/0/B/4600/08 PT/0/4600/08 correlates process and effluent monitor i
! readings with laboratory analyses of radionuclide l 1
concentrations. With the addition of the Equipment !
Staging Butiding and the associated ventilation radiation monitor 2 EMF-59, it was necessary to change Tech. Specs.
, and FSAP. Section 11.4.2.2 to reflect the added monitor. :
j It was determined that an unreviewed safety question did j i not exist.
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i HP/0/B/1003/15 describes a method for calculating the HP/0/B/1003/15 l total gsseous, particulate, halogen and tritium activity j that is released from the Contaminated Parts Warehouse, ,
j the Interim Radwaste Building, and the newly added (
7 Equipment Stating Building ventilation systems. FSAR j 1 Section 11.4.2.2 needs to be changed to reflect the ,
l addition of the Equipment Staging building Ventilation j
, Monitor, 2 EMF-59. It was determined that an unreviewed ;
j safety question did not exist, i t
P'l/0/B/4600/19 PT/0/B/4600/19 establishes a program tor periodically ,
sampling, analyzing and documenting radicactive gaseous l
, effluents as required by Tech. Specs. With the addition {
q of the Equipment Stagie.g Building and the associated j ventilation radiation monitor 2DIF-59, it was necessary to l change Tech. Specs, and FSAR Sect.on 11.4.2.2 to reflect l the added monitor. It was determined that an unreviewed '
i safety question did not exist. l l
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