ML20029B160
| ML20029B160 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/31/1990 |
| From: | Stimac S COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9103060031 | |
| Download: ML20029B160 (6) | |
Text
l
[/ ~') Ocmmonwealth Ed!scn 1400 Opus Place
(
Downers Grove, Illinois 60515 February 28, 1991
-Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk
Subject:
Zion Station, Units 1 & 2 10 CFR 50.59 Annual Report fBC_ QodeLNo.sm50:29.5_.anL 50:30A
Dear Dr. Hurley:
Pursuant to 10 CFR 50.59(b)(2), Commonwealth Edison is providing the required annual report for Zion Station (Facility Operating License Nos.
The "Haukegan Memorial Airport Expansion Plans" and
" Pressurizer PORV/ Safety Valve Cha11eneges" reports are also provided pursuant to Zion Technical Specification 6.6.3.B.e and 6.6.3.B.1, respectively.
The 10 CFR 50.59 report consists of descriptions and safety evaluations for changes to the facility as described in the safety analysis report.
The report only contains changes made to the facility; no tests or experiments governed by paragraph (c) of 10 CFR 50.59 were executed.
Please direct'any questions regarding this matter to this office.
Very truly yours, L
r 2
S.F. Stimac Nuclear Licensing Administrator cc:
C. Patel (NRR)
A. Bert Davis (RIII)
J.D. Smith-Zion Resident Inspector
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9103060031 901231 l /
O PDR ADOCK 05000295
/
R PDR
4 ATTACHMENT 1 ZION NUCLEAR POWER STATION 10 CFR 50.59 ANNUAL REPORT 1990 DOCKET 50-295 and 50-304 COMMONHEALTH EDISON COMPANY I
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4 TABLE OF CONTENTS 1.
Environmental, Radiological and Meteorological Monitoring II.
Haukegan Memortal Airport Expansion Plans III. Annual Occupational Exposure Data IV.
Challenges to Primary System PORV's and Safety Valves V.
10 CFR 50.59 Report 1.
Modifications 2.
Tests 3.
Experiments 4.
Other Saf;ty Evaluations
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c 1.
Environmental, Radiological and Meteorological Monitoring:
This report is submitted as Part III of the Zion Station c
Annual Operating Report which is transmitted under separate cover.
II.
Haukegan Memorial Airport Expansion Plans:
The Airport master record (FAA 5010-1) and airport map (FAA 5090-1) has been updated and submitted by the Haukegan Port Administrator (see Enclosure 1 of this report)
Ongoing expansion plans at the Haukegan Regional Airport consist of lend orquisition and obtaining aviation easements.
III. Annual Occupational Exposure Data:
This report details Personal Radiation Exposure per Regulatory Guide 1.16 and is transmitted under separate cover.
IV.
Challenges to Primary System PORV's and Safety Valves:
No challenges occurred to either the Primary System PORV's or Safety Valves during this reporting period. This report fulfills the requirements of NUREG-0737, Item II.k.3.3,
" Reporting S/RV Failures and Challenges."
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t V.
10 CFR 50.59 Report 1.
Modifications:
A.
Refueling:
Unit I refueling outage started on 9/7/89 and ended en 1/25/90. Fuel was loaded in 1989.
Unit 2 refueling outage started on 3/21/90 and ended on 8/30/90.
B.
Modifications:
M22-0-77-017
==
Description:==
This modification installs additional limit switches and a fuel building crane load cell stop to prevent crane from carrying an excessively heavy load over the spent fuel rack area of the fuel pool.
50.59 Evaluation:
This modification brings the design into compliance with the safety analysis report, The modification limits the travel of the crane and does not introduce any new crane functions.
H22-0-85-007
==
Description:==
This modification improves the de-aeration of the primary water system by installing a better designed pumping system in place of the existing vacuum pumps.
50.59 Evaluation:
This modification enhances the design of the existing vacuum pumps. No new accidents are created and the modification is bounded by previous accident analysis.
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7 H22-0-85-011'
==
Description:==
This modification replaces obsolete turbine building oil coalescing filters with a " plate" type oil coalescing unit to improve oil removal efficiency. This modification also adds a solid collection trough to collect accumulated sludge.
50.59 Evaluation:
This modification improves the.
efficiency of the separator The equipment affected by this modification does not interact with equipment important to safety.
H2?-0-85-042
==
Description:==
.This modification' replaces station battery-chargers and batteries to
, increase the capacity and reliability of_the DC system.:
.50.59 Evaluatio'n:.
The new batterles provide almost twice the capacity of the existing-batteries. The-replacement
' batteries will perform the same-function.as the original batteries for aLlonger period of time. The voltage remains-~ unchanged.
H22-0-86-006 h
Description:
This modification replaces the service
~
water booster pumps packing with single j
mechanical seals that require'no flushing water.rThisl modification r
-reduces bad packing-leaks in these-pumps which continue despite-frequent maintenance. This will also reduce bearing. failures caused by water leaking into'the bearing oil reservoirs.
50.59 Evaluation:
This modification enhances pump
-performanen because of the rediv. tion of paching leaks. The ir,tallation'of the single
'uechanical seals will not degrade safety and does not create any_new accident or malfunction of
. equipment.
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'k M2210-87-003-Descriptlon:
This. modification upgrades the waste:
F, treatment sludge handling system. This includes the insta11ation of-an indoor drying bed and' chemical injection system to process sludge throughout the year.
50.59 Evaluation:
The function of the equipment being replaced _ remains unchanged.
The equipment added improves the i
process by reducing dry active waste and does: not interact with-i any equipment important to safety.
The e'quipment added also increases reliability and-lessens the possibility of spreading any contaminat_lon from sludge drying
-operation.
.-M22-0-87-008
-Description:
This modification adds a large_ capacity bulk cationic polymer addition system I
to the waste water treatment system.
50.59.-Evaluation:
The waste water treatment facility does not interact with any systems important-to safety. The modification enhances economic caeration_of--the system. Should t1e bulk polymer tank rupture and its1 contents-: spill-into_ the -
equalizati_onitank it-could be neutralized and cleaned-up without affecting overall_ water quality or safety in-any-way.
_M22-0-87-029
==
Description:==
This modification disables the water sampling system trouble _ alarm-due to the removal of analyzers from OLP06.
-50.59 Evaluation:
This modification removes-a locked-in alarm due to removal of analyzers:in OLP06. It:does not affect system performance or:
affect the operability of other equipment.
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'H22-0-88-008
==
Description:==
This modification installs retractable phone cord reels in phone wells of-control room control' boards and installs an intercom and sound power phone to disposition HED's 112 and 299. 59 Evaluation:
The seismic mounted retractable phone cord reels do not impact on any safety related equipment nor can create a different type of accident or malfunction. The modifications are necessary to satisfy human factor requirements.
s H22-0-88-009
==
Description:==
This modification adds. dual controls and annunciation for the common "0" diesel generator as a result of HED's 8, 90,- 95,-318, and'388.=The modification addresses-HED's associated' with the-inability to control the
- common diesel generator from the Unit 2 control board when necessary-to supply Unit 2 ESF bus 247 from-the common diesel generator.
50.59 Evaluation:
The modification provides the same capabilities to-the Unit 2 operator as those that are already y
available to the Unit 1 operator-,
t The modification adds duplicate controls for.the swing diesel but'
~does'not introduce,an equipment malfunctionLthat~was not previously evaluated. This addition of the new equipment will not significantly change the structural capab111tles of the panels or' structures to which they-.
are attached.
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..{'i H22-0-88-010
==
Description:==
This modification involves:the rearrangement of-controls and
-annunciator buttons on-control room control board OCB05. In addition, a guardrail-is being installed and annunciators for OCB04 and OCB05 are being separated from the Unit-1/2 boards. These changes are necessary to address HED's 1, 8, 119, 167, 213, 216 298, 336, and 433.
50.59 Evaluation:'
The control switch rearrangement and cables added will not significantly change-the-structural capabilities of-the panels or.ths structures to which l
they are attached.-No new interactions with the existing equipment are created by the rearranged components. Any.
separation concerns are mitigated
'by ensuring that wires from switches.in different safety-divisions'do not cross each other and-are not bounded.
i, M22-0-88-011
==
Description:==
This' modification rearranges existing controls and meters on: control-room board 0CB04 in a configuration that-s s
provides functional-groupings of these 1
t components.nThese changes are necessaryL i
to address HED'ss8, 166 3333,:395, 396,-
1426, and 432.
50.59 Evaluation':
This modification does.not chenge
-the configuration of the existing-
-. system nor-creates any new_
interfaces with existing systems.
Any separation concerns are imitigated by ensuring'that wires from switches in different safety divisions do not cross each other and are not bounded.
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LM22-0-88-013 4
==
Description:==
This modification adds a fill-line to-hot water expansion tank.
50.59 Evaluation:
The hot water and auxiliary steam is not safety related and does not-interface with safety systems.
2#
This modification provides a-source of water to fill the hot water system.
M22-0-88-017
==
Description:==
This modification provides power feed and in-plant telephone-lines needed to.
implement a new computerized
.information management: system.LThe power will come from non-ESS MCC-1324 to the PRIME computer room.
50.59 Evaluation:
This modification'does not effect equipment important to safety nor does the power feed and telephone line alter any-auxiliary power limiting condition of operation.
1
'M22-0-88-018-
==
Description:==
This modification adds a fire damper in the recirculation return duct for the Technical Support Center's makeup-filter unit. This modification is necessary-to: comply with 10 CFR' 50, Appendix R Fire Protection requirements to-have rated fire dampers'in-ducts-which penetrate fire barriers.-
50.59. Evaluation:L ~This modification is designed and installed to meet seismic
-r requirements.
ir flow circult:
A through the Auxiliary Electrical Equipment Room is not dependent t
m'e upon makeup from the'TSC makeup-filter' unit. Thus, there is no-possibility ~for accident or
. malfunction which are different than previously evaluated.
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4 H22-0-88-035 i
==
Description:==
This modification. rearranges existing control switches on control room offgas panel OCBIS in a configuration that provides functional groupings of these components. These_ changes are necessary to address various HED's, 50.59 Evaluation:
This modification does not change j
the configuration of the existing system nor creates any new interfaces with existing systems.
1 Any separation concerns are mitigated by ensuring-that wires from switches in different safety divisions do not cross each other and are not bounded.
.M22-0-88-036
==
Description:==
This modification rearranges existing alarms and lights on control room fire prote; tion panels 2CB51, 2CB99, 2CB107, and 20108. These changes are necessary to. address HED 257.
50.59 Evaluation:
This modification does not change the configuration of the existing system nor creates'any new-interfaces;with existing systems.
This modification only rearranges-l_lghts on_ existing-panels to satisfy human factors requirements,
_H22-0-88-037 This modification adds:an AgastatT125V
==
Description:==
DC time delay l relay in.the auxiliary building pressure high-low. annunciator =
alarm circuit.:Thi; time delay relay.
would reduce'the numberiof false alarms by blocking-the spurious _ signals caused by gusty winds:that actuate the auxiliary building pressure.high-low alarm at panel OC805. This change is necessary to address HED_279.
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50.59-Evaluation:
This modification eliminttes spurious alarms to allow better.
. operator-recognition of an alarm
-that requires action. This modification only delays the response of the auxiliary building pressure high-low alarm.
- M22-0-89-005
==
Description:==
This modification upgrades the existing power: supply.for-a new telephone system. The power supply consist of a primary AC feed from MCC-1321A, an auxiliary:AC feed from panel LP3C, and-a battery backup supply, 50.59 Evaluation:
The IBT telephone system is a non-safety related-system. The modification increases the reliability of the power feed to the system by providing a battery backup supply which allows the system-to remain operable in the event of a loss of all AC power.
M22-0-89-009
==
Description:==
This modification disconnects at the-
.i fixtures some of-the; existing normal control room lighting fi tures from theirJcircuits and reconnects them to existing emergency AC lighting-circuits. These changes _are necessary to address HED's 76 and 77.
1 50.59 Evaluation:
This modification will have
= negligible effect on the;1oading on-the diesel generator or the-safety __related-buses.gThe_ rewired.
lights are connected to emergency-ll lightingLcircuits such=that they-do not overload those" circuits 1and therefore do not affect diesel loading. All_ wiring is routed:in flexible conduit between adjacent fixtures-and no new seismically y
~ supported conduits are required-,
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~H22-0-90-530-
==
Description:==
This modification reconnects the annunciator-input to general services panel OCB04 from liquid waste disposal panel OLP05. This modification is being performed due to.evisions to the Operating Shift Organization causing-
'the Rad Haste operator:to be away from panel.0LP05 for various tasks The annunciator input was removed during modification H22-1/2-76-19 since panel OLP05 was permanently manned at that-time.
50.59 Evaluation:
This modification has no interactions or impacts on safety related systems or components..
This-modification only invelves reconnecting existing leads for annunciator input. No physical changes are-involved.
-M22-1-81-009
==
Description:==
This modification adds a synchronizing relay to the manua, close'ctreuitry on
'each of the diesel generator output breakers and adds a time delay relay set of contacts to the automatic close
- portion of each of the diesel generator 3
output breakers which closes 2 seconds
{
after.an-undervoltage condition exist on the bus ~.
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50.59 Evaluation:
The synchronizing relay does not affect diesel generator output
-breaker operation during emergency operation. The probability of failure of the diesel generator output breaker due to this modification is extremely low and would affect only one of three safety buses.-The-time delay relay only affects; breaker operation during emergency conditions-if the diesel is-already running unloaded. The effect is that it ensures load:shed and proper j
diesel generator loading during emergency operation instead of immediately transferring all bus loads to the diesel. The modification decreases the probability of tripping or T
equipment. damage during emergency ~
conditions.when the engine-is already running, t
H22-1285-046
==
Description:==
This modification replaces station
'a battery chargers and batteries to increase the. capacity and reliability of the DC system.
- 50.59 Evaluation:
.The new batteries provide alnost
+
o twice the capacity of the. existing batterles. LThe replaceraent
-batteries wl11. perform the same-function asLthe original:-batterles for a longer period'of time. The-voltage remains unchanged.
H22-1-86-010' 3
==
Description:==
This modification adds an isokinetic q
. probe-in'the auxillary building exhaust =
duct to the: vent stack for the Illinois
-Department'of Nuclear, Safety's new stack monitoring facility,'The probe is-attached to a sample line routed to the IDNS facility.
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-50.59 Evaluation':
There are no accidents or malfu.ictions postulated that relates to the vent stack exhaust duct. exiting the. auxiliary building. The installation of the IDNS' isokinetic probe is completely independent of all station safety systems and 5
downstream of all iodine and particulate removal systems.
M22-1-86-018
==
Description:==
This modification. terminates leads sending HRSS alarm signals to the control room at ILP89 and ILP90--'in order-to eliminate nuisance alarms.
50.59 Evaluation:.
Annunciators provided at' local 1
- panels. HRSS equipment sensed is-not safety related, 1
H22-1-87-003
==
Description:==
.This modification adds a level L
transmitter and chart recorders to provide an accurate and reliable method to-monitor RCS level'during refueling andidrain-down conditions.
50.59 Evaluation:
-This modification ensures accurate and reliable monitoring of RCS level during all conditions:of-refueling-to: help prevent loss'of RHR and:thus'increasevthe margin-of safety. Loss of cooling:durin0.
1 shutdown and refueling has already' 4
1 been= evaluated.
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M22-1-87-009-
Description:
This modification re-connects-penetration pressurization air to containment isolation valves 1FCV-IA01A/B, ICS0052, TCS0053,
-ICS0054, 1C50055, ICS0056 1C50057, ICS0058,1CS0059,- 150V-PR26A/ B/C/D, and IFCV-PR24A/B These lines =were-disconnected under modification M22-1 019 in order to facilitate containment leak detection while performing an Integrated Leak Rate Test.
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50.59. Evaluation:- -This modification restores the penetration pressurizatfon air to the various containment isolation r
valves back to its origina'l design. Restoration of this'line increases the margin-of-safety by increasing the-containment-isolation: valves sealing capabi11ty, f
M22-1-87-023-
==
Description:==
This modification reroutes the instrument air supply to the penetration pressurization air dryers to ensure that the normal--air supply can be predried by the-penetration pressurization air' dryers prior to entering into the distribution: lines.
150.59(Evaluation:'
There are no new failure effects.
R created by this modification as the sources-'andEcomponents
. required to: dell.ver--supply remain unchanged,cThe double (redundantV check valves'are retained on-the
. rerouted air lines in order to
-prevent air-leakage'to the instrument. air system from the penetration pressurization system.
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M22-1-87-038
==
Description:==
This modification adds an isolation valve in the seal drain line for each of the RHR pumps to prevent borated water from entering the upper portion of the mechanical seal, Additionally, the lines will be re-sloped to allow for proper draining.
50,59 Evaluation:
This modification does not affect the operation of the RHR system and improves seal performance, thus, decreasing the chance for seal failure. The modification improves the reliability and performance of the RHR mechanical seals.
H22-1-87-039
==
Description:==
This modification adds alarmed hand switches and test pushbuttons/ lights in the MSIV circuitry. This allows de-energization of the MSIV coli during hot and cold shutdown without pulling MSIV fuses and de-energization of hydraulic pumps, 50,59 Evaluation This modification does not directly affect the operation of the MSIV circuitry, and therefore, does not affect the MSIV in mitigating accidents, Each handswitch feeds an alarm which would alert the operator of a
-switch in the wrong position. The test pushbuttons/ lights and their connections are identical to other test circuits in the same system.
The presence of the handswitches and test pushbuttons/ lights do not create any significant additional failure modes. The unlikely failure of a switch will only affect one train on one MSIV, The redundant train will close the MSIV during an accident.
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.4 M22-1-87-055-l
==
Description:==
This modification adds flanged spool I
pieces into;the area of the containment-air sampling line piping which previously contained air filter canisters. These spool pieces will ensure the seismic integrity of the associated piping.
50.59 Evaluation:
'The portion of this system addressed in this modification is non-safety vo.ated and does not perform any post-accident l'
functions. However, the installation of these spool pieces i
ensures the seismic integrity of the associated piping.
H22-1-87-077 x
==
Description:==
.This modificat hn removes >the steam
-generator program level meter LI-505 P
from the main control board because it does not present needed operating information. The modification also adds a differential. pressure gauge to indicate the-delta'(P) between the main i
steam header.and the feedwater header.
This. addition aids the-operator in' preventing reactor trips during startup.
.l by negating the need for-the operator
-to look at two different gauges and hand calculating-the difference.in pressure between.the steam header-pressure and_the feedwater header pressure.,The removal and addition are unrelated except for the location on the main control board.
50.59 Evaluation:
This modification does-not change any existi.ng control: circuitry ineluding alarms and annunciators.
The-isolation of protective systems'is not changed. There is y
no change in the operation of
-sterm or feedwater flows.
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z H22-1-88-001 DMcription:
This modification disables the automatic input to the containment evacuation alarm fror 1 source range high flux at shutdown Jm due to spurious alarms caused uy noise spikes on the NIS source range channels.
M.'i? Evo.umivn:
The containment alarm for high count rate is mentioned only in the Dilution During Refueling" accident analysis. However, the control room operator is credited with terminating the dilution based on control room indication of an increase in count rate.
Therefore, eliminating the automatic containment alarm will not affect the consequence of the dilution accident or any other acciant. Audible indication of
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source ra..e count rate will continue to be available both in the control room and in the y
containment.
M22.1-88-008
==
Description:==
This modification disables the turbine driven main feedwater pump thrust bearing trip in order to eliminate spurious trips.
50.59 Evaluation:
This equipment is not safety related and does not affect safety related equipment from performing its intended function. This equipment is not essential for safe shutdown ar.d will not cause other equipment to malfunction.
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H22 1-88-023
==
Description:==
This modification adds the following indication to the main control boards:
steam generctor narrow range level to CB08. CCH discharge header pressure to CB08, hydrogen monitoring containment isolation valves position indication to CB09. This modification also rearranget switcFes and meters in a configuration that is consistent with human engineering practices. These changes are necessary to address HED's 8, 259, 273, 281, 319, 335, 363, 372, 412, and 421.
50.59 Evaluation:
The rearranged switches and r.,eters and the new indication added to the main control boards do not significantly change the structural capabilities of the panels or structures to which they I
are attached. All separation requirements have been maintained.
1 In'eractions with existing ci uits are mitigated thre. ugh the pruurement of Class 1E relays and seismically qualified indicators, seismic mounting of equipment, routing of cables through the applicable raceways, and sneak circuit analysis.
H22-1-88-024
==
Description:==
This modification rearranges existing controls and indicators on main control boards CB08 and CB16 in a configuration that provides functional groupings of these components. This modification also rearranges other control board components consistent with human engineering practices. These changes are necessary to address HED's 8, 45, 56, 75. 80, 174, 290, 335, 361, and 421.
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50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events. This modification does not alter any oserating systems or functionally c1ange any existing control schemes. All relocated equipment is seismically installed and maintains divisional separation.
M22-1-88-026
==
Description:==
This modification rearranges existing controls, switches, indicators, and scales on main control boards CB06 and CB07 in a configuration that provides functional groupings of these components consistent with human engineering practices. These changes are necessary to address HED's 8, 148, 157, 165, 169, 174, 261, 262, 284, 287, 323, 324, 330, 335, 358, 362, 365, 375, 383, 390, 405, 414, 420, and 440.
50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events. This nodification does nct alter any operating ystems or functionally change any existing control schemes. All relocated equipment is seismically installed and maintains divisional separation.
H22-1-88-02?
==
Description:==
This modification rearranges existing controls and switches on main control board CB03 in a configuration that provides functional groupings of these components consistent with human engineering practices. This modificatter also adds a guardrall on main control boards CB01 - CB04 to minimize the postibility of inadvertent switch ac'9vation, These changes are necessary to address HED's 8, 12, 101,-
102, 174, and 264, i
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50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events. This modification does not alter any operating systems or functionally change any existing control schemes. Relocated equipment is seismically installed and maintains divisivr;I :eparation.
The guardrall is selsmic mounted and has no impact on any system configurations.
H22-1-88-028
==
Description:==
This modification reroutes the control cables for pressurizer power operated relief valves, letdown control valves, and excess letdown isolation control valves ( IICV-RC455C, IPCV-RC456, ILCV-RC459, and 1A0V-VC8381) from cable trays to conduit to protect these cables from hot spots or spurious shorts. These changes are necessary to address issues identified in a 10 CFR 50, Appendix R audit.
50.59 Evaluation:
This modification ensures a more conservative operation nf the designated valves in the event of a fire by separating cables into individual conduit and thus allowing operators to disconnect power to these-valves from the main control board.
M22-1-88-030
==
Description:==
This modification adds a seal-in
'eature to control circuits of extraction steam valves IMOV-ES0001, IMOV-ES0002, IMOV-ES0003, IMOV-ES0004, IMOV-E50005, IMOV-ES0006, IMOV-ES0007, IMOV-ES0008. IMOV-ES0009, 1H0V-E50010.
and IMOV-ES001). These changes sre necessary to address HED's 226 and 378.
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50.59 Evaluation:
This modification does not affect any circuit required to respond to or mitigate an accident. The modification actually allows the operator to devote more attention to monitoring plant conditions for safety because of the momentary time to initiate valve travel when required.
H22-1-88-033
==
Description:==
This modifi,ation removes eleven (11) snubbers from service located in the steam generator blowdown, component cooling, reactor coolant drain, main steam, and chemical and volume control systems.
50.59 Evaluation:
Reviseo calculations have demonstrated that removal of these snubbers will not exceed stress
)
levels for the given load combinations on these systems. The removal of these snubbers do not alter the function of the associated systems or induce stresses in excess of that allowed for the load combinations.
H22-1-88-039
==
Description:==
This modification reroutes two divisional reactor trip system control cables from a non-divisional power cable tray. Additionally, this modification removes an unassigned spare control cable from a divisional cable trav and abandons it in place.
These changes are necessary to address discrepancies identified during the NRC Safety Systems Outage Modification Inspection audit.
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1 50.59 Evaluation:
This modification does not change the control logic of the reactor trip breakers and only changes the routing of two control cables. In fact, this modification corrects deviations from electrical separation and voltage segregation i
requirements.
e M22-1-88-040
==
Description:==
This modification reroutes the power feeds for auxiliary building ventilation system exhaust fans (OA and OB). Additionally, this modification adds smoke detectors in the auxiliary electric equipment rooms, smoke detectors in.the component cooling water pump area, and fire breaks near the auxiliary feedwater pumps. These changes are necessary to address discrepancies identified during the 10-CFR 50 Appendix R audit.
50.59 Evaluation: _
This modification increases the overall reliability of the l-auxillary building ventilation system by correcting deviations from fire protection requirements.
The modification decreases the consequences of a fire and does
- not directly affect equinment required to mitigate an accident.
n There are no new failure modes i
that directly affect. safety related equipment..
M22.1-88-055
==
Description:==
This modification replaces the rod position indicators with_more dependable LED's. This includes the addition of a new RPI panel, routing of cables, and power supplies. These changes are necessary to address HED's 364 and 379.
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/sc1:ID805:23 1
- - -.. ~.. -.
.ma__,m__,., _,.
_-,.__.,.,m
,._,,,,m..,
,a,,,,,_,_____,,
,.,,w,.,,...,_,%,,,,,,_
_,y
50.59 Evaluation:
This modification does not significantly change the structural capabilities of the RPI panel or structures to which they are attached. The RPI panel and selector switches are seismically quallfled and mounted.
Interactions with other safety related equipment are mitigated by maintaining separation requirements and sneak circuit analysis.
H22-1-88-070
==
Description:==
This modification adds fiber optic cable as the communication lini between the H2500 process computer and the Prime computer to improve reliability and speed of plant data transfer.
50.59 Eveluation:
This modification provides redundant systems and increases availability and reliability of data for post-accident analysis.
The change is a communications upgrade to assure the functions of an existing system.
H22-1-88-079
==
Description:==
This modification adds inhibit circuitry to the low header pressure autostart signal for the service water and component cooling pueps and to the low-low steam generator level autostart signal for the motor driven auxiliary feedwater pumps. These circuits ensure the successful autostart of these components following a safety injection, loss of offstte power, or degraded voltage condition.
/sc1:ID805:24
50.59 Evaluation:
This modification defeats only low pressure or low-low water level autostarts during accident conditions. It does not defeat the autostarts for normal conditions or reactor trips with offsite power available. Train and division redundancy is maintained.
A failure of any of the components or features added with this modification will, at worst, increase the potential to affect valid accident autostart attempts on the modified pumps on the respective division or train. A ioss of a single division or train has been previously considered.
The features added with this modification increases the margin of safety by ensuring that low-low level or low pressure signals occurring during dead bus conditions will not result in anti-pump lockout or out-of-sequence autostarts.
H22-1-89-005
==
Description:==
This modification re-positions the "A"
auxiliary feedwater aumps remote shutdown panel sw'tcies to match the motor driven pumps configuration. These changes are necessary to address an event whereby the auxiliary feedwater pump was inadvertently started when attempting tc ttart the auxiliary lube oil pump, 50.59 Evaluation:
This modification only changes the orientation of specific components with no new equipment or logic /
circuitry changes being made. The potential for an operator to inadvertently operate the wrong switch is reduced.
/scl:101v t25
l H22-1-89-014
)
==
Description:==
This modification removes forty (40) snubbers from service located in the steam generator blowdown, component cooling, reactor coolant, safety injection, and chemical and volume control systems.
50.59 Evaluation:
Revised calculation $ have demonstrated that removal of these snubbers will not exceed stress levels for the given load combinations on these systems. The removal of these snubbers do not alter the function of the associated systems or induce stresses in excess of that allowed for ths load combinations.
H22-1-89-017
==
Description:==
This modification disables the reactor water flow controller and the boric acid flow controller makeup deviation alarms at main control board CB35 to eliminate spurious alarms caused by flow oscillations. These changes are necessary to address llED 279.
50.59 Lyaluation:
This modification does not affect any circuit required to respond to or mitigate an accident. The modtfication actually allows the operator to devote more attention to monitoring plant conditions for safety by eliminating sourious alarms. The events associated with these annunciators occur slowly and the operator has knowledge from other safety system alarms of these events.
/tc1:ID805:26
M22-1-90-503
==
Description:==
This modification replaces the existing reactor coolant pump (1C) Labyrinth seal transmitter (IPT-148) with a Rosemount transmitter.
50.59 Evaluation:
The transmitter is seismically mounted and qualified and is functionally equivalent to the replaced model. The modification does not alter system /r.omponent design functions required to mitigate an accident.
H22-1-90-505
==
Description:==
This modification adds a section of wireway between an existing cable tray and wireway to provide the necessary electrical separation required between division C/10L cables and division 17C cables.
50.59 Evaluation:
This modification does not change any system or component but simply extends an electrical raceway. The electrical raceway is seismically installed.
H22-2-84-043
==
Description:==
This modification adds circuitry for instrumentation failure indication to the control room on loss of sample flow or loss of AC power to the auxiliary building ventilation radiation monitor 2RT-PR25, 50,59 Evaluation:
The modification only increases the instrument reliability and does not alter s; stem / component design functions required to mitigate an accident.
/sc1:lD805:27
M22-2-85-042
==
Description:==
This modification replaces station battery chargers and batteries to increase the capacity and reliability 4
of the DC system.
50.59 Evaluation:
The new batteries provide almost twice the capacity of the existing batteries. The replacement batteries will perform the same function as the original batteries for a longer period of time. The voltage remains unchanged.
M22-2-85-046
==
Description:==
This modification replaces station battery chargers and batteries to increase the capacity and reliability of the DC system.
50.59 Evaluation:
The new batteries provide almost twice the capacity of the existing batteries. The replacement batteries will perform the same function as the original batteries for-a longer period of time, The voltage remains unchanged.
M22-2-86-009
==
Description:==
This modification adds a pr(ssure switch to the suction side of each of the RHR pumps. This pressure switch monitors pressure at the suction of the pump in modes 5 and 6 to prevent loss of RHR suction due to low reactor vessel level. The modification has an annunciator window.and no control function.
/scl:ID805:28 i
D 50.59 Evaluation:
This modification does not have any impact on RHR pump operation.
The instrument is located on a small diameter line on the static leg and any leak would be small in comparison with system flow. Under normal operating conditions the switch is isolated by a safety related valve. Thus, potential for such a leak is very low and is bounded by the safety analysis.
M22-2-86-016
==
Description:==
This modification removes a redundant test contact operating in parallel with a six relay contact (used in the test mode only) that autostarts the-diesel generators. This modification allows functional verification of the operability of the six relay contact to autostart its respective diesti.
50.59 Evaluation:
This modification does not affect any circuit used during non-test conditions. It decreases the probability of a diesel generator start failure due to faulty relay contacts needed for diesel generator autostarts on ESF actuation.
H22-2-86-018
==
Description:==
This modification terminates leads sending HRSS alarm signals to the control room at 2LP89 and 2LP90.in order to eliminate nuisance alarms.
50.59 Evaluation:
Annunciators provided at local panels. HRSS equipment sensed "^t safety related.
/sc1:ID805:2-.
s 4
H22-2-86-026
==
Description:==
This modification adds a drip leg and loop seal to steam jet air ejector discharge header and gland steam exhaust header to remove condensation to protect pland steam exhaust fans.
50.59 Evaluation:
The offgas system cannot cause or create an accident. This nodification would not impact the detection, by radiation monitors, of any cadionuclides into the offgas system and leakage would be isolated in the containment. The failJre of a drip leg or loop seal in the offgas system does not impact any componer.1 design-functions important to safety.
M22-2-86-035
==
Description:==
-This modification provides breaker closure indication to the process computer requence of events program for all 4kV ESF components and the 480kV RCFC's as well a a reference input for initiation of safety injection and station blackout for accurate timing purposes. This modification also installs simulated safety injection and station blackout test actuation switches to start the SI and safe shutdown timers, 50.59 Evaluation:
The modification does not affect the operation of any ESF component during non-test peilods. It only simplifies hardware and manpower requirements during the performance of a surveillance test. This modification adequately isolates and disables test switches during non-testing perir's. The computer connections cannot affect the operation of the ESF breakers or actuation relays.
/sc1:ID805:30
_ ~ _ _ _ _ __
C H22-2-87-012
==
Description:==
This modification adds comparators to pressurizer pressure loops to allow a pressurizer low pressure alarm independent of any controllers or control switches.
50.59 Evaluation:
The modification does not interact with any existing safety related equipment and only involves a non-safety related annunciator.
M22-2-87-023
==
Description:==
This nodification reroutes the instrument air supply to the penetration pressurization air dryers to ensure that the normal air supply can be predryed by the penetration pressurization air dryers prior to entering into the distribution lines.
50.59 Evaluation:
There are no new failure effects created by this modification as the sources and components required to deliver supply remain unchanged. The double (redundant) check valve are retained on the rerouted h,r lines in order to prevent air leakage to the instrument air system from the penetration pressurization system.
M22-2-87-032
==
Description:==
This modification replaces existing control room control board keylock switches with non-keylock type switches for valves 2MOV-SI8813, 2MOV-SI8814, 2MOV-CS0003, 2POV-CS0005, 2H0V-CS0007, 2MOV-SI8811A/B, 250V-RC08, 250V-RC09, 250V-RC10, 250V-RC11, and 250V-RC0101.
These changes are necessary to address HED's 79, 222, 227, 234, 392, and 435.
/sc1:20805:31
50.59 Evaluation:
This modification is electrically equivalent and in the same physical location as existing switches. This modification does not alter any operating systems or functionally change any existing control schemes.
M22-2-87-038
==
Description:==
This modification adds an isolation valve in the seal drain line for each of the RHR pumps to prevent borated water from entering the upper portion of the mechanical seal. Additionally, the lines are re-sloped to allow for proper draining.
50.59 Evaluation:
This modification does not affect the operation of the RH1 system and improves seal perfoimance, thus, decreasing the chance for seal failure. The modification improves the reliability and performance of the RHR mechanical seals.
H22-2-87-054
==
Description:==
This modification adds fire barrier walls for the auxiliary feedwater pumps.
50,59 Evaluation:.
This modification does not affect the operation of the auxiliary f- ' water pumps. These walls are sed to ensure that one fire does not affect all three auxiliary feedwater pumps.
M22-2-88-001
==
Description:==
This modification disables the automatic input to the containment evacuation alarm from the source range high flux at-shutdown alarm due to spurious olarms caused by noise spiles on the NIS source range channels.
I
/sc1:ID805:32 l-
4 50.59 Evaluation:
The containment alarm for high count rate is mentioned only in the " Dilution During Refueling" accident analysis. However, the control room operator is credited with terminating the dilution based on control room indication of an increase in count rate.
Therefore, eliminating the automatic containment alarm will not affect the consequence of the dilution accident or any other accident. Audible indication of source range count rate will l
continue to be available both in the control room and in the containment.
M22-2-88-023
==
Description:==
This modification adds the following indication to the main control boards:
steam generator narrow range level to CB08, CCH discharge header pressure to CB08, hydrogen monitoring containment isolation valves position indication to l
CB09. This modification also rearranges switches and meters in a configuration that is consistent with human i
engineering practices. These changes are necessary to address HED's B, 259, l
273, 281, 319, 335, 363, 372, 412, and 421.
50.59 Evaluation:
The rearranged switches and meters and the new indication added to the main control boards do not significantly change the structural capabilities of the panels or structures to which they are attached. All separation requirements have been maintained.
Interactions with existing circuits are mitigated through the procurement of Class IE relays and seismically qualified indicators.
seismic mounting of equipment, routing of cables through the applicable raceways, and ;.ieat circuit anolysis.
/sc1:ID805:33 1
_ _ _ _.-..... ~.
s' 4
H22-2-88-024
==
Description:==
This modification rearranges existing controls and indicators on main control boards CB08 and CB16 in a configuration that provides functional groupings of these components. This modification also rearranges other control board components consistent with human engineering practices. These changes are necessary to address HED's 8, 45, 56, 75, 80,174, 290, 335, 361, and 421.
50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events. This modification does not alter any operating systems or functionally change any existing control schemes. All relocated. equipment is seismically installed and maintains divisional separation.
H22-2-88-026
==
Description:==
This modification rearranges existing controls, switches, indicators, and scales on main control boards CB06 and CD07 in a configuration that provides functional groupings of these e
components consistent with human engineering practices. These changes are necessuy to address HED's 8,148, 157, 165, 169, 174, 261, 262, 284, 287, 323, 324, 330, 335, 358, 362, 365, 375, 383, 390, 405, 414, 420, and 440.
-50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events, This modification does not alter any operating systems or functionally change a' > axisting Untrol schtmes, i'l relocated equipment L
is selsmically installed and maintains divisional separation.
/sc1:IO805:34
M22-2-88-027
==
Description:==
This modification rearranges existing controls and switches on main control board CB03 in a configuration that provides functional groupings of these components consistent with human engineering practices. This modification also adds a guardrail on main control boards CB01 - CD04 to minimize the possibility of inadvertent switch activation. These changes are necessary to address HED's 8, 12, 101, 102, 174, and 264.
50.59 Evaluation:
This rearrangement provides for better operator recognition of plant controls during operations and unusual events. This modification does not alter any operating systems or functionally change any existing control schemes. Relocated equipment is seismically installed and maintains divisional separation.
The guardrail is seismic mounted and has no impact on any system configurations.
H22-2-88-028
==
Description:==
This modification reroutes the control cables for pressurizer power operated relief valves, letdown control valves, and excess letdown isolation control valves ( 2PCV-RC455C, 2PCV-RC456, 2LCV-RC459, and 2A0V-VC8381) from cable trays to conduit to protect these cables from hot spots or spurious shorts. These changes are necessary to address issues identified in a 10 CFR 50, Appendix R audit.
50.59 Evaluation:
This modification ensures a more conservative operation of the designated valves in the event of a fire by separating cables into individual conduit and thus allowing operators to disconnect power to these valves from the main control board.
/sc1:10805:35
.. _ - _ - _.. _ _ _. _. _ _ _ _. ~.... _. _
M 4.
4 H22-2-88-030
==
Description:==
This modification adds a seal-in feature to control circuits of extraction steam valves 2H0V-ES0001, 2HOV-ES0002, 2HOV-ES0003, 2HOV-ES0004, 2HOV-ES0005, 2HOV-ES0006, 2HOV-ES0007, 2H0V-ES0008, 2HOV-ES0009, 2HOV-ES0010, and 2H0V-ES001). These changes are necessary to address HED's 226 and 378.
j 50.59 Evaluation:
-This modification does not affect L
any circuit required to respond to or mitigate an accioent. The modification actually. allows the operator to devote more attention to monitoring plant. conditions for safety because of the momentary time-to initiate valve travel when required.
H22-2-88-042
==
Description:==
This modification disables failed pressurizer heater: elements.
50.59 Evaluation:
This modification does not represent a change in the basic design or. function of this system.
Pressurizer heaters are not required to mitigate an accident nor impact.on equipment important 1
to safety.
M22-2-88-069
==
Description:==
This modification removes va lous snubbers from service located in the steam generator blowdown, component cooling, reactor coolant drain, safety injection, and chemical and~ volume control systems.
I 4
/sc1:ID805:36
50.59 Evaluation:
Revised calculations have demonstrated that renoval of these snubbers will not exceed stress levels for the given load combinations on these systems. The renoval of these snubbers do not alter the function of the associated systems or induce stresses in excess of that allowed for the load combinations.
M22-2-88-070
==
Description:==
This modification adds fiber optic cable as the communication link-between the H2500 process computer and the Prime computer to improve reliability and speed of plant data transfer.
50.59 Evaluation:
This modification provides redundant systems and increases availability and reliability of data for post-accident analysis.
The change is a communications upgrade to assure the functions of an existing system.
M22-2-88-079
==
Description:==
This modification adds inhibit circuitry to the low heater pressure autostart signal for the i.ervice water and component cooling pumpg and to the low-low steam generator Itvel autostart signal for the rotor driven auxiliary feedwater nevo'.. These circuits ensure the esetessful autostart of these e;51ponents following a safety injection, loss of offsite power, or degraded voltage condition.
/sc1: ID805:37
e 50.59 Evaluation:
This modification defeats only low pressure or low-iow water level autostarts during accident conditions. It does not defeat the autostarts for normal conditions or reactor trips with offsite power available. Train and division redundancy is maintained.
A failure of any of the components or feat';res added with this modification will, at worst, increase the potential to affect valid accident autostart attempts on the modified pumps on the respective division or train. A loss of a single division or train has been previously considered.
The features added with this modification increases the margin of safety by ensuring that low-low level or low pressure signals occurring during dead bus conditions will not result in anti-pump lockout or out-of-sequence autostarts.
M22-2-89-004
==
Description:==
This modification adds timers for the source range high flux at shutdown alarm circuit to reduce spurious alarms, 50.59 Evaluation:
The timer allows for better cperator recognition of events by reducing spurious alarms. The alarm still performs its intended function for the required event (a reactivity addition accident while shutdown) which is not impacted by a time delay of a few seconds.
H22-2-89-005
==
Description:==
This modification re-positions the "A"
auxiliary feedwater pumps remote shutdown panel swi;thes to match the motor driven pumps configuration. These changes are necessary-to address an event whereby the auxillary feedwater pump wa> inadvertently started when attempting to start the auxiliary lube oil pump.
/sc1:ID805:38 e"79Tw-&yw Pmm
+'
'TN-+
=
M'--- - * ' -t4+'d9-"v-*
+-'""* - - ^ - - '4""-'
r
?-
c-- - - -
3,-.
50.59 Evaluation:
This modification only changes the orientation of specific components with no new equipment or logic /
circuitry changes being made. The potential for an operator to inadvertently operate the wrong switch is reduced.
M22-2-89-017
==
Description:==
This modification disables the reactor water flow controller and the boric acid flow controller makeup deviation alarms at main control board CB35 to eliminrte spurious alarms caused by flow esc 111ations. These changes are necessary to address HED 279.
50.59 Evaluation:
This modification does not affect any circuit required to respond to or mitigate an accident. The modification actually allows the operator to devote more attention t
...nitoring plant conditions for
. rety by eliminating spurious alarms. The events associated with these annunciators occur slowly and the operator has knowledge from other safety system alarms of these events.
H22-2-89-019
==
Description:==
This modification replaces the present stem sealing system on the pressurizer l
spray valves with a live loading mechanism and packing configuration to avoid packing leaks which have led to forced outages.
50.59 Evaluation:
This modification does not affect the valves ability to perform its intended function. The packing
~.s non-safety related and failure of the packing would only account for minor amount of lealage.
/sc1:!D805:39
H22-2-90-507
==
Description:==
This modification retrains and reconnects cable #33250, #21482, and
- 31735 to meet cable separation criteria. These changes are necessary to address discreptqcies identified during the NRC Safety Systems Outage Modifica+1on Inspection audit.
50.59 Evaluation:
Retraining and reconnecting cables restores required train separation, thus, increasing the reliability of these systems during events. This modification eliminates or reduces the previous failure mode of possible interaction between divisions.
/ sci:ID805:40 l
l
2.
Tests:
There were no tests conducted that involved a change in the Technical Specifications, FSAR, or created an unreviewed safety question.
3.
Experiments:
There were no experiments conducted that involved a change in the Technical Specifications, FSAR. or created an unreviewed safety question.
4.
Other Safety Evaluations:
A.
Temporary Alterations:
TA-90-001
==
Description:==
Temporary alteration bysassing Unit I valves IFCV-IA01A/B wit 1 a hose to leak test valves without losing instrument air to the containment. This allows PORV's to remain operable during test.
Date Installed: 01/06/90 Date Removed: 01/07/90 50.59 Evaluation:
Containment isolation capability is not required in nodes 5 or 6.
Valves are restored to operable status prior to entry into mode of applicability.
TA-90-002
==
Description:==
Temporary alteration to install blind flange on component cooling pump suction. This will achieve isolation on suction line during maintenance and repairs.
Date Installed: 01/25/90 Date Removed: 03/01/90 50.59 Evaluation:
One pump and one heat exchanger can be Inoperable indefinitely without affecting single mode failure, Suction valve it closed to assure isolation. F1onge is installed only as seconda y isolation.
/sc1:lD805: 41 n-
_m. _
TA-90-013
==
Description:==
Temporary alteration enabling radiation monitor alarm 1RT-PR26. Different terminal boards are use to ensure that the high radiation alarm and instrument failure alarm remain operable.
Date Installed: 02/26/90 Date Removed: 03/09/90 50.59 Evaluation:
This temporary alteration ensures that the function of the radiation monitor alarm remains operable. No monitors that affect safety are changed.
TA-90-016
==
Description:==
Temporary alteration blocking open Unit 2 service air isolation valve 2FCV-SA01A into the containment.
Alteration to provide an uninterruptable supply of air for outage work.
Date Installed: 03/16/90 Date Removed: 05/18/90 50.59 Evaluation:
Containment isolation capability.
is not required in modes 5 or 6.
Valve is restored to operable status prior to entry into node of applicability.
TA-90 017
==
Description:==
Temporary alteration blocking open Unit 2 service air isolation valve 2FCV-SA018 into the containment.
Alteration to provide an uninterruptable supply of air fr.-
outage work.
Date Installed: 03/16/90 Date Removed: 05/18/90 50.59 Evaluation:
Containme-+ isolation capability is not req. ired in modes 5 or 6.
Valve is restored to operable status prior to entry into mode of applicability.
/sc1:10805:42
l TA-90-018
==
Description:==
Temporary alteration blocking open Unit 2 valve 2FCV-FP08 to assure system function during outage work.
Date Installed: 03/16/90 Date Removed: 05/18/90 50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6.
Valve is restored to operable status 3rlor to entry into mode of applica)111ty.
TA-90-021
==
Description:==
Temporary alteration blocking open Unit 2 containment sump discharge isolation valves and by)assing containment sump pump interloci.-This permits operation of the containment sump pumps during the outage by holding valves open during loss of power while ESF bus drop testing is underway.
Date Installed: 03/22/90 Date Removed: 05/18/
50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6.
Valves are restored to operable status 3rior to entry into mode of appilca) titty.
TA-90-022
==
Description:==
Temporary alteration bypassing the containment isolation function on Unit 1 instrument air isolation valves IFCV-IA01A/B into the containment.
Alteration to provide an uninterruptable supply of air for outage work.
Date Installed: 03/14/90 Date Removed: 03/16/90 50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6.
Valves are restored to operable status prior to entry into mode of applicabi11ty.
/sc1:lD805:43 c
O TA-90-024
==
Description:==
Temporary alteration to renove/ replace plate from a roof penetration on the fuel Building and install seal to allow eddy current test cables, plugging control cablei, and sleeving control cables to pass through.
Date Installed: 03/19/90 Date Removed: 05/17/90 50.59 Evaluation:
Although the temporary hole would be sealed, the lower pressure in the fuel Building would draw any air leakage into the Fuel Building and would not allow an uncontrolled release.
TA-90-026
==
Description:==
Temporary alteration utilizes the power feed supporting the Unit 2 control rod drive (28) ventilation fan. The control rod drive ventilation fan, which ventilates the control rod drive mechanism on top of the Unit 2 reactor, l
is inoperable during this time.
Additionai power was needed inside the containment during refueltag and maintenance activities.
Date Installed: 03/17/90 Date Removed: 06/13/90 50.59 Evaluation:
This control rod drive ventilation fun is not required to be operable during reactor shutdown. The fan is not part of the ESS system.
I
/sc1:10805:44
p TA-90-027
==
Description:==
Temporary alteration utilizes the power feed supporting the Unit 2 control rod drive (2A) venti ation fan. The control rod drive ventilation fan, which ventilates the control rod drive mechanism on top of the Unit 2 reactor, is inoperable during this time.
Additional power was needed inside the containment during refueling and maintenance activities.
Date Installed: 03/17/90 Date Removed: 06/13/90 50.59 Evaluation:
This control rod drive ventilation fan is not required to be operable 1
during reactor shutdown. The fan is not part of the ESS system.
TA-90-030
==
Description:==
Temporary alteration to provide temporary power feeds for fuel handling radiation monitors during installation of RMDS.
L Date Installed: 03/28/90 Date Removed: 04/26/90 50.59 Evaluation:
Radiation monitoring capabillty is
(
not required in modes 5 or 6.
These nonitors are restored to operable status prior to entry into mode of applicability.
TA-90-031
==
Description:==
Temporary alteration bypas'ing the containment isolation function of the Unit 2 instrument air isolation valves 2FCV-IA01A/B while maintaining the instrument air function to containment.
N e Installed: 03/28/90 Date Removed: 03/31/90 50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6.
Valves are restored to operable status prior to entry into mode of applicability.
/scl:10805: 45 l
TA-90-033
==
Description:==
Temporary alteration to fail close isolation dampers for the Unit 0 diesel generator room ventilation fan, the service water area ventilation fan (OAN), and the auxiliary building exhaust fan (OD) during Bus 247 outage.
Date Installed: 04/17/90 Date Removed: 04/23/90 50,59 Evaluation:
All dampers are placed into their isolated positions, Redundant ventilation systems will supply fan functions to requ! red equipment and out-of-vsrvice times are adhered to.
TA-90-034 Dest iption:
Temporary alteration to fail close isola.tlon dampers for the Unit 2 diesel generator (2B) room ventilation fan, the service water area ventilation fan (OCN), the auxiliary building exhaust fan (0F), the auxiliary building supply fan (OC), the auxiliary building charcoal booster fan (OC), and the control room HVAC unit (08) during Bus 249 outage.
Date Installed: 04/05/90 Date Removed: 04/08/90 50.59 Evaluation:
All dampers areLplaced into their isolated positions Radundant ventilation systek
supply i
fan functions to rey,,ed equipment and out-of-service times are adhered to.
TA-90-035
==
Description:==
Temporary alteration
- ail close isolation dampers fc.
ne Unit 2 diesel generator (2A) room ventilation fan, the service water area ventilation-fan (ODN), the auxiliary building exhaust fan (CE), and the auxiliary building charcoal booster fan (OC) during Bus 248 outage.
Date Installed: 05/15/90 Date Removed: 05/17/90
(
/scl:ID805:46 l
50.59 Evaluation:
All dampers are placed into their isolated positions. Redundant ventilation systems will supply fan functions to required equipment and out-of-service times are adhered to, r
TA-M "
bescription:
Temporary alteration to install globe valves on the service water pumps centrifugal separator drain header.
This alteration is necessary to provide the ability to control the packinq lube i,
water pressure more effectively.
Date Installed: 05/13/90 Date Removed: N/A 50.59 Evaluation:
The addition of the globe valves on the drain line header will not change the normal function of the drain line. Fail ~e of the valves 7
will not affect the pump operetion.
TA-90-038
==
Description:==
Temporary alteration to 4kV ESF Bus 247 breaker-control by specifically preventing non-synchrone.s closure of breaker 2471 upon trip of breaker 2424 with diesel generator "0" running unloaded and permitting normal operation of breaker 2473 by completing control circe try.
Date Installed: 04/08/90 Date Removed: 04/19/90 50.59 Evaluation:
This temporary altL ation does not change the-circuit configuration as previously evaluated. It reduces the possibility of non-synchronous closures of breakers and insures operability of the breaker and thus the diesel ge ne r a tc,r.
/scl:ID805:47 l
l J-
~ _. _
4 1
TA-90-039
==
Description:==
Temporary alteration to 4kV ESF Bus 248-
- breaker control by specifically preventing non-synchronous closure of
' breaker 2483 upon trip of breaker 2434 with diesel generator "2A" running.
unloaded.
4 Date Installed: 04/08/90 vate_ Removed: 05/18/90L 50.59 Evaluation:
This temporary alteration does not change the circuit configuration as.previously evaluated. It reduces _the poss'Lility of non-synchronous closures of breakers and insures operability of the breaker and thus the diesel-generator.
-TA-90-040-e
Description:
Temporary alteration-bypassing the containment isolation function on Unit 1 instrument air isolation valves IFCV-c IA01A/B into the' containment.
Alteration'to provide an uninteruptable supply of air for outage work, 10 ate.In~ stalled: 04/18/90 Date Removed: 04/29/90-50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6..
Valves are restored to operable-status prior to entry into mode of r
applicability.
1 LTA-90-042
Description:
Temporary alteration deactivates the
. permissive. circuitry for the operation of.a " loop bypas; valve open"
- nnunciator. This ts'necessary to facilitete LSIV (loop D) repair.
- Date Installed
- 04/19/90
. Date Removed: 05/04/90 3
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50,59 Evaluation:
.The-temporary alteration only affects the annunciator and does not affect any control or_.
Interlock functions. Reactor protection is not' required while in mode 5. Overpressure protection
~!
is not required because the plant is in mid-loop operation.
TA-90-045 Pescription:
Temporary alteration to remove / replace plate from'a roof penetration on the Fuel Building and install seal to allow plugging control cables to pass through, Date Installed: 04/27/90' Date Renoved: 05/16/90 50,59 Evaluation:
Although the temporary hole would'
'be sealed, the lower pressure in Lthe fuel Building would-draw any air-leakage into the fuel Br?iding and would not allow an uncontrolled release.
TA-90-046'
==
Description:==
This temporary alteration' deactivates the reactor coolant. pump (10) Number 2 seal standpipe' level alarm to prevent' nuisance. alarms during loop D RCP and
- LSIV repairs,-
,Date: Installed: 04/25/90' Date Removed: 05/24/90 50.59 Evaluation;-
The reactor coolant pump standpipe alarms:are not required until reactor' coolant pump is running a
and areErestored prior to-
. operation of the-pump.-
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TA-90-048
==
Description:==
Temporary alteration adds two demineralized flushing water isolation valves in the primary sample room chiller package to provide for isolation of the chiller package during repairs. This temporary alteration is provided until ininor modification makes valves permanent.
Date Installed: 05/03/90 Date Removed: 11/30/90 50.59 Evaluation:
These new isolation valves are installed to provide isolation of the chiller package during repairs. The temporary alteration did not alter the functional requirements of the chiller package.
TA-90-049
==
Description:==
Temporary alteration to use spare contacts for containment isolation yhlve 250V-PR26D.
Date Installed: 05/12/90 Date...maved: 05/15/90 50.59 Evaluation:
The temporary alteration ensures that the valve performs its intended safety function. The use of these spare contacts do not alter the normal capability of the valve.
TA-90-052
==
Description:==
Temporary alteration adds a temporary line to reroute Unit 1 beric acid injection tank (BIT) outlet valve leakage to the recctor coolant drain tank via relief valve. This prevents leakage from thermally cycling BIT cold leg injection lines.
Date Installed: 05/18/90 Date Removed: N/A
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4 50.59 Evaluation:
The rerouting affects the BIT cold leg injection flow transmitter.
However, this flowmeter is used for indication only. During normal operation, leakage of up to 10 gpm would result, but such leakage in containment is boanded by safety analysis.
TA-90-053
==
Description:==
Temporary alter -
' dis a temporary line to rercute Unit 2 ooric acid injection tank (BIT) outlet valve leakage to the reactor coolant drain tank via relief valve. This prevents leakage from thermally cycling BIT cold injection lines.
Date Installed: 06/09/90 Date Removed: N/A 50.59 Evaluation:
The rerouting affects the BIT cold leg injection flow transmitter.
However, this flowmater is used for indication only. During normal operation, leakage of up to 10 gpm would result, but such leakage in containment is bounded by safety analysis.
TA-90-055
==
Description:==
Temporary alteration bypassing the containment isolation function of the Unit 1 instrument air isolation valves 1FCV.801A/B wnile maintaining the instrument air function to containment.
Date Installed: 05/24/90 Date Removed: 06/01/90 50.59 Evaluation:
Containment isolation capability is not required in modes 5 or 6.
Valves are restored to operable s..atus prior to entry into mode of applicability.
/sc1: ID805:51
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TA-90-060
==
Description:==
Temporary alteration disables the -.
electrical-input to t N Unit.l service water strainer-bachash valves (in the normally closed position)'. These valves-are manually opened when backwashing is necessary. Silt accumulates around the valves causing excessive-packing leaks when-attempting to stroke-the valves and the motor operators do not_ fully open the valves when backwashing.
Date'-Installed: 10/22/90 Date Removed: N/A 50.59 Evaluation:
These valves _are required to operate only during backwashing of the strainer baskets and are normally in the-closed position.
These valves do not provide an isolation-function. Isolativn is provided_during an accident to'the common drain header using other isolation valves.
TA-90-061
==
Description:==
Temporary alteration disables the
-e Rctrical input to the' Unit 2 service water strainer backwash valves (in the normally closed position). These. valves.
are manually opened when:backwashing is-necessary.;Sil_t accumulates around the
-valves causing excessive packing leaks
-when-attempting to stroke-the-valves and the motor operator _s do not fully ~
open the valves when backwashing.=
Date Installed: 10/22/90 Date Removed: N/A 50.59 Evaluationi These valves are required ~to operate only'du-:ri backwashing of the strainer ba b t and are normally in the closed position.
These valves do not provide an isolation function. Isolation is provided during an accident to the common drain-header using other isolation valves,
/scl:ID805:52.
I
l TA-90-062
==
Description:==
Tempcrary alteration lifting leads to incore thermocouple (M-10) indication on Unit 1. This thermocouple indicates core exit temperature above core location M-10 and has been intermittently indicating high, causing problems with subcooling monitoring.
Date Installed: 06/18/90 Date Removed: 08/31/90 50.59 Evaluation:
Sufficient redundancy remains in the core exit thermocouple system to provide adeauate monitoring.
This failure of the thermocouple and subsequent disabling does not affect operation of the subcooling nonitor.
==
Description:==
Temporary alteration disables the motor operator brake for the RHR pump discharge crossover to cold leg injection line isolation valve (2MOV-RH8716A). The motor brake offers little assistance in preventing internal effects when seating the valve.
Date Installed: 07/08/90 Date Removed: N/A 50.59 Evaluation:
The temporary alteration does not degrade the valves ability to function nor affects its performance, reliability, response time, automatic actuation, or failure mode.
TA-90-065
==
Description:==
Temporary alteration disables the motor operator brake for the RHR pump discharge crosscve' to cold leg injection line is>lation valve (2MOV-RH8716C). 'he motor brate offers little assistar.ce in prrventing internal effects when seating the valve.
Dat-Tnstalled: 07/08/90 Date Removed: N/A
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50.59 Evaluation:
The tempoiary alteration does not degrade the valves ability to function nor affects its performance, reliability, response i
time, automatic actuation, or failure mode.
TA-90-066
==
Description:==
Temporary alts : tion installs a valve bonnet on manual :e??a 2CS0020 to act as a pressure bounusry. The function of the valve is to isolate NaOH to the 2B containment spray eductor for iodine removal.
Date Installed: 07/10/9)
Date Rems
- N/A 50.59 Evaluation:
The valve block will not prohibit the supply of Na0H The originally de'.lgned valve bonnet will provide th( sealing characteristics and the 2B containment spray train is available for todine removal.
TA-9n.^58 s !sciption:
.emporary alteration to replace a reactor vessel level instrumentation system RTD with a different RTD model Date Installed: 07/13/90 Date Removed: 08/18/90 5C.59 Evaluation:
This change has no effect on the normal function of the RTD. The RTD is used for indication only.
TA-90-069'
==
Description:==
Temporary alteration lifting leads to incore thermocouple (M-12) indication on Unit 2. This thermocouple indicates core exit temperature above core location M-12 and has failed, giving false high and low indications.
Date Installed: 07/14/90 Date Removed: 10/09/90
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50.59 Evaluation:
Sufficient redundancy remainsfin the core exit thermocouple _ system to provide adequate monitoring.
o This f ailure of. the thermocouple and subsequent disabling-does not-affect' operation of the subcooling moniter.
TA-90-070
==
Description:==
Temporary alte*ation prevents Unit 2 relief valve 2VOR1?0 19-the_ chemical and volume control system from performing its normal fun: tion. The temporary change _-is necessary.to determine if H2 gas is leaking by_the relief-valve and to reseat the relief valve if there is leakage.
Date Installed: 07/14/90 Date Removed: 07/14/90 50.59_ Evaluation:
Rupturing of,the VCT has been previously evaluated. Constant surveillance of VCT pressure-ensures overpressure protection-during temporary alteration-installation.
TA-90-071
- .1
==
Description:==
-Temporary alteration replaces.ITT Grinnell hydraulic snubber _1MSRS-150-20 (designed _with a remote reservoir) with a
an-upgraded designsthat-has-an1 integral reservoir. The old tubing _ls: capped.-
Date~ Installed: 07/14/90' Date Removed:'N/A
=
- 50.59~ Evaluation:
The temporary alteration only
. replaces snubber vith a-different-type _The replacement snubber maintains the same level of_
j u '
protection.
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TA-90-072
==
Description:==
Temporary alteration bypasses the high pressure side sensing line for Unit I steam generator feedwater loop C steam flow transmitter 1FT-522. The sensing line exhibits symptoms of a clogged line causing false alarms at full power operation, Date Installed: 07/17/90 Date Removed: 09/10/90 50.59 Evaluation:
The tempcary alteration does not change the function of 1FT-522 as it will be connected to the "Lo" side of it.T-529. The number of operable channels for reactor protection and safeguard actuation is maintained.
TA-90-076
==
Description:==
Temporary alteration lifting leads to incore thermocouple (H-05) indication on Unit'2. This thermocouple indicates core exit temperature above core location H-05 and has failed, giving false high indications.
Date Installed: 08/17/90 Date Removed: 10/09/90 50.59 Evaluation:
Sufficient redundancy remains in the core ex1.t thermocouple system to provide adequate monitoring.
This failure of the thermocouple and subsequent disabling does not affect operation of the subcooling monitor.
TA-90-080
==
Description:==
Temporary alteration lifting leads to incore thermocouples (A-11, D-03, K-03, M-05, M-10, and M-13) indication on Unit 1. These thermocouples indicate core exit temperature above core locations A-11. D- 03, K-03, M-05, M-10, and M-13, respectively, and has failed, giving false high and low Indications, Date Installed: 08/31/90 Date Removed: N/A
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3 50.59 Evaluation:
Sufficient redundancy remains in the core exit thermocouple system to provide adequate monitoring.
These failed thermocouples and subsequent disabling does not affect operation of the subcooling monitor.
TA-90-084
==
Description:==
Temporary alteration disables the circulating water pump trip on high delta (P) across screens on 1PDS-CH41, 1PDS-CH42, ana 1PDS-CH43. This is necessary to prevent loss of electrical power to the PDS as a result of flooding in the cribbouse.
Date Installed: 09/11/90 Date Removed: 09/13/90 50.59 Evaluation:
The circulating water system is not used to mitigate the consequences of a radiological accident and no equipment important to safety is involved, TA-90-088
==
Description:==
Temporary alteration lifting leads to incore thermocouples (C-13, F-15, H-05, J-07, L-14, and M-12) indicition on Unit 2. These thermocouples indicate core exit temperature above core locations C-13, F-15, H-05, J-07, 1-14, and M-12, respectively, and has failed, giving false high and low indications.
Date. Installed: 10/09/90 Date Removed: 11/01/90 50.59 Evaluation:
Sufficient redundancv remains in the core exit thermc;oucle system to prov1(le adequate monitoring.
These failed therr.occuples and subsequent disablina does not affect operation ci the subco ding monitor.
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TA-90-089
Description:
Temporary alteration disables fire protection-deluge for' Unit 2 Areas 2-fi, 2-F2, and 2-F3 due to the-failure of the main power transformer (2H).
These are fire-detectors / sensors for the main power-transformers 2E,.2H, and unit auxiliary transformer 241.
l Date Ihstalled: 09/23/90 Date Removed: 11/01/90 50.59 Evaluation:
The deluge system for the
' transformers are not required during the time that.the transformers.are'not in operation.
TA-90-093
Description:
Temporary alterationLdisables: control room HVAC air-handler outlet' damper OFCV-PV22 to a-failed closed position.
The temporary alteration will prevent-
~the-damper from falling open when fan
- (air handler); breaker is d -energized.
during air handling-filte: change-out.
7
- Date-Installed: 11/07/90 Date Removed:- 11/26/90 l50.59 Evaluation:
The air' handlers are Lout-of-service for the duration of the~ temporary alteration. The resulting short--'ctreutting of> air flow-through the:.non-running HVAC
= unit would not'significantly.
effect control.-room temperature-conditions.
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.s TA-90-098
==
Description:==
Temporary r<teration lifting leads to incore th', mocouples (C-13, F-15, G-08, H-05, 3 v7, L-14, M-12, and N-08) indic.tlon on Unit 2. These therDocouples indicate core exit tem erature above core locations C-13, F-,5, G-08, H-05, J-07, L-14, M-12, and H 08, respectively, and has failed, giving false high and low indications.
Date Installed: 11/01/90 Date Removed: N/A 50.59 Evaluation:
Sufficient redundancy remains in the core exit thermocouple system to provide adequate monitoring.
These failed thermocouples and subsequent disabling does not affect operation of the subcooling nonitor. The temporary alteration will leave at least 4 thermocouples per quadrant per train as specified in-NUREG-0737 which is an adequate number to satisfy safety related thermocouple functions.
TA-90-109
==
Description:==
Temporary alteration disables the isolation valve from the boric acid evaporator to the waste gas analyzer to prevent operation of the solenoid valves OHG-934K and OHG-934L from opening and causing a gas release. The beric acid evaporator has been decommissioned and the valves no longer are required to operate for gas sampling. The temporary alteration ensures adequate isolation of the line.
Date Installed: 12/29/90
-Date Removed: N/A i
- /sc1:ID805:59 i
't 50.59 Evaluation:
A radioactive gas release is prevented by de-energizing the solenoids and ensuring an adequate isolation boundary from the automatic gas analyzer. The temporary alteration does_not effect the gas analyzer nor disables or effects the other components which are sampled by the gas analyzer.
TA-90-Ill
==
Description:==
Temporary alteration replaces the 2A EDG cranitase atmospheric vent spark / flame arrester element with a wire mesh screen and rain hood to maintain the-rodent / bird barrier. The temporary alteration affects the-normal function to diffuse any flame front as a result of a crankcase explosion.
Date Installed: 12/26/90 Date-Removed: N/A 50.59 Evaluation:
This temporary alteration affects
-no equipment that will increa:a the consequence of an accident.
The temporary alteration eliminates high crankcast pressures resulting from ice formation in the flame arrester and therefore reduces the consequences of a malfunction of equipment important to safety.
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Miscellaneous Onsite Reviews:
OSR 001-90
==
Description:==
This Onsite Review documents the use of a carbon spacer for a valve packing configuration to valve IMOV-RH8702.
50.59 Evaluation:
The spacer is added to improve packing reliability. It has no affect on the valve's ability to stroke. The spacer addition results in no adverse conditions that would affect equipment malfunction. The change reduces the potential for packing failure resulting in RCS leakage, OSR 012-90
==
Description:==
This Gnsite Review doce.-air the use of a different type of compe.; ut cooling pump ditrharge pressure gaJge isolation valve.
50.59 Evaluation:
The use of a givoe valve in place of a gate valve for isolation of a pressure gauge on a 150# system is functionally equivalent. The globe valve will not increase the probability or consequences of any active or passive failure cf the co.nponent cooling system.
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