ML19345G541
| ML19345G541 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/01/1981 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML19345G540 | List: |
| References | |
| NUDOCS 8104070489 | |
| Download: ML19345G541 (14) | |
Text
73 L) s FACILITY CHANGES, TESTS. AND EXPERIMENTS Facility Changes 6
FC-1 1 This change consisted of routing a thermostatically controlled heating duct to the Exterior Cable Penetration Room. The duet is tied into the Plant culti-r zone hesting unit to provide heated air to maintain the Penetration Room above freezing temperatures in the vinter. Also, a combination security / cold air barrier at the outside vall of the Penetration Room underneath the centain=snt building transite skirt vall was installed.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC h72 This change consisted of adding a du==y load to the static inverter utilized for providing 115 VAC to the instr =nent and control components in the Reactor Centain-ment Supply Isolation Valve Sche =e; this sche =e's power source is the 125 VDC station battery.
The reason for t. tic change was to add stability to the inverter. Prior to the addition of the dw:=y load, the inverter was loaded to only 6.h% of its capacity; resulting in increased harmonic content in the output and creating susceptibility to tripping and internal component damage with minor changes in output loading.
The du==y load addition requires the inverter to operate at approximately 60% of rated capacity, reducing har=onic content and rendering the inverter ic=une to
=inor changes in output loading.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC L82-This change consisted of relocation of the discharge canal sample piping to allov maintenance accessibility to the sample collector, which had been inhibited by security requirements. The sample piping was moved from the vest to the east side of the canal.
In eddition, those portions above the lake level vere insulated and heat traced.
13e Safety Evaluation concluded that the change did not constitute an unreviewed '
safety question. The piping was moved to improve convenience and heat traced 1to. increase availability. The function of the piping vas' not changed or impaired.
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Facility Changes (contd)
FC h8h This change consisted of providing a h80V, 3 phase power source to the office addition corridor. This power is for the purpose of running portable electric heaters during the vinter months. The power is taken from one of the velding outlets in the Machine Shop, with a 50A breaker installed for protection.
The Safety Evaluation concluded that an unreviewed safety questions does not exist.
IFC-h85 This change consisted of installing additional cathodic protection anodes between the south end of the screenhouse and Office buildings to protect local under-ground piping and tanks.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC h86 This change consisted of removing a ventilation exhaust fan and intake structure from the Plant stockroom outside vall. The openings were covered with matching siding.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC h87 This change consisted of the insta ocion of a seal-in' circuit into each of four (h) containment isolation valve control circuits. The above four (h) control circuits
" dictate the operation _of nine (9) containnent isolation valves. These valves are CV h091, CV h092, CV-h093, CV h027, CV-h117, CV h102, CV h103, CV h031, and C7 hC25:
The seal-in circuit consists of a relay, a momentary contact _ push but*.on switch and'an indicating la=p.
The relay, when energized via the nocentary contact push button, seals in the valve. control circuitry. Relay 1-opout occurs either upon an isolation signal or loss of voltage to the valve circuitry. The lamp, when illuminated.. indicates that the circuit is nor=al (energized).
The' purpose of this modification is to prevent automatic reopening of the above isolation valves when a containment isolation ' signal clears.
Specification Field Change 001 vas perfor=ed in con, nction with this Facility Change.
s 7acilit'/ Changes (contd) 3 FC h87 (centd)
The Safety Evaluatf n concluded that this change did not constitute an u-aeviewed safety question.
FC h89 This change consisted of the addition of a 3abecek and Wilecx accoustical valve
=cnitoring syste= to provide positive indication of steam dru= safety relief valve opening / failure to close. This =odification was =andated by Section 2.1.3a of NUEEG 0578.
Set Point Changes80-020 and 80-023 and Specification Field Change 8C-011 vere perfor=ed.'.n conjunction with this Facility Change.
The Safety Evsluatien concluded that this change did not ccnstitute an unreviewed safety question.
FC h91 This change consisted of the addition of public address syste= cc=ponents for these areas identified as being =arginal in audibility during a Plant site e=ergency siren actuation test perfor=ed as a result of IE Sulletin 79-13. After installa-Sion of the ec=ponents, another siren actuation test vas performed in which i
audibility was acceptable.
' The Safety Evaluatien concluded that this change did not constitute an unreviewed safety question.
FC h92 This change consisted of the addition of a 15 kv, 7.5 ch= neutral reactor en the
=ain atation transfor:er to limit fault current and consequent damage. Installa-
~ tien also included the a? tion of a 15 kv lightning arrester between the reactor and transfor=er vinding.
'This change was dee=ed necessary because investigation by Consu=ers Fever Cc=pany's Electrical Engineering Depart =ent indicated that the Big Ecek Point transformer was inherently.veak in short circuit withstand capability. The neutral;reacter will reduce the short circuit duty and hence the probability of transfor er failure due to a;short circuit.
- The Safety Evaluation concluded that this change did not censtitute an unreviewed safety question.
s Facility Changes (contd) h FC-h93 This change consisted of adding a stack gas effluent high range radiation =onitor and a containment high range radiation monitor. These =onitors were installed as a result of the TMI short ter= lessons learned.
The stack gas monitor consists of a lead brick shielded detector set next to the stack gas sample line in the -advaste area. The containment monitor is a detector located close to the sphere vall in the Exterior Penetration Roc =. Both monitors read out in the Operations Support Center.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC h9h This change consisted of installing six (6) sample taps on the condenser air ejector jet bok and two on the jet box drain. The taps consist of a valve, which is capped while not in use, and a weld-o-let or pipe tee, depending on the application. These ' taps allow operations to deter =ine water levels in the jet box and whether the drains are operating correctly.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC-h95 This change consisted of the installation of a radio co==unication syste= in direct contact with the Energency Operations Facility located in Boyne City, as required by NURIG 0578. The system consists of an antenna coaxial antenna line, a re=ote control. station and a transmitter. Power is supplied via the site e=ergency inver system to ensure operability at all times ~
The ' Safety Evaluation concluded that there was not an unreviewed safety question.
The additional load imposed on the emergency bus is within the capabilities of
'the diesel generator and the tire barrier broken to perfor= this modification was
_ repaired to its previous protective condition.
FC h96 This. change consisted ~ of the construction of a new entry way into the Shift Supervisor's office.. This entry way 'was located on the vest end of the north vall directly across the hall fro = the Control'Roo=.
.A nev metal door and frame vsc installed and the ~ existing door on the vest vall vas locked and the door handles re=oved.
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Facility Changes (contd) 5 FC h96 (contd)
The purpose of this change was to provide an entrance into the Shift Supervisor's office which would be at safe radiation levels during a nuclear accident condition.
The original door location did not neet this requirenent.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
FC-507 This change consisted of installing two (2) additional overhead light fixtures and a 120 volt A-C outlet in the Receipt Inspection Area of the Stockroom. The
. additional lighting and outlet vere provided to aid Quality Centrol personnel in their receipt inspection. tasks.
1 The Safety Evaluation concluded that this change did not constitute an unreviewed safety question-4 r
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Specification Field Changes 6
SFC 80-001 This change consisted of the exchanging of the colored '. ens caps on the indicat-ing la=ps installed via Facility Change FC h87 The existing a=ber lens caps were. exchanged fer white lens caps. This was done to be consistent with Consu=ers Fever Company station standards; a white light indicates a nor=al condition and the lamps in Facility Change FC h87, when illu=inated, indicates
~the circuit energized and nor=al.
This Specification Field Change was perfor=ed in conjunction with Facility Change FC-h87 The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 80-002-This change consists of the exchanging of the colored ens caps on the indicat-ing la=p installed via Facility Change FC-392. The existing amber lens cap was exchanged for a white lens cap. This was done to te consistent with Consu=ers Fever Company station standards; a white lens indicates a n;.~al condition and the la=p in Facility Change FC-392, when illuminated, indicaces 125 volt D-C syste= normal.
This Specification-Field Change was 9erfor=ed in conjunction with FC-392 which was co=pleted in 1979 and described in the previous annual report.
Se Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 80-003 This change allows supervision of the audible alar = circuit of the Fire Cetection Syste= ty relocation of a terminating resistor. The change ter=inates the circuit at end of line _ rather than source, providing supervisien. This SFC vas perfor=ed in conjunction with Facility Change FC L625, remaining portions of which
- vill not'be completed until the 1961 calendar year.
- The Safety Evaluation concluded the.t this change did not constitute an unreviewed safety question.
SFC 80-00k
~his change consisted 'of replacing hard wired indicating lamps on the Peactor
-Eepressurization System uninterruptable power supplies (UPS), with plug-in. type
Specification Field Changes (centd) 7 SFC 80-00h (ecntd) necn bulbs. This change facilitates changing la=ps en-line without shutting do-the UFS.
The Safety Evaluation eeneluded that there was not an =revie _ed safety question since the change =erely replaced existing indicating larps, and power cens=ptien would be slightly less than the original la ps.
~ SFC f 0-005 Thf change involved the replacement of the L80 VAC MCC 52-2326 breaker utili::ed for supplying power to the electric fire pump. The original breaker, GE type TJ236C6225 was found defective during routine breaker =aintenance. 3reaker type TJ236C5225 vas used as a direct replace =ent (SFC 79-011) until an i=preved type '"!C36225A breaker could se purchased. A Technical Evaluation by teth Consu=ers Power Cc=pany Syste= Protection and Laboratory Services Oepart=ent and the Vendor was perfor=ed. The criginal type breaker is obsolete and can no lenger te purchased.
The Safety Evaluation cen:1uded that this change did not constitute an unrevie red safety question.
SFC 80-006 This change consisted of adding vashers to the centrol rod drive p=p suction valve springs. The vashers were added to increase spring tension to achieve a good suction valve seal and to =aintain containment integrity, as these internal peppet _ valves serve as part of the contai=ent isolation tcundary en the control rod drive supply line.
The Safety Evaluatien cencluded that this change did not ecnstitute an unreviewed
-safety questien.
SFC 80-007 and SFC 80-0C3 These changes increased the =axi== opening angle for the supply and exhaust sphere ventilation isolation butterfly valves. The opening angle change was based upon a reanalysis by Allis Chal=ers. The supply butterfly valve opening angle was changed fron h5 cpen to 75 cpen.(SFC 80-007). The exhaust butterfly valve cpen-ing angle was changed.frc= h5 open to 85 cpen (SFC 80-006). At tl.ese new throttling angles, the butterfly valves vould not experience da= age caused by differential pressure during a 'oss of coolant accident. They would still be able to perfor= their -intended functicas of contai=ent. isolation and subsequent contain-
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Specification Field Changes (contd)
SFC 80-007 and SFC 80-008 (contd)
=ent vacuu: relief (Reference SFC 80-017).
The Safety Evaluation concluded that these changes did not constitute an unreviewed safety question.
SFC 80-009 This field change to the installation specification for the Fire Detection System additions (Reference FC h623) allowed installation of an amber bypass light on the side Control Roon panel as opposed to the front panel.
(Note: FC h623 was not co=pleted in 1980.)
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 80-010 This change consisted of adding a six (6) second time delay to the station power transfor=er(s).overcurrent alarm circuitry. This modification eliminates nuisance alar =s caused by starting currents of large, rotating equipment.
The Safety Evaluation concluded that an unreviewed safety question did not exist.
SFC 80-011 This change' replaced pneumatic air receiver gauge PI-IAL) (steam dru= pressure
.indientor) with a. digital inditator while relocating this pressure ~ indicator.
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relief Relocation ~ias required.to provide room.for installatica of the stea= dru:
valve =onitoring system installed per. Facility Change FC h89 A digital indicator vas used because it required less panel space than a pneu=atic air receiver gauge while.providing greater accuracy.
.The' Safety' Evaluation Leoncluded that this change did not. constitute an unreviewed-safety question.
SFC 80-013 and'SFC 80-01h This. change consisted of throttling the contain=ent intake ventilation check.
valve '(SFC '80-013) Land the containment exhaust ventilation check valve (SFC 80-Olb Jto.a position analyzed by Atvoed.and Morrill Co=pany and MPR Associates to allov
- safe closure unde'r accident conditions (Reference SFC 80-015, SFC 80-016,; SFC.80-017).
. Specification Field Changes (contd) 9 SFC 80-013 and 80-Olh (contd) j The Safety Evaluation concluded that these changes did not constitute an unreviewed safety question.
SFC 80-015 and SFC 80-016 These changes =odified the air cylinders of the supply and exhaust sphere venti-lation isolation check valves. Based upon analysis results, to determine check valve perfor=ance during a loss of coolant accident, an extension of the air
- cylinder had to be performed. This 3" extension is to prevent overpressurization and possible damage to the air operator cylinder and tubing. This change will ensure ventilation isolation check valve operability (containment isolation and relief) during and after a loss of coolant accident (Reference SFC 80-013, vacuu:
SFC 80-01k, SFC 80-017).
The _ Safety Evaluation concluded that these changes did not constitute an unreviewed safety question.
SFC 80-017 This change consit<.ed of modifying the air supply to provide the ability to isolate the operating air to either the supply or exhaust containment ventilation iso-lation valves independently. ' Dais change provides greater flexibility for taking one valve-train out of service for maintenance (Ncte: this change was performed prior to SFC 80-015 and SFC 80-016).
To acco=plish.this change, an additional isolation valve and minor changes to the air. operator (s). supply air pipine were ' required.
The Safety Evaluation concluded that this change did not constitute an unreviewed' safety question.
JSFC 80-018' This: ch'ange consisted of modifying the ' vent" piping for the control rod drive.
scra= du=p tank by replacing a threaded cap on the 2" floor stub to the encicsure dirty stub with tvo street:elbovs.
As lpart of IE Bulletin 80-17 requirements, a positive, continuous atmospheric ventLvas established on the'scra= dump tank vent by this change. The use of two
. street elbows.vas to--direct any possible effluent during scram dunp tank: venting
.towards the floor to minimize radiological impact and to preclude plugging (by
~
1 debris) by;having the' opening for1the vent point' downward.
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Specification Field Changes (contd) 10 SFC 80-018 (centd)
Specification Field Change 80-019 is relat-d to this =ciification.
The Safety Evaluation concluded that this change did not constitute an unreviewed
. safety question.
SFC 80-019
'This change. consisted of replacing the two street elbows installed in SFC 30-018 with a vent baffle / arrester to contain radicactive fluids expelled due to trapped pressure.
During =anual-sert testing frc= nor=al operating pressure and temperature, the totally open vent as modified with the tvo street elbevs, resulted in a significant a=ount of water and air being expelled from the 2" vent. This was due to trapped pressure within the sera = discharge volu=e (approxi=ately equal to reactor pressure after 60 see'onds). When the scras was reset and.the drain and vent opened. the residual pressure. in the scran discharge volu=e acted as a =oving force to expel the fluid until the pressure reached at=ospheric levels. This resulted in a large a=ount ' of water being sprayed onto. the ficor and adjacent equi;=ent.
The baffle / arrestor. serves to eliminate the. expulsion of -liquids by alleving a volu=e for containing the vent ' effluent. The taffles act as a labryinth to reduce-the pressure at the vent outlet en the baffle nrrester which is diree ed away. from adjacent equip =ent.
2.
The Safety Ivaluation eeneluded that this change did not constitute an unreviewed safety question.
SFC 80-021
~ This change replaced the =etalic "O" ring.of the inecre flange with a rubber "O"
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ring andladded a thimble as - a' backup to' the beveled seat. The -ubber "0" ring and thi=ble' serve as a sealing nediu= to eli=inate. or reduce the proble= of s=all
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drips and leakage through a flanged cennection.
The SafetyLEvaluation concluded that the change did not constitute an =nreviewed safety question.
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.SFC 80-023
$ *his change' replaced thel reactor level sensing line upper root valve with a lpackingless valve..The upper rect valve-had a history of_ packing. failures causing
-leakage proble=s. This valve was replaced '.ith a nev. type of sealed valve that vil15 not. leak past it's sten.
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Specification Field Changes (contd) 11 SFC 80-023 (contd)
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 80-02h This change replaced the recirculating pu=p cross drain valve with a packingless valve. The recirculating pu=p cross drain valve had a history of packing failures causing leakage problems.
The valve was replaced with a new type of sealed valve that will not leak past its ste=.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 80-026 This change involved replacing ~ the original "3arksdale Mbdel 31T" pressure switches used for PS-IA 106A and PS-IA 1063. The function of PS-IA 106A and PS-IA 1063
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is to provide a "high reactor pressnre alar =" at 1355 psig - 5 psis. The 3arksdale switches had _de=enstrated a setpoint drift that made the alar = unreliable. These
- svitches were replaced with " Static-0-Ring" pressure switches, =cdel
- 93n-Kh5-ML-ClA-TTX7. Engineering Analysis (EA-GiJ-80-026-01) deter =ined that the L SOR switches were equal to or betterithan the original equip =ent.
The Safety Evaluation concluded that this change did not constitute an unreviewed safety' question.
SFC 80-028
.This ' change consisted of =illing of the 75-ton Gantry Crane Fuel Transfer Cask
. Safety Device Tag-line dru=.
. The' diameter cf the safety device tag-line drun was reduced to ensure the vertical
- =ction of the =ain heist and the: safety device _ tag-line was synchronized to
~
- =aintain'the sa=e rate of' ascent / descent. -This. enables the tag-line to be taut
.to provide instantaneons tripping of the safety. device in the event of hoist
=alfunction..
The. Safety. Evaluation concluded that an unreviewed safety. qu'e'stion did net exist.
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Setpoint Changes 12 SPC 80-018 This change consisted of changing the range of PT-186 from 0-500 psig (10-50 =a) to 0-1500 psig-(10-50 =a).
This pressure transmitter is utilised to =enitor ECCS line pressure in the event
'of a 1CCA, the pressure of which should not exceed 200 psig.
However, testing requirements on the ECCS valves at power operation, subjected the transmitter to reactor operating pressure of 1335 psig, causing sero shift or the transmitter due to.the sudden pressure increase greater than the calibrated range. Calibration of the transmitter to enable operation at pressures up to 1500 psig should alleviate this problem.
The Safety Evaluation concluded that there was not an unreviewed safety question as this was'a calibration c1ange that fell within the design specifications of the pressure trans=itter.
SPC 80-019 This setpoint change allows for the AC emergency oil pump to be test started.
The original setpoint for.PS 651 (TPS) was 80 psig (decreasing). With the turbine cn line,' the pressure on PS. 615 only delays to -98 psig using the test valve.
L The setpoint vas changed to 100 psig to facilitate on line testing.
The Safety Evaluation -concluded that there were no cafety related i=plications or interfaces.
SPC 80-020 This change established the steam drum relief valve monitoring syste='s high alar = setpoint as 20 g's acceleration.
This _ change was performed in _ conjunction with Facility Change FC-489 It has Ebeen superseded by Setpoint Change 80-023 The Safety Evaluation concluded that this change did not constitute an unreviewed safety. question.
'SPC-80-0211 This change consisted of raising the float voltage on the _ Reactor Depressurisation
- Syste:/Uninterruptable Pover' Supply _ battery charging systems. The voltage was previously set at 129 volts per the: Consumers' Power Cc=pany station binder.
'The-
- vendor (=anufacturer. of the batteries), recen= ended that the voltage be readjusted
-tci l32 volts. This -eadjustment would-help alleviate th'e -proble= cf = low specific igravity t' hat Big Rock Point has been experiencing with the Exide Type 3CA3 batteries.
Setpoint Changes (contd) 13 SPC 80-021 (contd)
The Safety Evaluation esneluded that this change did not censtitute an unreviewed safety question.
SPC 80-023 This change established the stea= dru: relief valve =cnitering syste='s high alar = setpoint as 9 g's acceleration.
This change was perfer ed in conjunction with Facility Change FC h89 and SFC 30-011.
It supersedes Setpoint Change 80-020.
The Safety Evaluation concluded that this change did not constitute an unrevierad safe., question.
SPC 80-02h Tnis change consisted of reducing the Eeactor Depressurization Systen reactor water level trip setpoint ~ frc= " equal to or greater than 3'1" above the top of active fuel" to " equal-t7 cr greater than 2'9" above the top of active fuel" in accordance with Technical Specification A end=ent No. 3L.
The Safety. Evaluation concluded that this change did not constitute an unreviewed safety question.
SPC 80-025' This change consisted of reducing the reaccor water level trip setpoint utilized for ECCS actuatic - frc= " equal to or greater than 3'1" above the top of acti~e fuel" to " equal to or greater than 2'9" above the top of active fuel" in accordance
-with Technical Specification Anend=ent No. 3L.
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-The Safety Evaluation concluded that this ";hange did not constitute an.unreviewed safety question.
SPC 80-0261 This change censisted of reducing the Eeactor Protection Systes reactor water level trip. setpoint: utilized for reacter sera = and contain=ent -isolation frc= " equal to-or greater.than 3'1" above the top of active fuel" to " equal to or greater than 2'9" above the top of active' fuel":in'accordance with Technical, Specification k
- A=endment"No.-3
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The Safety Evaluation concluded that this change did not constitute an unreviewed s afety-. question.
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Special Site Tests 1
i SST-16 l
This test censisted of the collection of data, in the for= cf current, voltage and pcver, frc= strategie locations in the Plant's station pcVer syste=.
Se
' data vas utilited to verify the validity of a ec=puter pregrs=.
2e ec=puter progra= vas utilined-to analyze the adequacy of the plant's statien pcver syste=
to =aintain proper voltage ccedi*iens with regards to both:
- 1) poten*ial overicading due to transfers of either safety or non-safety leads, and
- 2) potential starting transient proble=s.
Se data was successfully eclieeted en June 27,199f,
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- u -esults forwarded 4
for ec=parisen with ec=puter results.
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Se.analyning and collection of data frc= *he station pcver syste= vas requested by the US Nuclear Regulater/- Cen=issien (US:EC) in a letter dated Aurast c,1979 2e Safety Evaluation eeneluded that perfor=ing this test did not eenstitute an unreviewed safety questien.
I
..e.e._3 ~t.
e 2is test ecesisted of Icading the e=ergency diesel renerator to 190 - 10 K'a', via a resistive lead bank, for a' =ini= = period of 2k hours. 21s test was perfer ed and successfully cc=pleted during the =enth of Dece=ter,1930.
t 21s _ test' was conducted to satisfy a' ec =itse + -ada to the US Huelear Eeralatery Cen=ission' (USN?.C), via a letter frc= DA31xel to JGKeppler US:3C, dated
' Cetober 31, 1979
- A test report was generated describing the test and its results and is filed in r
- the Special' Site Uest file.
Se Safety. Evaluation concluded that. this test. did set constitute an unretieved
- safety. question.
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