ML20042B810
| ML20042B810 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/19/1982 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20042B807 | List: |
| References | |
| NUDOCS 8203260172 | |
| Download: ML20042B810 (16) | |
Text
~. :.... w
. - -.. =. =.. _..: :
.=
==.
--.:2..-
. ~, :..
^
f
-t h
FACILITY CHANGES, TESTS AND EXPERIMENTS l
Facility Changes Big Rock Point Plant 4
1 J
T l
1 4
i l
l-4 i
i 4
8203260172 820319 i
PDR ADOCK 05000155 j
R PDR i
i nu0382-0031c142
...--.----.---._-__._.._.-_a_..;.-
i e
e FACILITY CHANGES. TESTS AND EXPERIMENTS Facility Changes
.FC h35 This change consisted of relocation of a nitrogen charging pump utilized for (1) maintaining the liquid poison system nitrogen header pressure and (2) testing of steam drum relief valves. Involved in the relocation were installation of a new 480 VAC power supply and extension of 1/2 inch stainless steel tubing to the liquid poison system nitrogen header.
Relocation was performed to be consistent'with ALARA practices, classed as a non-safety related modification and the safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC khD This change consisted of permanently installing an a= meter shunt into the station battery circuitry to enable monitoring of the total station battery current load during service and discharge testing of the station battery.
Previously, battery cabling had to be disrupted and the shunt temporarily installed during surveillance testing.
The shunt was mounted in an approved enclosure to protect it from damage, provide permanent storage and convenient access for connecting monitoring equipment. The shunt fixture was also equipped with appropriate bus work jumpers to allow bypassing of the shunt when no station battery testing is required, thus reinstat-ing the circuit to its previous arrangement.
This change was performed to eliminate a personnel safety hazard; the safety evaulation concluded that this change did not constitute an uneeviewed safety question.
FC h59 This change consisted of replacement of a manual isolation valve in the main station transformer fire water deluge system with an automatic isolation valve designed to close whenever ECCS ficv is required. This change ensures that fire water pressure to the ECCS is not robbe i should a main transformer fire occur si2ultaneously with a LOCA situation.
Valve installation was performed in accordance with material code requirements of the ANSI B31.1 Power Piping Code (as required by NFPA No.13) and other appropriate NFPA standards.
The safety evalua+
concluded that the modification did not constitute an unreviewed safet-stion.
(
Reference:
Amendment No. 39 to Facility Operating License No. DPR-6 the Big Rock Point Plant.)
FC 468 This change consisted of adding a second level of undervoltage protection on the station' power system to protect the system from sustained degraded voltage conditions at the off-site power sources. This improves' the reliability of
2 station equipment by not allowing the equipment to be subjected to sustained undervoltage conditions.
Three undervoltage relays, one per phase, were installed to monitor the voltage on the 2h00 volt bus. The relay settings are such that h80 volt equipment is protected from degraded voltage, below 85% of normal. The relaying is arranged in a 3/3 Logic to trip the incoming voltage to the 2h00 volt bus after a ten second time delay. Existing undervoltage relays (h80 volt A-C) provide the required load shedding and emergency diesel generator starting and loading.
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
(Also see Specification Field Changes SFC 80-041, SFC 81-005, and SFC 81-007.)
FC h80 This change consisted of the addition of a check valve in the control rod drive suction piping line inside containment. This valve was added to provide a more reliable method of performing the containrant isolation function (inside contain-ment) for the control rod drive pump supply. Originally, this function was served by internal poppet valves (3) within the pump (essentially check valves).
Also, a high point vent was added to the suction line external to containment to facilitate testing and relief valves were added to the suction lines between the check valve and pump to preclude overpressurization in the event of suction poppet failure (see Specification Field Change SFC 31-003).
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
(
Reference:
Amendment No. h0 to Facility Operating License No. DPR-6 for the Big Rock Point Plant.)
FC h88 This change consisted of the addition of appropriate relaying, visual indication and audible annunciation circuitry to provide mcnitoring of Engineered Safety Feature (and other essential) valving within the plant.
Basically, the modification circuitry monitors the remote manual controller (valve handsvitch) positions to immediately alert the control room operator that the valve has been placed in a non-automatic or off-normal mode.
For example, if an ESF valve is placed in a non-automatic position, ie, the remote manual controller placed in " Pull-to-Stop" position, the operator is alerted to this through an audible annunciator and visual display to indicate the valve is in an off-normal position.
This modification also provides monitoring of the ESF valve initiation circuitry, as loss of power to the valve control circuit will also alert the operator in the same fashion.
Other essential non-automatic valving (such as the reactor recirculation pumps suction and discharge valves) which is normally operated with the remote manual controllers In the " locked-out" position to preclude the possibility of hot shorts causing valve closure, are monitored in the opposite manner.
i.
. _... ~ _
__ _ a.. ;...
3 The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
( Also, see Specification Field Changes SFC 80-034, SFC 80-035, and SFC 80-038.)
FC h97 This change consisted of minor changes to the physical configuration of the reactor vessel level sensing element reference column and heat tracing of both the reactor vessel and steam drum level element reference columns to stabilize the density of 4
water in the columns.
This change decreases the probability of equipment malfunction important to safety by ensuring that the flash point (250 F) of the reference leg during a decreasing pressure transient is not violated and also results in a more accurate indication i
of level and trip signals during normal operation, anticipated transients and accident conditions.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
(Also, see Specification Field Change SFC 81-001.)
FC-501 i
This change consisted of adding an acid tank containment dike around the sulfuric i
acid bulk storage tank to retain acid which may escape from the tank. The dike will prevent the acid from being discharged directly to Lake Michigan either via storm sewers or natural run-off.
Approximately six to ten feet of limestone below the tank would neutralize the acid before it reaches the lake through natural ground seepage.
The dike is designed to hold approximately 1500 gallons or one and one half times the normal volume of acid (1000 gallons) kept in the tank.
This modification was performed to meet environmental considerations, classed as a non-safety related modification and the safety evaluation concluded that this change did not constitute an unreviewed safety question.
]
FC-503 This change consisted of adding a piping support to the enclosure spray header f
j located on the south steam drum wall. The additional piping support brings the system into conformance with the ANSI B31.1 Power Piping Code and is for dead l
weight considerations only (this deficiency was noted in the IE Bulletin 79-lh piping walkdown).
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
(Also, see Specification Field Change SFC 80-037.)
FC-505 This change consisted of expanding the gas cylinder storage area to provide additional storage area for gas cylinder bottles. The original storage area had become overloaded and adequate separation of gas types to meet safety and storage requirements was becoming difficult to maintain.
i i
A section of the west loading dock was expanded into the truck loading pit and portions of the dock then utilized for a new metal-enclosed storage area.
w=
h This charge was performed to meet storage and personnel safety requirements, was not classed as safety-related and the safety evaluation concluded that an unreviewed safety question did not exist.
FC-508 This change consisted of replacing pneumatic control lines that passed through the containment vall with electronic control units to serve the same function.
Basically, the control air signals were terminated at the containment inner and outer valls and electro-pneumatic conversion units were then utilized to pass the signal through the containment vall via electrical penetrations. This change I
eliminated three instrument air lines (one-fourth inch copper tubing) that penetrated containment and were susceptible to breakage and a subsequent breach of containment (penetration valving was then closed and capped to maintain contain-ment boundary).
The three air lines involved consisted of air signals to the two reactor blow-down system valves to radwaste and cooling water flow to the shutdown heat exchangers.
The safety evaluation concluded that the modification did not constitute an un-reviewed safety question.
FC-509 This change consisted of adding appropriate relaying to the emergency condenser j
system outlet valve schemes to automatically open their respective inlet valve if J
the outlet valve receives an open signal.
i l
During power operation, if the outlet valve on either tube bundle develops leakage, j
the inlet valve may be closed (on one tube bundle only). With this modification, automatic opening of the inlet valve is provided, thereby placing both tube bundles j
in service (without the modification, the control room operator would have been required to open the inlet valve).
3 The safety evaluation concluded that this modification did not constitute an un-reviewed safety question.
FC-511A This change consisted of replacing the existing 1000 gallon Emergency Diesel j
Generator fuel oil tank with a new 5000 gallon tank and utilizing the 1000 gallon tank for fuel oil supply to the Diesel Fire Pump.
(The original 275 Diesel Fire 4
l Pump Tank was disconnected, plugged and abandoned in place. )
This modification was performed to provide a larger fuel supply to eliminate l
significant radiation exposure for refueling the diesel equipment during plant i
accident conditions. No changes were made in the function of either system.
l The safety evaluation concluded that the modification did not constitute an un-j reviewed safety question.
l FC-511C t
l This change consisted of reloacting the spare emergency diesel generator to an area near the plant well house, installation of transformers, switchgear and cabling to allow spare generator operation from a more remote location.
4 1
5 This modification was performed to reduce potential operator radiation exposure in the event of an accident (LOCA). No functional changes were made to the emergency power system; the modification.is an alternative means to allow use of the spare emergency generator from a remote location during instances when high radiation exposures may exist.
The safety evaluation concluded that the modification did not constitute an unreviewed safety question.
FC-513 Following installation of a new emergency lighting system at Big Rock Point as a result of Fire Protection Modifications, the original emergency lighting system
. powered from either the emergency diesel generator or station battery via an automatic throwaver switch was not required.
This change disconnected the original system from the station battery, installed a manual disconnect to enable operation of the original emergency lighting system from the emergency diesel generator (if needed as manual backup) and revised the wiring on the automatic throwover switch to maintain the stack obstruction lighting equivalent to the original scheme.
The safety evaluation concluded that the modification did not constitute an un-reviewed safety question.
FC-515 This change consisted of modifying the enclosure spray system by extending the spray lines into the steam drum cavity and providing cooling spray to maintain the steam drum cavity area atmospheric temperature below 235 F.
To accomplish this change, existing nozzles were removed, new lines added into the cavity and resizing of spray nozzles to obtain an optimum spray pattern was performed.
( Also, see Specification Field Change SFC 80-030. )
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
(
Reference:
Amendment No. 37 to Facility Operating License No. DPR-6 for the Big Rock Point Plant.)
FC-516 This change consisted of adding a piping fitting to a suction strainer associated t
with the reactor core spray recirculation system to enable testing per the i
l ASME Code,Section XI, Subsection IWC-5222.
This section of the ASME Code requires that open ended portions of lines in non-closed systems be tested to demonstrate unimpaired flow. This modification The provides a method for testing the suction strainers and associated piping.
piping fitting is capped during normal operation so the original function of the suction strainer will not be altered.
l The safety evaluation concluded that the modification did not constitute an unreviewed safety question.
1 i
i
.e.
m
..r-
.mu
__m-,
___g,._.
,,c_,y_ - _, _.m,y mm.,,
g.
,,,,_.y..
__-_w,,
-w.
- ....~.~..:..
6 FC-518 This change consisted of providing fusing to additional annunciator circuitry to prevent loss of the station service annunciators because of shorting, grounding, etc. of individual annunciator circuits within containment during such time j
that the containment could exhibit a hostile environment.
Selective fusing of annunciator circuitry was performed previously (FC-371 and
- FC-372 during 1976); however, the primary criteria at that time was total sub-mergence of circuitry.
During this change, nine (9) additional circuits were fused. With the annunciator circuits individually fused in this manner, individual circuitry will be lost i
prior to main breaker tripping. Surveillance testing has been implemented to monitor the fuse condition on a monthly basis; the fuses utilized are of the indicating type.
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
FC-521 1
This change consisted of adding two portable classrooms at the plant site.
Addition of the classrooms was deemed necessary by increased training requirements,-
classed as a non-safety related modification and the safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-52h This change consisted of the construction of a used oil drum storage area on the j
plant site.
l To accomplish this, a concrete containment dike was constructed to store approxi-mately 12 barrels, with sufficient capacity to contain the volume of leakage from one barrel (55 gallons).
.This change was completed as a result of agreement with the Department of Natural Resources to prevent vaste oil from contaminating Lake Michigan and/or ground vater; classification was non-safety-related and the safety evaluation concluded i
that the modification did not constitute an unreviewed safety question.
i FC-529 This change consisted of the addition of an oil level indicator on the diesel fire pump fuel oil tank.
j Although equipped with a level switch to provide Operations personnel with level i
information, a local indicator was not available for use when filling the tank or for normal monitoring of tank level.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
l 4
mr,,
v m.4m--
r--,,.
,, -.c e,-,y-r, v-
.,, --.um, w w-i
--,.r.
.mr,-
,,.v-.4,.,r-s--
m---
--.~L-.._.__
L___
Specification Field Changes T
i SFC 79-02h This change consisted of adding redundant manual isolation valves on condensate supply lines to the resin regeneration system and to containment to prevent contamination of condensate water with reactor cooling water backflow.
The safety evaluation concluded that the additional valves provide redundancy; no system or component required for safety is affected and the change did not constitute an unreviewed safety question.
SFC 80-020 This change consisted of replacing the containment sphere ventilation exhaust butterfly valve with a functionally equivalent replacement.
Replacement was performed to obtain a newer model valve that would provide better sealing characteristics. The function, operation, size, purpose, etc. remained the same.
The safety evaluation concluded that replacement of the valve with a different model did not constitute an unreviewed safety question.
SFC 80-022 The following changes all address equipment anchorage modifications required to meet seismic qualification.
In each case, the safety evaluation concluded that an unreviewed safety question did not exist. These modifications are a result of IE Information Notice 80-21.
SFC 80-022A - Diesel Fire Pump - battery rack modifications and seismic anchorage SFC 80-022B - Station Battery - new free-standing battery racks and seismic.
anchorage l
SFC 80-022C - Diesel Fire Pump Control Panel - seismic anchorage SFC 80-022D - h80 V MCC 2A and 2B - seismic anchorage 125 V MCC - seismic anchorage SFC 80-022E -
SFC 80-022F - Emergency Diesel Generator Room Heater - new brackets and welded anchorage to ceiling 480 V MCC 1C and 2C - seismic anchorage SFC 80-022H -
SFC 80-022I - Sodium Hypochlorite Tank - bracing of cradle to strengthen same, l
voiding of contents and prohibiting use SFC 80-022J - Integrated Leak Rate Test Equipment Storage - movement restricted by cable attachment to concrete vall SFC 80-022K - On-Line Computer System - seismic anchorage SFC 80-022L - 480 V MCC 1A and Reactor Protection M-G Set Control Panel (C05) -
l seismic anchorage SFC 80-022P Containment Ventilation Panel (C20), Containment Instrument l
Panel (C30) and 480 V MCC 2D - seismic anchorage l
SFC 80-022Q - 480 V Distribution Panel 2P - rigid bracing SFC 80-022R h80 V Load Center - seismic anchorage SFC 80-022T - Electric Fire Pump Panel (C-lT) - additional anchorage SFC 80-022U - Air Shed Ventilating Panel (C26) - seismic anchorage SFC 80-022V - Nitrogen Bottle Storage Rack - replace chains with rigid rack SFC 80-022W - Emergency Diesel Generator Cooling Water Head Tank - extra bracing l
to provide positive support SFC 80-022X - 125 Volt DC Distribution Panels - additional bracing (l
. n _
. _ _____ =
J 1
L. _
~'
8 SFC 80-029 This change involved a review of Cycle 17 core loading and compared its nuclear and thermal hydraulic characteristics with reference analysis associated with -
reference Cycle 15 The safety evaluation concluded that nuclear characteristics for Cycle 17 vere similar to reference Cycle 15, previous transient and accident analysis conservatively bounded core conditions for Cycle 17, the cycle would therefore respond to transients and accidents as previously analyzed or with less severe consequences and the new core loading did not constitute a potentially unreviewed safety question.
SFC 80-030 This change addressed replacement of the enclosure spray header nozzles as described in Facility Change FC-515 The replacement nozzles were selected to provide adequate enclosure spray and improve iodine washout capability due to droplet size reduction.
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
(
Reference:
Amendment No. 37 to Facility Operating License No. DPR-6 for the Big Rock Point Plant.)
SFC 80-031 This change consisted of modifying the enclosure spray initiation signal to provide prompt actuation of enclosure spray flow if containment pressure exceeds 2.2 psig.
Previously, the flow actuation was delayed for 15 minutes upon signal initiation.
Elimination of the delay provides immediate cooling to the steam drum cavity area, limiting atmospheric temperatures to 5235 F (see Facility Change FC-515 and Specification Field Change SFC 80-030).
The new initiation signal is supplied by four pressure switches in a series parallel network, providing a one of two taken twice logic for spray initiation.
(
Reference:
Amendment No. 37 to Facility Operating License No. DPR 6 for the Big Rock Point Plant. )
The safety evaluation concluded that this modification did not constitute an I
unreviewed safety question.
SFC 80-03h, SFC 80-035, and SFC 80-038 These changes consisted of engineering design changes to Facility Change FC h88 (Engineered Safety Feature Bypass Indication Modification).
Due to errors in the original circuitry design for FC h88, electrical feedback through new relays prevented the circuitry from operating as intended. These errors were detected in FC h88 checkcut. Circuitry changes were made to correct the problems and meet the design intent of Facility Change FC h88.
.+--v--
m.-..
l i
9 1
1 The safety evaluations concluded that these changes did not change the design intent of the modification and did not constitute an unreviewed safety question.
SFC 80-036 i
This change consisted of relocating the basket strainer in the fire water supply to (1) the core spray heat exchanger and (2) the alternate path for emergency core cooling.
Previously, the basket strainer was operated with one strainer removed to allow unfiltered water to the core spray heat exchanger. By relocation of the basket strainer upstream of the alternate supply for emergency core cooling, filtered water is available for this function if required while the flow path to the core spray heat exchanger remains unaffected.
The safety evaluation concluded that this modification did not constitute an unreviewed safety question.
i SFC 80-037 This change consisted of an engineering design change to Facility Change FC-503.
i As designed, the pipe support interfered with existing equipment. A design change j
was necessary to install the support.
The safety evaluation concluded that the pipe support would be installed in the same location and still handle the dead weight of the pipe as originally intended and that installation of the support as revised did not constitute an unreviewed safety question.
SFC 80-039 This change consisted of replacing short sections and various types of insulated wire utilized in junction boxes, devices, etc., with wire of known qualification status.
During Electrical Equipment Qualification inspections, several devices were noted to contain wire and splices for which qualification status could not be determined.
All such viring locations and devices noted were corrected with LOCA qualified l
vire and " shrink" type insulating sleeving.
I The safety evaluation concluded that replacement of the questionable wire and splices would increase the margin of safety and would not constitute an unreviewed i
safety question.
}
SFC 80-Oh0 l
This change consisted of modifying the piping supports to the fire system piping i
to improve the seismic response of the system and reduce the probability of a l
line break.
t The safety evaluation concluded that this modification did not constitute an j
i unreviewed safety question.
l I
.. : w u.....
.:==
2 m : ::.
= zu a; ;;,
10 I
SFC 80-Ohl SFC 81-005, and SFC 81-007 1
j These changes consisted of engineering design changes to Facility Change FC h68 l
(Station Power Undervoltage Protection).
During installation of Facility-Change FC h68, the 125 volt D-C power source was changed to a different breaker on the D-C distribution panel to maintain a proper relationship between wire size and breaker size. Also, internal wiring changes i
and test stud additions were made to the new relay panel to allow for proper i
testing of the undervoltage relays, i
The safety evaluations concluded that these changes did not change the intent of j
the original safety evaluation for Facility Change FC-468 nor did they constitute -
any unreviewed safety questions.
SFC 81-001 This change consisted of approval for a functionally equivalent cable substitution on Facility Change FC h97 (Level Element Reference Leg Modifications).
2 The use of a different cable (6/C #1h cable instead of two 3/C #14 cables) was to gain physical space and permit ease of installation. The 6/C cable was functionally identien1 to the original specification and met all necessary environ-mental qualification properties.
The safety evaluation concluded that this change did not affect the original design
?
and did not constitute an unreviewed safety question.
SFC 81-002 This change consisted of approval for-use of a functionally equivalent time delay relay to replace an obsolete model per vendor recommendation.
i f
The replacement relay was determined to have the same electrical requirements as the original relay in the specified time delay interval; both relays were products of the same manufacturer.
l The safety evaluation concluded that relay replacement did not constitute an unreviewed safety question.
i SFC 81-003 This change was basically an engineering design change to Facility Change FC h80 l
(Control Rod Drive Pump Suction Piping Check Valve Addition) when it was recognized that leakage through the pump internal poppet valves could result in l
overpressurization of the suction line piping.
l A relief valve was added to the suction line of each pump to relieve pressure prior to reaching the design rating of the piping.
The safety evaluation concluded that the addition of the relief valves did not constitute an unreviewed safety question.
it i
SFC 81-005 (see SFC 80-0h1) i i.,
. ~
. u
....:... _ c.. _ _.... A. u
... a... t
._2__,__2 l
4 11 j
SFC 81-006 This change consisted of replacing the internal switch components utilized for monitoring containment water level with switches having a higher temperature rating.
The replacement switches were rated at 250 F, while the original switches were rated at only 160 F (containment vessel design temperature is 235 F).
The safety evaluation concluded the this change did not constitute an unreviewed safety question.
SFC 81-007 (See SFC 80-Ohl)
SFC 81-008 This change consisted of the addition of manual isolation valves to a modification in progress, namely, Facility Change FC h90 (High Point Vent) and is considered an engineering design change.
With the original design package, manual isolation valves were not included and isolation capability of the solenoid operated vent lines was not available for either repair or testing. Also, the high point vent modification has not been completed and installation of the manual isolation valving per ASME code allowed continued plant operation by meeting the requirements for primary system contain-ment.
The safety evaluation concluded that the addition of the manual isolation valves did not constitute an unreviewed safety question.
SFC 81-013 This change consisted of revising the 120 VAC power circuitry in the telephone equi ent room to provide power to all telephone equipment from the emergency power system.
Previously, some equipment in various plant locations and in the telephone equip-ment room was powered by plant lighting circuits. New dedicated outlets were j
installed in the telephone room, equipment from other plant locations was moved to the telephone room and both the new outlets and plant lighting circuits were clearly identified for use.
t The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SFC 81-014 4
This change consisted of revisions to the Piping Material Specification for Big Rock Point Plant to allow the use of improved material types (Type 316 SS for Class C# piping and Type SA-333 Carbon Steel for Class A*, B*, and D*
l piping (* Big Rock Point Plant Piping Categories). Also, this change permits the use of two inch and smaller carbon steel fittings of 3000 lb class (previous
{
rating of 4000 lb is no longer a standard item).
t
~.
j 12 This change to the plant piping specifications was performed following a review of General Electric Service Informstion Letters No. 2h3 and 249 The safety evaluation concluded that the revisions to the plant piping specifi-cation did not lessen the assurance of overall system integrity and did not I
constitute an unreviewed safety question.
1 SFC 810-15
(
This change consisted of changing the pump impeller size on the reactor cleanup pump. The original impeller was 6-3/h" diameter, the replacement impeller diameter may be reduced to 6-5/8".
This change was made to meet a new vendor standard.
The safety evaluation concluded that the safety related function (primary system integrity; pumping is a reliability concern) had not changed and that use of the new, smaller impeller did not constitute an unreviewed safety question.
SFC 81-018 This change consisted of replacing the containment exhaust ventilation valve solenoid valves with valves having larger size parts. The change was made to provide larger venting capacity and faster closing time for the exhaust valves.
J The original valves were equipped with 11/16" orifices, the new valves were equipped with 1" orifices. Other than orifice and port size, the valves were essentially the same (ie, same vendor and model classification).
The safety evaluation concluded that replacement of the valves did not constitute an unreviewed safety question.
)
SFC 81-020 This change consisted of replacing emergency lighting units utilized in security areas at the plant site with functionally equivalent units.
The originally specified lighting units had become obsolete with limited availa-bility of repair parts.
I The safety evaluation concluded that replacement of the lighting units did not l
constitute an unreviewed safety question.
SFC 81-025 This change consisted of decreasing the temperature range of the reactor vessel i
and steam drum level reference leg temperature controllers from 0 to 1000 F to l
0-500 F to provide greater deviation meter resolution.
The range change was performed via replacement of range calibration components j
supplied by the equipment vendor.
i The safety evaluation concluded that this change did not constitute an unreviewed safety question.
il
-..v.
,.J_-,
_, _,, ~,,. _,,
._,-,,g_,,
,,_y.m
-_,~.m y
.._mm.,
4 13 i
.SFC 81-026
.t 3
This change consisted of relocating a sample line on the domestic water sand I
filters supplying the make-up demineralizer system.
i As installed, the sample line was connected to the equalizing line which presented sampling problems due to a lack of positive pressure on the sample line. The i
sample line was relocated to the backwash header upstream of the backwash regulator valve.
The safety evaluation concluded that this piping change did not constitute an f
unreviewed safety question.
I SFC 81-027 This change consisted of replacement of a defective battery cell in the station battery system with a cell recommended by the manufacturer as a functionally i
equivalent substitution; the original cell type is obsolete and no longer made.
I l
The safety evaluation concluded that the replacement cell had an overall average cell performance higher than the original type and the change did not :onstitute.
r an unreviewed safety question.
i l
i l
l l
t f
i
^
14 Set Point Changes SPC 81-029 This change consisted of lowering the setpoint on the stack fan exhaust plenum low vacuum alarm from -3.75" H O to -1.5" H 0.
2 2
This change was performed to remove the masking effect of the low vacuum alarm from standby fan start annunciation on the common alarm system.
The safety evaluation concluded that by lowering the setpoint to -1.5" H 0, the 2
annunciator system would provide information that the standby fan had started (at -2.5" H O), provide indication of low plenum vact.um in the event both fans 2
tripped and that the change did not constitute an urreviewed safety question.
~- -
= --
4 1.._ -. -. _ :, _
_.. _n _ :..
,c__.,
i
...f 15 4
Special Site Tests SST-19 I
The purpose of this test was to ensure that additional water volume due to a i
)
reactor. scram could be contained in the scram dump tank with the scram dump tank already half filled with water. The additional volume was to be received
~
vithin the Technical Specification scram time off2 5 seconds.
Results of the test indicated that all drives could be fully inserted in less than 1 5 seconds (well within the Technical Specification time limit of 2.5 seconds). The test was considered complete and successful.
The safety evaluation concluded that performance of the test did not constitute an unreviewed safety question.
4 SST-21 This test consisted of a valkdown of various plant system components and piping (including supports) to gather data through various methods such as photography, I
sketching, manufacturer's data collection, measurements, and multiple vibration response samplings utilizing oscillographic monitoring equipment.
The primary purpose of the sampling was to estimate the frequency of the funda-mental mode of various items in order to determine where it falls on the 4
corresponding floor-response spectrum. As this was basically an information gathering test, no specific acceptance criteria was established; the data was collected for informational purposes.
The safety evaluation concluded that performance of the test did not constitute an unreviewed safety question.
i i
I 1
i i
s
_