ML20107B200
See also: IR 05000219/1973004
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U. S. ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATORY OEE...TIONS
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RO Inspection Report No.:
50-219/73-04
Docket No.: 50-219
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License No.: nPH 16
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Lic ensce :
Jersey Central Power & Light Co.
Oyster Creek
Priority:
Category:
C
Location:
Forked River. New Jersev
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Type of Licensce:
1930 MWt. BWR
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Type of Inspection:
SPecial
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March
13, 1973
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Dates of Insp'ect. ion:
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Special - February 13-16, 1973
Dates of Previous Inspection: Routine - November 9-10. 12. 13 & 20,
Dec ber 7-8, 1972
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PrLtcipal Inspector:
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.3[2)[h3
Dalc
F.S.Cantrell,Reac([Idspector
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Accompanying Inspectors :
Nonc
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_ _ _ . . _ . _
Date
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None
Other Accompanying Personnc!:
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Reviewed Ey: 4k[
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D. L. Caphton,' Senior Reactor Inspector
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DEKOK95-258
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SUMMARY OF FINDINGS
Enforcement Action
A.
Paragraph.3.3.C.2 of the Technical Specifications specifies, "The pump
1.. an idle recirculation loop shall not bc s tarted unless the tempera-
ture of the coolant within the idle recirculation loop is within 500F
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of the reactor coolant temperature."
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Contrary to the above requirement, the B recirculation pump was started
on March 10, 1973 with a temperature differential of 117 F between the
coolant within the idle recirculation loop and the reactor coolant tempera-
ture.
B.
Paragraph 6.2. A of the Technical Specifications states in part, "De-
tailed written procedures with appropriate check off lists and instruc-
tions will be provided for the following conditions;
1.
Normal
startup, operation, and shutdown of the complete plant and of all
systems and components involving nuclear safety of the plant... 4. Pre-
ventive or corrective maintenance operations which could have an
effect on the safety of the reactor." Paragraph 6.2.C of the Technical
Specifications states, " Standing instructions to the operating staff
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shall require that the procedures identified in A.. . . .above are to be
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followed in conducting activities identified therein."
Contrary to the above requirements, the B and D recirculation 'spops
were removed from service to replace the brushes on the MG sets and
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returned to service without the use of written procedures. The pro-
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cedure for operating the nuclear steam supply system (No. 301) as
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modified by a temporary procedure change, dated December 18, 1970,
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requires, in part, shutting down to recover an idle loop if the differ-
ential between the loop and the reactor exceeds 50 F.
Licensee Action on Previously Identified Enforcement Items
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Not inspected.
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Design Changes
Not inspected.
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Unusunt Occurrences
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The B recirculation loop was returned to service on March 10, 1973 with a
differential temperature of 1170F between the temperature of the reactor
coolant and the temperature of the coolant in the idle loop. The APRM
recorders in the same reactor quadrant as the B recirculation loop showed'
that the flux increased
approximately 17% when the pump was restarted,
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Other Significant Findings
/.. Current Findings
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1.
Operations
.The plant.was operating at 1880 MWt with one recirculation loop
valved out prior to reducing power to approximately 1550 MWe'to
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individually remove the. B and D recirculation loops ^ from service-
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on March 10, 1973. Following replacement of the brushes on the MG
sets, power was. returned to 1880 MWt. The stack release rate was
125,000 uCi/sec.
2.
. Operating Logbooks
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The transient associated with returning the idle loop'to service
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on March 10, 1973 was not noted in either the Shift Foreman's
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. Log or the Control Room Log.
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B.
Status of Previously Reported Unrasolved Items
Not inspected.
Management Inter' view
The exit interview was conducted with'Mr. McCluskey on March 13, 1973.
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A.
Scope and Findings of the Inspection
1.
The inspector stated that two violations of Technical Specifications
were found during the review of the abnormal occurrence involving
the restarting of the B recirculation pump as follows:
The B recirculation pump was _ restarted with the temperature
a.
differential between the idle recirculacion loop and the
reactor coolant temperature greater than 50 F.
b.
The B and D loops were isolated and returned to service
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without the use of procedures or without the operating per-
sonnel reviewing the procedures prior to performing the
operation. This is evident by the fact that the procedure
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requires the temperature differential to be less than 50
and that if the temperature differential _is greater than .50 ,
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the temporary change to the operating procedure (No. 301)
dated December 18, 1970, requires the plant. to be shut down .
to reclaim the idle loop.
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2.
The transient associated with this event was not recorded in
either the Shift Foreman's Log or the Control Room Log. The
inspector stated that these logs are suppocad to provide a
history of plant operation, and as such, abnormal occurrences
and unusual conditions should be recorded in these logs. The
inspector stated that the failure to record this event in either
log supported the inspector's position during previous discussions
that the content of these particular logs did not provide a
reasonably complete record of significant events at Oyster Creek.
The inspector further stated that it was his position that the
information recording requirements for the Shif t Foreman's Log
required a step increase. The licensee's representative agreed
that this event should have been recorded in the Log and stated
that this matter had been discussed with shif t personnel and
would again be re-emphasized to operating personnel.
3.
The inspector stated that the Techni 31 Specifications require
written procedures for operation and maintenance of the reactor.
The inspector stated that he would not take the position that a
detailed check list was required to remove or return a recircula-
tion loop to service; however, this was an evaluation that Jersey
Central should make as a part of their investigation of this
abnormal occurrence. This matter should be a part of each in-
vestigation of an abnormal occurrence. The licensee's representa-
tive stated that the Operating Procedure for the recirculation
loops was being revised to provide more definitive instructions
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for the operator. He stated that the Jersey Central investigation
of this event would include an evaluation of the greater use of
check sheets in performing operations at the plant.
4.
The inspector stated in his discussion of the procedural require-
ment to shut the plant down prior to reclaiming an idle loop
if the temperature differential exceeded 50 F, some of the
operating personnel did not consider this a necessity. The
inspector pointed out that the Technical Specifications permit a
temporary procedure change if the temporary procedure change
does not change the intent of the procedure. A temporary proce-
dure change to permit reclaiming the idle loop without shutting
the plant down would not be considered within the intent of the
procedure. The licensee's representative stated that the plant
could have continued to operate on three recirculation loops
and that it would not have been necessary for operating personnel
to make a decision prior to holding a meeting of the Plant Opera-
tions Review Committee to approve a procedure change.
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5.
During a subsequent telephone conversation, Region I was informed
that General Electric had provided information to show that an
analysis of the stress in the recirculation nozzle of a similar
reactor vessel had been made using a 4000 temperature change over
a 26 second period. The results of this analysis showed that the
stresses were within design limits. The licensee indicated that
this would be included in the written report to the Directorate
of Licensing concerning this event, which would be issued within
10 days.
6.
In response to questioning about corrective action on matters
identified in a letter from J. P. O'Reilly to Jersey Central
dated March 7, 1973, the licensee representative stated that all
of the radioactive material areas, radiation areas and high
radiation areas have been properly identified, and all drums
of radioactive material have been stored in shield facilities.
Jersey Central is evaluating how to lock high radiation areas
in accordance with Technical Specification requirements. The
shipment of radioactive waste drums is continuing, but the back-
log is essentially unchanged. Jersey Central is evaluating bids
for outside help in preparing waste drums for shipment and in
cleaning up the Radioactive Waste Building. The licensee's
representative stated that he was currently working with the JC
Manager of Nuclear Generation preparing Jersey Central's reply
to the March 7, 1973 letter.
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DETAILS
1.
Persons Contacted
T. J. McCluskey, Station Superintendent
J. T. Carroll, Operations Supervisor
J. L. Sullivan, Technical Supervisor
E. J. Growney, Technical Engineer
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2.
Recirculation Pump Started with Greater Than 50 F Temperature Differential
The B recirculation loop was returned to service on March 10, 1973 by
opening the discharge valve, restarting the B recirculation pump and
closing the bypass valve. At the time of this actL on, there existed
a differential temperature of 117 F between the temperature of the
reactor water and the loop water. Technical Specifications paragraph
3.3 prohibits restarting an idle loop unless the temperature of the
coolant within the idle recirculation loop is within 50 F of the
reactor coolant temperature.
The B recirculation loop had been removed from service to replace
brushes on the MG set that supplies power to the recirculation pump
motor at 12:30 /GI on March 10, 1973 by closing the pump discharge
valve, opening the bypass around the discharge valve, and de-energizing
the MG sets.
Opening the bypass valve permits backflow through the
recirculation loop and normally maintains the coolant temperature
in the loop within approximately 10 F of the reactor coolant tempera-
ture, however, operating personnel did not consider the effect of con-
tinued operation of the cleanup system on idle loop temperature. The
pgeg
clean up system is fed from the B loop, upstream of the suction valve,
and discharges to the B loop, downstream of the discharge valve. With
the loop discharge valve closed and the bypass valve open, the colder
water from the clean up system backflowed through the bypass valve
gradually lowering the temperature of the water in the recirculation
pump and the temperature of the feedwater to the clean up system.
The recorder for the recirculation loop temperature showed that the B
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loop temperature dropped approximately 117 F while the loop was iso-
lated and increased the same amount when the pump was restarted
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approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later (Attachment 1).
The recorders for the
average power range monitors (APRM) in the same quadrant as the B
recirculation loop showed that the flux increased approximately 17%
when the pump was restarted (Attachments 2 and 3).
This flux increase
is attributed to the associated increase in recirculation flow when
the recirculation pump was restarted, and to a negative moderator
tenperature coefficient. Rod block alarms were received when the
wap was restarted, but the flux increase was less than that required
to initiate a high flux scram. The narrow range reactor pressure
recorder showed a pressure surge of 4-5 psig at the tbme the B
recirculation pump was restarted.
Subsequent to the above, the D loop was isolated and returned to
service without the above effects. (Attachment 4)
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'a..
Safety' Analysis
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Starting an idle recirculation loop with a 375 F differential
was analyzed in the Facility Description and Safety Analysis -
Report (FD&SAR) for the resulting nuclear transient (for.1600
V
NWt). This event was not re-analyzed in the application to
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increase power to 1930 MW and the event was not analyzed for
the Oyster Creek vessel with respect to the stresses or strains
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. created in the recirculation nozzle by starting a loop with the
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tanperature differential in excess of 50 F.
In a subsequent
telephone conversation, a licensee representative stated that
General Electric supplied information to show that a stress
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analysis had been made on a boiling water reactor vessel for
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restarting the recirculation loop with a 4000 differential tanpera-
ture over a period of 26 seconds. This analysis showed only
skin stresses that are easily accountable for by fatigue analysis.
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' The licensee's representative further stated that this information
would be included in the report to be submitted to the Directorate
of Licensing.
b.
Procedures
Reactor Operating Procedure No. 301, entitled " Nuclear Steen
Supply System", provides instructions for operating the recircula-
tion loops. Section 3.02 of Procedure 301, entitled " Prerequisites",
Steps 2.E.2, specifies (sic) " pump filled with water same temperature
as pumps (check reactor water tanperature)". A temporary procedure
sque
change dated 12/18/70 requires a shutdown to recover an idle loop
if the differential between the loop and the reactor exceeds 50 F.
This caution note was also added to Section 3.1,
" Placing
Recirculation Pump in Operations" via a Temporary Procedure
Change dated 12/18/72 as follows:
"If temperature differential
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between the loop and the reactor is greater than 50 F, the
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reactor will have to be shutdown and cooled down to recover
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the loop."
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Technical Specifications paragraph 6.2.a requires " Detailed
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written procedures with appropriate check off lists and instruc-
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tions shall be provided for the following conditions;
1.
Normal
startup, operation and shutdown of the complete plant and all
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systems and components involving nuclear safety of the plant....
4.
Preventive or corrective maintenance operations which could
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have an affect on the safety of the reactor." Technical Speci-
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fication 6.2.C requires in part, " Standing instructions to the
operating staff shall require that the procedures identified in
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A. . ..above are to be followed in conducting activities identified
therein." No check list was available which was specifically
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applicable to the job of removing and returning a recirculation
loop to service. From the events that transpired, it was
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apparent that the operating procedure (No. 301) was not reviewed
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prior to removing and returning the recirculation loops to
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service, nor was the procedure used as a guide for this' operation.
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At the time of the inspection, the licensee was in the process
of revising and updating procedure No. 301; however, the re-
vised procedure had not been reviewed by the Plant Operations
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Review Committee, a requirement of the Technical Specifications.
The inspector was informed that the licensee planned to present
this procedure to the PORC for review and approval at the next
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meeting.
3.
Stack Release Rates
The inspector reviewed data sheets, recorder charts and laboratory
analyses to determine the effect of plant operations on the stack
release rate. From the recorded release rates and from a review
of plant operations, it appears that any change in plant operations
causes a temporary increase in the stack release rate,
i.e.,
in-
creased power, removal of rods, reduced power, increased recircula-
tion flow, etc. Normally the effect is temporary for a few hours;
however the stack relt.ase rate has increased from an average of about
40,000 uCi/sec during the latter part of January after the plant was
returned to power from the Decedber 29, 1972 to January 10, 1973
outage, to in excess of 100,000 uCi/sec during March. Based on
laboratory analysis of the stack release rate, this rate has7raried
from 108,748 uci/see to 137,539 uci/sec. Based on an analysis
March 12, 1973, stack release rate was 124,963 uCi/sec.
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In restanse to a question, a licensee representative stated that
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Jersey Central planned to sip the core during the forthcoming re-
fueling outage (starting the weekend of April 14, 1973) in an effort
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to locate and remove the leaking fuel assemblies.
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50-219
MADISON AVENUE AT PUNCH BOWL Ro AD e MoRRISToWN. N.J. 07960 e 539 6118
,
March 29, 1973
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Mr. Robert J. Schemel, Chief
Operating Reactors Branch #1
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APR 2 1973
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Directorate of Licensing
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United States Atomic Energy Commission
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Washington, D. C. 20545
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Dear Mr. Schemel:
In accordance with your letter dated January 17, 1973, the
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following information was assembled regarding the corrective action
taken to avoid a reoccurrence of incidences of the nature reported to
the AEC on April 20, 1972 and October 6, 1972.
Reactor Building Ventilation System Circuitry Modification
l
As was reported on April 20, 1972, a Limiting Condition for
l
Operation was violated when a circuit malfunction prevented the reactor
building supply dampers from shutting regardless of the operation of
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the supply fans.
It was discovered that this malfunction would occur
every time one of the three supply fan circuit breakers was " racked
!
out".
This happened because a " racked out" breaker would supply a
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" fan running" signal to each of the twenty supply damper's logic
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circuits.
Since the three " fan running" signals fed a series OR
circuit, one racked out breaker and two deenergized fans would
create the logic to allow the dampers to remain open.
1
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On August 29, 1972, a circuit modification was implemented
which corrected the above situation. Now a "rac'xd out" fan sends
a " fan stopped" signal to a parallel OR circuit.
For a supply dampey
to remain open, it is now necessary for at least one fan to be running.
Liquid Poison Pump Circuitry Modification
The problem with the control circuitry for these pumps is
similar to that discussed above.
hhenever one pump's breaker was
" racked out", the other pump was rendered inoperable. The control
circuit has a feature which will not allow both pumps to run
simultaneously. Originally, this was implemented by having a
_,.
normally closed auxiliary switch from the A pump's starter in
the B pump's starting circuit (and vice versa) . hhen the A
pump was started, the auxiliary switch would open and thereby
prevent the B pump from being energized.
Because the auxilia
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Mr. Robsrt J. Schemel
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Mtrch 29, 1973
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switch was mounted to the circuit breaker frame, its contacts in
,
the standby pump's starting circuit were physically removed when
the breaker was racked out.
This simulated one pump operating and
. subsequently locked out the standby pump.
On December 20, 1972, both pump circuits were modified as
follows: An interposing relay mounted to the control cabinet was
added to each control circuit.
These relays are normally deenergized
and have nomally closed contacts which function as interlocks for
the standby pump.
The auxiliary switches have been removed from the
pump starting circuits and have been changed to normally open contacts
which control the interposing relay.
h' hen a pump is started, its
auxiliary switch closes and causes the interposing relay to energize.
This, in. turn, opens the contacts in the standby pump's starting
circuit and thereby prevents it from starting.
If a breaker is
racked out, it has no affect on the state of the' interposing
relay. Therefore, the operability of the standby pump is not
affected.
In addition to the above modifications, an investigation
was conducted for all Engineered Safeguards Systems which could
possibly exhibit failures similar to those discussed above.
Specifically, the study concentrated on racking out a breaker
of a component and its affects on other redundant components
in the system.
The study was completed on December 1, 1972
and revealed'no additional problem areas.
Regarding your request for a proposed Technical Specification
change, we do not feel it to be warranted. The Technical Specifications
at present delineate the action to be taken if redundant safeguard system
equipment is rendered inoperable.
Recently we have issued a Standing
-Order which requires the testing of a redundant system immediately
after its counterpart is rendered inoperabic or found to be inoperable.
Since these meet the intent of your request, no changes to the
Technical Specifications are deemed necessary.
Very truly yours,
( /
(
Donald A. Ross
Manager, Nuclear Generating Stations
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