ML20107C006
See also: IR 05000219/1974002
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U.S. ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATORY OPERATIONS
REGION I
RO Inspection Report No:
50-219/74-02
Docket No:
50-219
Licensee:
Jersey Central Power and Light Company'
License No: DPR-16
,
Madison Avenue at Punch Bowl Road
Priority:
-
Morristown. New Jersey
Category:
C
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Location:
Oyster Creek. Forked River New Jersey
Type of Licensee:
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Type of Inspection:
Routine, Unannounced
Dates of Inspection:
January 21-25, 1974
Dates of Previous Inspection:
Januar.y 11-12, 1974
Reporting Inspector;
M
J/t v/W
ard'G. Greenman, Reactor nsgector
date
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Accompanying Inspectors: b
.[
3/4 ?// y
l
. Thomas (TAB), October l}/J473
D'a t e
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Date
Date
Date
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Other Accompanying Personnel:
None
Date
3/07/2Y
Reviewed By:
fN < /
k
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,vta
w Donald L. Caphton, Senior Reactor Inspector,
Date
Reactor Operations Branch
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9604170181 960213
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DEKOK95-258
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SUMMARY OF FINDINGS
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Enforcement Action
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A.
Violations
l'.' ' Technical Specification 4.5.F.1.D - Failure of MSIV's to meet
specified leakage rates.
NS03B leak test failure (JCP&L letters to DL dated
a.
September 21, 1973 and December 7,1973 (revised),
subject A0 73-23)
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b.
NSO4A and NSO4B leak test failure (JCP&L letter to DL
dated October 12, 1973, subject A0 73-24)
NSO4A leak test failure (JCP&L letter to DL dated
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January-25, 1974, subject AD. 74-05)
2.
Technical Specification 2.3(1)(a) and 2.3(2)(a) - Failure to
set the average power range monitor and rod block setpoints to
specified values.
(JCP&L letter to DL dated October 16, 1973,
subject A0 73-26)
(Details, Paragraph 6.b)
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3.
Technical Specification 2.3.7 - Failure of low pressure main
steam line pressure switches to trip at < 850 psig during sur-
ve111ance tests.
RE 23A, B, C, and D (JCP&L letter to DL dated -December 24,
a.
1973, subject A0 73-30)
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b.
RE 23C (JCP&L letter to DL dated January 15, 1974, subject
A0 74-01) -(Recurrent violations)
4.
Technical Specification 3.1.1.B.6 - Failure of a main steam
line high radiation monitor to. trip during surveillance.
(JCP&L
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' letter to DL' dated January 9,1974, subject A0 73-34)
(Details,
. Paragraph 11.b)
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5.
Technical Specification 3.5.A.6 - Failure to inert the torus
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content within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after placing the
atmosphere to 5% 02
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mcde switch in run.
(JCP&L letter to DL dated January 26, 1974,
(f)
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subject A0 74-6)
6.
Technical Specification 2.3.5 - Failure of isolation condenser
system time delay relays to initiate at < 15 seconds.
(JCP&L
letter to DL dated January 29, 1974, subject A0 74-8)
7.
Technical Specification 6.6.2 - Abnormal Occurrence Reports -
Failure to notify the Director of the Regional Regulatory
Operations office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a 10 day report.
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a.
24 Hour Notification
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A0 73-23(1)
b.
10 Day Written Report
(1) A0 73-22
(2) A0 73-24
(3) A0 73-32
(4) A0 73-34
4WMd
(Details, Paragraph 13)
8.
Tec'anical Specifications 4.7.A.5 and B.1 - Failure to perform
weekly checks of station and diesel generator batteries.
(Details,
Paragraphs 10.a(4) and b(1))
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9.
Technical Specifications 6.2.A.4 and 6.2.D - Installation of
jumpers without benefit of a written procedure.
(De tails ,
Paragraph 8)
B.
Safety Items
None
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Licensee Action on Previously Identified Enforcement Items
1.
Failure to report seismic shock suppressor failures.
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Subsequent supressor failures have been reported as required. An
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ongoing audit of surveillance areas is also disclosing prior oc-
curring reportable items. The licensee has made additions and changes
to the JCP&L staff. This item is considered closed.*
2.
Failure to maintain startup transformers operable and provide written
procedures for relay testing.
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The licensee's corrective action is still ongoing.
Procedures for
relay testing have not yet been reviewed by PORC. This area will be
reviewed during the course of subsequent inspections.**
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3.
Failure to complete core spray motor operated valve surveillance
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tests at required frequencies.
The licensee has assigned a staff engineer and an engineering assistant
responsibilities for auditing surveillance records. Audit results
. to date have identified previously undisclosed reportable items.
This item is considered closed.***
4.
Failure to maintain outside tank activity less than the 10 Ci limit.
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The licensee implemented a procedural change January 25, 1974 requiring
necessary sampling in the event of leaks. This item is considered
closed.****
5.
Safety Item - Failure to calibrate portable survey instruments
quarterly.
The licensee has implemented a new recordex control system.
Surveillance records indicated instruments have been calibrated
in accordance with a quarterly frequency. Additionally, 12 PIC 6A
portable instruments (0-100 R/hr) have been ordered to replace old
equipment. This item is considered closed.*****
- RO Inspection Report 50-219/73-18 dated January 8, 1974
and
JCP&L letter to RO:I dated November 9, 1973.
- JCP&L letter to RO:I dated November 20, 1973.
- JCP&L letter to RO:I dated October 30, 1973.
- JCP&L letter to RO:I dated October 30, 1973.
- JCP&L letter to RO:I dated December 3, 1973.
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. Design Changes
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Unusual Occurrences
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The following abnormal occurrences and events were reviewed. Comments-
concerning specific areas are noted within this report.
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A.
MSIV (NS03B) failed to meet allowable leakage requirements.1'
B.
A differential pressure switch failed to trip and actuate the reactor
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building to torus vacuum breaker block valves.2
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'C.
MSIV's (NSO4A and NSO4B) failed to meet allowable leakage requirements.3
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D.
An Isolation Condenser initiation relay failed to function during a
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surveillance test.4
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E.
Limiting safety system settings for the APRM neutron flux scram and
rod ~ block were not properly set.5
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F ." A nipple connecting the relief valve to the 1-3 containment spray
heat exchanger (emergency side) failed due to salt water corrosion.6
G.
Leakage was identified from the RBCCW system to the discharge canal
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via the service water system.7
H. . An inoperable snubber (fluid loss) on the steam line to the B Isolation
Condenser was found during surveillance inspection.8
I.
All four (4) main steam line low pressure switches tripped at less
than the minimum required setpoint, during surve111ance.9
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1 JCP&L report to DL dated September 21, 1973, Subject A0 73-23.
2 JCP&L report to DL dated October 3,1973, Subject A0 73-23(1).
3 JCP&L report to DL dated October 12, 1973, Subject A0 73-24.
4 JCP&L report to DL dated October 9,-1973, Subject A0 73-25.
5 JCP&L report to DL dated October 16, 1973, Subject A0 73-26.
6 JCP&L report to DL dated October 26, 1973, Subject A0 73-27.
7 JCP&L report. to DL dated November 8,1973, Subject A0 73-28.
8 JCP&L report to DL dated November 13, 1973, Subject AO 73-29.
9 JCP&L report to DL dated December 24, 1973, Subject A0.73-30.
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Momentary interruption of 125 V DC power supply'ing instrumentation
associated with safeguards systems.10
K. .The test' spool valve for NSO4A did not reset properly, following a
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five percent closure test.ll (Details, Paragraph 9)
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A damaged relay in the plant protection system.12
M.
Four. (4). isolation condenser high flow sensors tripped in excess of
specified A. values.13
N.
A main steam line high radiation monitor failed to ' trip during
surveillance testing.14
(Details, Paragraph 11.b)
O.
An unexplained isolation of the
"B" Isolation Condenser during a
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routine reactor cooldown on November 25, 1973.15
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P.
A spill of chromate water on December. 20, 1973 when a drain line from
a temporary storage tank froze and subsequently cracked.16
Q.
One (1) low pressure main steam line pressure switch tripped below
specified limits.17
R.
One main steam line high flow sensor in each safety system actuated
in excess of maximum allowable levels.18
isEh
S.
Five (5) inoperable snubbers (fluid loss) were identified during
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surveillance.19
10 JCP&L report to DL dated December 29, 1973, Subject A0 73-31.
11 JCP&L report to DL dated January 7,1974, Subject A0 73-32.
12 JCP&L report to DL dated December 20, 1973, Subject Damaged Relay.
13 JCP&L report to DL dated January 4,1974, Subject A0 73-33.
14 JCP&L. report to DL dated January 9, 1974, Subject A0 73-34.
15 JCP&L report to DL dated January 2, 1974, Subject Unexplained
Isolation of B Condenser.
16 JCP&L report to DL dated January 3,1974, Subject Spill of Chromated
Water.
17 JCP&L report to DL dated January 7,1974, Subject A0 74-01.
18 JCP&L report to DL dated January 17, 1974, Subject A0 74-02.
19 JCP&L report to DL dated January 24, 1974, Subject A0 74-03.
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MSIV(NS03B)failedtoinig0ially close with'the reactor shutdown and
the mode switch in refuel.
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MSIV (NSO4A) failed to meet acceptable leakage rate requirements
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during testing.21
V.
The torus was not inerted to 5.0% 02 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of placing the
mode switch in run.22
W.
One of four (4) reactor high pressure sensors tripped 'in excess of.
specified limits.23
X.
Three of four (4) time delay contacts associated with high pressure-
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isolation condenser switches failed to close within specified preset
' times.24
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Other Significant Findings
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A.
Current Findings
1.
Diesel Generator Modification
The licensee has installed the permanent (single) fast start relay
for both diesel generators and has completed functional testing.
(Details, Paragraph 10.c)
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2.
Ng Inerting Problem
The licensee began reducing power from about '340 MWe at 10:00 A.M.
January 22, 1973. Power wrs reduced to approximately 292 MWe by
12:30 P.M.* when load reduction ceased.
(Details, Paragraph 3)
3.
Dead Fish Located in Lagoons and Marinas
Signs of fish morta11 ties apparently resulting from the shutdown
January 11-12, 1972 were observed coming to the surface. No
new kill was evident.
(Details. Paragraph 12.b)
20 JCP&L report to DL dated January 25, 1974, Subject A0 74-04.
21 JCP&L report to DL dated January 25, 1974, Subject A0 74-05.
22 JCP&L report to DL dated January 28, 1974, Subject A0 74-06.
23 JCP&L report to DL dated January 28, 1974, Subject A0 74-07.
24 JCP&L report to DL dated January 29, 1974, Subject A0 74-08.
- Change No. 19 to the Technical Specifications dated January 23, 1974.
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4.
Chromate Water Storage
Temporary storage of chromate water is continuing.
(Details,'
Paragraph 12.a)
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B.
Status of Previously Reported Unresolved Items
Not inspected
Management Interview
A management interview was conducted January 25, 1974 with Mr. D. A. Ross,
Manager, Nuclear Generating Stations and Mr. J. T. Carroll, Station
Superintendent. Messrs. Reeves, Chief Engineer; Swift, Maintenance
Engineer; Sullivan, Operations Engineer and Growney, Technical ingineer
were also in attendance for JCP&L.
Items discussed are summarized below:
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A.
General
The inspector summarized the scope of the inspection as related to a
review of operating logs and records, surveillance records, GORB and
PORC. committee meeting minutes and a review of Abnormal Occurrences
reported since the last inspection.
B.
Diesel Generator Modifications
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The inspector informed licensee representatives that he had reviewed
the final diesel generator "fix" and subsequent testing conducted and
that there were no further questions at this time. Licensee represent-
atives were also informed that a previous evaluation prepared by the RO
Technical Assistance Branch (TAB) would be incorporated as Details, Sec-
tion II to this report.
(Details, Paragraph 10.c and Details,Section II)
C.
Corrective Action Concerning Previously Identified Enforcement Items
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The inspector informed licensee representatives that corrective
action as described in Items 1, 3, 4 and 5 above had been reviewed
and that the inspector had no further questions concerning these
matters. The inspector noted, however, that commitment actions
should be completed in a timely manner referencing A0 73-28 dated
November 8, 1973 as an example. The 10 day report concerning this
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event specified procedural changes and such changes were not in
effect prior to the inspection.
A licensee representative stated that a system had been initiated by
approximately December 1, 1973 at the corporate staff level to close
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the loop on commitments. The licensee representative further stated
that this system ' is ' now working.
(Details, Paragraph 7)
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D.
Recirculation Loop Temperature Recorder and Multipoint Recorder
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The inspector stated that his review 1ndicated a disparity existed
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between the recirculation loop temperature recorder and multipoint
readings, such that assurance was not provided to adequately demon-
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strate compliance with the 50 temperature limit upon startup of an
idle loop.
A licensee representative stated that operators would be required to
monitor and record pump starts and further that the multipoint recor-
der would be examined for accuracy of readings during the next outage.
(Details, Paragraph 5.b(2))
E.
Chromate Water Storage
The inspector stated his position that continued storage of chromate
water in outside tank trucks no longer classified as " temporary
storage," and that this was considered an unacceptable arrangement.
(Details, Paragraph 12.a)
F.
Enforcement Items
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Licensee representatives were informed that violations (1-6 above)
previously disclosed arf. reported by the licensee would be identified
in the report following this inspection.
Items 7-9 under enforce-
ment action above were identified as apparent violations.
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DETAILS, SECTION I
pt;
1.
Persons Contacted
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Mr. D. A. Ross, Manager, Nuclear Generating Stations
Mr. J. T. Carroll, Station Superintendent
Mr. D. L. Reeves, Chief Engineer
Mr. J. L. Sullivan, Operations Engineer
Mr. J. P. Maloney, Operations Supervisor
Mr. R. F. Swift, Maintenance Engineer
Mr. E. J. Crowney, Technical Engineer
Mr. K. O. Fickeissen, Technical Supervisor
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Mr. E. I. Riggle, Maintenance Supervisor
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Mr. E. D. Skalsky, Radiation Protection Supervisor
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Mr. A. H. Rone, Assistant Staff Engineer
Mr. J. Henning, Staff Engineer
Mr. R. Stodnour, Staff Engineer
Mr. F. H. Rodies, Engineering Assistant
Mr. H. Kurtz, Local Marina Owner
2.
Administration and Organization
a.
Facility Staffing
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Recent changes and additions to the JCP&L staff were discussed
during a previous management meeting.*
b.
Plant Operations Review Committee (PORC) Meetings
The PORC met on the following dates and the minutes were reviewed
by the inspector.
No deficiencies were identified.
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Date
Meeting No.
be
October 2, 1973
38-73
October 3, 1973
39-73
October 4-6, 1973
40-73
October 15, 1973
41-73
October 15, 1973
42-73
November 1, 1973
43-73
November 7, 1973
44-73
November 8, 1973
45-73
November 13, 1973
46-73
- RO Inspection Report 50-219/73-18.
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c.
General Office Review Board Meeting Minutes (CORB)
The CORB met on the following dates and the minutes were reviewed
by the inspector. No deficiencies were identified.
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Date
Meeting No.
September 11, 1973
46
September 26, 1973
46A
November 9, 1973
46B
October 1, 1973
Subcommittee
(diesel generator
modification)
October 24-25, 1973
47
December 19, 1973
48
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3.
Operations
Reactor operations resumed December 20, 1973. On December 22, the
reactor was operating at about 340 MWe at 10:00 A.M.
A power reduction
was initiated to approximately 292 MWe when a temporary change to the
T. S. was issued by DL permitting operation with containment atmos-
phere greater than 5% 02 (torus). A nitrogen supplier arrived
onsite at about 1:45 P.M. and the licensee was in compliance with
Technical Specification 3.5.A 6 by 2:30 P.M.
At the conclusion of
the inspection the reactor was operating at 515 MWe (1600 MWt).
4.
Logs and Records
The following logs and records were reviewed without comment except-
as noted elsewhere within this report.
a.
Station Log Book - September 30, 1973-January 16, 1974
b.
Shift Foreman's Log - September 30,1973-January 16,19.'4
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Plant Operating Review Committee (PORC) meeting minutes - October 2,
c.
1973-November 13, 1973
d.
General Office Review Board (CORB) meeting minutes - September 26,
1973-December 20, 1973
Surveillance Records for the reactor coolant system and emergency
c.
power system for the periods as indicated within this report
f.
All Abnormal Occurrences since the last routine inspection
g.
Jumper memorandums dated July 19, 1969 and December 11, 1970
h.
Safety Valve certifications - May 4, 1973
5.
Primary System
The following surveillance records for the periods indicated were
reviewed by the inspector. No violations were identified.
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a.
Reactor Coolant Samples
Surveillance results for the period September 1,1973-January 7,
1974 were reviewed. The licensee analyzes samples on a daily'
basis. Records indicated that requirements of T. S. 3.3.E and
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T. S. 4.3.E were satisfied concerning content of chloride ion
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and conductivity.
b.
Thermal Transients
(1) lieatup and Cooldown
The inspector audited temperature recorder chart records on
a sampling basis for the period September 1, 1973-January 13,
1974. Records indicated that the average rate of coolant
temperature change did not exceed 100*F in any one hour
interval, the T. S. limit.
(2)
Idle Recirculation Loop Pump Start
The inspector audited recirculation loop temperature recorder
and multipoint recorder chart records on a sampling basis for
the period September 1, 1973-January 13, 1974. Records indi-
cated that the 50* T. S. limit was not exceeded. The inspec-
tor noted that multipoint recorder points were in some
instances printing inaccurate temperature indications, i.e.,
0-98*.
The inspector also noted that in some instances
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charts were not marked to indicate which pumps had been
started.
(Recirculation Loop Temperature recorder provides
a permanent record of any two (2) pumps.)
The inspector
discussed documentation requirements with respect to the
50* limit with a cognizant licensee representative. The
representative concurred with the inspector's comments and
stated that in the future, pumps when started would be iden-
tified to provide adequate documentation. The apparent
multipoint recorder problem was also discussed at the exit
interview.
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c.
Reactor Coolant System Leakage
Surveillance records for the period September 1, 1973-January 11,
1973 were reviewed, and indicated that limits of T. S. 3.3(d) were
not exceeded. An increased unidentified leakage rate occurred in
January 1974.* Unidentified leakage in general varied from 1.0-
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2.7 gpm.
Identified leakage for the period was approximately
4.0 gpm.
- RO Inspection Report 50-219/74-01, dated February 7, 1974
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d.
Valve Replacement
'During the 1973 refueling outage the licensee replaced five safety
valves as specified by Technical Specification 4.3.D.
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indicated'the following:
Records
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Valve No.
Setpoint (as installed)
BK 6259
1212
BK 6311
1221
BK 6310
1212
BK 6314
1212
BK 6533
1239
Certification wac provided by Dresser Industrial Valve's", Instrument
Division.
Setpoint settings for replacements complied with values
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listed in Technical Specification 4.3.D.
6.
Reactivity Control and Core Physics
a.
Hydraulic Control Unit (Accumulator) Level and Pressure Switch
Surveillance *
The licensee has written a procedure to complete surveillance
requirements. Records indicated all switches were checked on
September 11, 1973. Level switches tripped between 51-52 mi
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and pressure' switch actuation' occurred between 940-970 psig.
According to licensee representatives surveillance will be con-
ducted each refueling outage.
b.
APRM and Rod Block Monitor Settings
A review of A0 73-26 indicates that engineers have been directed and
corrective action taken to notify the Shift Poreman of the following
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information:
(1) Core total peaking factor and location
(2) APRM 100% setting and allowable peaking factor
(3)
Location and value of the MAPLHGR for each fuel type
(4)
Recirculation flow
(5) Approximate power
(6)
Specific instructions for further power level changes
(7)
Requirements for subsequent peaking' factor checks by Operations
(8)
When to' request engineering assistance.
Additionally, Shift foremen are now. required to complete a daily
check' list including average planar LUGR,-and peaking factor.
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- RO Inspection Report.50-219/73-13, Details, Paragraph 5.a.
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7.
Auxiliary Systems
RBCCW and Service Water Systems
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The inspector's review of A0 73-27 concerning closed cooling water
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system leakage to the discharge via a service water path indicated
that procedural changes had not been made as discussed in a licensee
letter.* The licensee issued a temporary change notice dated
January 25, 1974 specifying sampling requirements. The inspector
also discussed potential for generic indications of salt water cor-
rosion with a cognizant licensee representative.
8. . Electrical Systems
Momentary Loss of 125 V DC Power
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A review of events as described in A0 73-31 dated December 14, 1973
indicated the power loss was momentary. The inspector also reviewed
JCP&L memorandums dated July 14, 1969 and December 11, 1970 describ-
ing jumpers and their usage. Based on the above, the referenced loss
was caused when a jumper installation was improperly conducted and
without using a formal written procedure (VIOLATION) . The licensee
subsequently developed a procedure for jumper installation and removal
in response to R0 Bulletin No. 73-6.
The inspector discussed the level
of management review required (Shif t Foreman) with cognizant licensee
representatives. With respect to this event, the licensee has
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written and PORC had approved a procedure to check for ground on the
Battery "A" Bus or'"B" Bus.
The procedure review did not indicate
any apparent deficiencies.
9.
Containment
MSIV Spool Valve Problems
A review of A0 73-32 and A0 74-09 and discussions with licensee
representatives indicated that insufficient residue was available
for analysis. The licensee initiated a new procedure prior to
returning the plant to operation following the failure January 16,
1974 to insure that'N2 has replaced air on the inner MSIV's. Param-
eters are observed during the daily 5% closure tests, as indicative
of possible problems. For operation, the licensee has established
a 100 psi minimum pressure (compressor) to assure a N2 atmosphere.
- JCP&L letter to DL dated November 8, 1973.
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10. Emergency Power-
The following surveillance records for the periods' indicated were'
reviewed by the inspector. - One violation with respect to test fre-
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quency was identified.
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a.
Diesel Generator
(1) Load Testing Every Two Weeks
January 1,1973-January 7,1974.
(2) Automatic Actuation
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June 1-2, 1973.
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(3) Annual Inspection
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August 19, 1973.
(! ' Starting Batteries
January 1-December 31, 1973. Records of weekly tests and
monitoring for diesel generator starting batteries indicated
that for the interval May-June, 1973 tests were conducted
May 10, 21, and June 8.
These test dates did not correspond
agpq
to the weekly frequency specified by Technical Specification 4.7. A.5 (VIOLATION) .
(5) Fuel Supply
February 1973-January 15, 1974. Records reviewed indicated
that a minimum of 14,500 gallons was maintained as required
by T. S. 3.7.C.4.
,
(6) Load Testing of D. G. Batteries (6 Month)
D. G. No. 1 and No. 2.
May 16, 1972-December 20, 1973.
b.
Station Batteries
(1) Specific Gravity and Voltage Checks
-January 1-December 1 31, 1973. Records of weekly tests
concerning station batteries indicated that for the
period May-June 1973 tests were conducted May 10, 21,
and June 8.
These test dates failed to correspond to
E
,
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1
B
_
.
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-
-
.
.
-
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-15-
the weekly frequency specified by Technical Specification
4. 7.B.1 (VIOLATION) .
.
(2)
_ Cell Voltage Measurements (Monthly)
- p.hl.<j
O,TjA
January 1-December 31, 1973.
(3)
Specific Gravity. Temperature. Electrolyte, and Water
Addition (3 Months)
January 1-December 31, 1973.
(4)
Load Testing of Station Batteries (6 Month)
Station Batteries A and B, April 21 1972-Decembst'13,1973
..
c.
Diesel Generator Modification
Records reviewed and discussions with licensee representatives
indicated that the licensee has installed a single relay for
each diesel generator to replace relays referenced in Details
.
Section II.
Figures 1-2. Simplified schematics of this change are shown in
,
diesel generator modification. Records indicated PORC and GORB rev
The FSR-A relays for both
j
generators was installed and tested on January 3 and 7, 1974.
'
According to licensee representatives the fast start testing
resulted in a successful start of both units with an engine
eggg
fault present.
approved procedure. Testing was conducted in accordance with an
11. Radiation Protection
Survey Instrument Calibration Log
a.
The inspector reviewed deficiencies identified in a previous
. _;
inspection.*
maintained.
Forms and sheets are now properly completed and
'
new control system in this area.The licensee is in the process of impic
i
These items are considered
closed.
Discussion with cognizant personnel indicated the
Radiation Protection Supervisor has assumed responsibilities
in this area.
b.
_ Main Steam Line Radiation Monitor Failure
A review of A0 73-34 and the plant logs indicated that followi
the monitor failure on December
ng
27, 1973, a one half scram
'
- R0 Inspection Report 50-219/73-13, Details, Paragraph 7 b
,
.
.
'
, .
.-
..
-16-
-
(Protection system action) was introduced on two separate
occasions. Following surveillance testing monitors B, C and
D vere also tested.
12. Environment
.
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a.
Chromate Water Storage
As a result of the recent chromate water spill * the licensee has
increased surveillance to one tour / hour in addition to shift tour
rounds. The acceptability of continuing storage was also dis-
cussed at the exit interview.
b.
Fish Mortalities
The inspector visited a local marina and visually observed fish
mortality signs from the marina dock. According to a marina
'
owner, signs of dead fish appearing at the water 's surface had been
evident for several days. Gull activity was also present. The
inspector cbserved no fish in distress and based on state of
putrefaction, the fish sighted appeared to be the result of a pre-
vious shutdown (January 11-12, 1974).
Numbers were estimated by
the inspector to be approximately 2,000 fish.
13. Miscellaneous
Late Reports
YNF4
The inspector audited abnormal occurrence reports and attendant 10
day reports pursuant to requirements of the Technical Specifications.
,
'
Review indicated the following late reports filed by the licensee.
24 Hour Report
A0 73-23-1
10 Day Reports
,
A0 73-22
A0 73-24
A0 73-32
A0 73-34
(VIOLATION)
- JCP&L letter to DL dated January 3, 1973.
,
$
. .
.
.
.
.
,
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.
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.
.
DETAILS, SECTION II
'
.Section II - Diesel Generator Circuit Modifications (V. Tho
,
- Ed >
i $. p
1.
_Ceneral
s
This section discusses the electrical aspects of the restart pr bl
'
experienced with both diesel generators during the recent loss of off
o em
site power event.1-
.
!
the licensee's abnormal occurrence report,1The scope of review
-
'
rective measures taken to prevent recurrence.and the adequacy of cor-
2.
Persons Contacted
.
.
. . .
Joseph T. Carroll, Plant Superintendent
"' '
-
E. I. Riggle, Maintenance Supervisor
i
Thomas Johnson, Electrical Maintenance Foreman
'
3.
Diesel Generator Modifications
The licensee stated that subsequent to the problem experienced with
the diesel generators during the loss of power event
into the matter resulted in modifications of the die
, investigation
start, and restart circuitry.
These corrective measures are dis-
sel unit 's fast-
of the diesel generator's starting circuitry. cussed below
,3gj
i
The corrective measures taken by the licensee involved the
installation of two relays and a jumper wire.
The two " fast-start"
auxiliary relays identified as FSRA (time delay) and FSRA
(instcntaneous), are installed parallel to the existing " fast st
t
relay (FSR).
tacts of the " deadline" (DLU) relay.The jumper wire is installed aro
art"
-
4
now permit the FSR, FSRA, and FSRA
In effect, these modifications
though an engine-fault is present.taneously upon loss of po
,
us even
is made possible because of the following additional circuitThis autom
ch.anges:
.
a.
A set of contacts from each new relay, FSRA and FSRA
installed in a series parallel circuit arrangement
I is now
sel generator's engine-fault reset circuitty.around the e
-
1 Licensee's Report to Licensing dated September 18
Oyster recek - Docket No. 50-219, Power Failure. ,1973, Subject:
'
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b.
The set of contacts from the FSRA relay has a five second time
delay "to open" feature while the other set of contacts from
r
the FSAR . relay has an instantaneous "to close" feature.
,
i
'
This
mode of bontact operation occurs only when FSRA and FSRA
',
.
I relays
are energized.
?b
. tr,. , ,1
In summary, the contact operation combined with the circuit arrangement
as discussed now provided the licensee with a " built-in" automatic five
,
second reset feature to. clear any engine-fault during a diesel genera-
,
- -
tor fast-start situation.
There is no longer a need to manually reset
'
q
the machine to obtain a " fast-start" following a manual shutdown of the
unit.
.effect during manual operation of the' diesel generator.
In annualIt is well to note, however, that the auto-re
'
operation, local reset action following unit shutdown is still required.
..
The licensee also stated that the above modifications were reviewed by
-
.
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the Plant Operations Review Committee (PORC) as required, and the pro-
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posed fix was found to be acceptable.
The modifiestions were completed
o
by October 1, 1973.
circuitry was successfully tested in that, Subsequently, the diesel unit'
,
to a fast-start condition while an engine fault existed.the unit properly respondi
Our review of the above circuit modifications revealed that these
corrective actions have been completed. We also reviewed the
1
licensee's abnormal occurrence report, and his test procedures of
'I
the diesel unit following the above modifications, and no items of
discrepancy were noted.
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