IR 05000317/1978026
| ML20062C973 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/06/1978 |
| From: | Dante Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062C957 | List: |
| References | |
| 50-317-78-26, 50-318-78-20, NUDOCS 7811150276 | |
| Download: ML20062C973 (12) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__
.
-'
-
C i l
U.S. NUCLEAR REGULATORY COMMISS10N OFFICE OF INSPECTION AND ENFORCEMENT
,
Region I Report No. 50-317/78-26; 50-318/78-20 Docket No. 50-317, 50-318 C
License No. OPR-53; DPR-69 Priority Category C
--
Licensee:
Baltimore Gas and Electric Company P. O. Box 1475
.
Baltimore, Maryland
Facility Name:
Calvert Cliffs Nuclear Power Plant, Unit 1 and 2 Inspection at:
Lusby, Maryland
'spection conducted-Sep mber 12-15, 1978 Inspectors:
se
/4 77 ~
D. F. J6finson, ~ Reactor Inspector date signed date signed
.
date. signed,-
,
,
Approved by-
^ ec. #
/4 - f-J'd r
R.R.Kei6g, hief eactor Pro,jects date signed Section No. 1 R0 Branch isoection Summary:
Inspection on September 12-15, 1978 (Report Nos. 50-317/78-26 and 50-318/78-20. )
Areas Inspected:
Routine unannounced inspection by a regional based inspector of plant operations including shift logs and records; licensee followup. actions on selected licensee event reports; licensee's preparations for refueling of Unit 2; and a facility tour.
The inspection involved 18 inspector-hours onsite for Unit 1 and 12 inspector-hours onsite for Unit 2 by one NRC inspector.
,
Results:
'
Of the four areas inspected, no items of noncompliance were found in three areas; one apparent item of noncompliance was found in one area (Infraction-failure to caaply with limiting conditions for operation Paragraph 2).
'
_.
Region I Form 12 (Rev. April 77)
- - ___ _ _______ _ _ _ _ - _ _ _ _ -
'-
~
-6 l
.
.
,
-
,
.
.
r i
(
l
__
i
-
DETAILS
!
!
1.
Persons Contacted
-
,
Mr. J. Carroll, Perfonnance Engineer (Operations)
!
i
- Mr. R. Denton, Supervisor-Technical Support
Mr. R. Douglass, Chief Engineer Mr. S. Jones,_ Training Coordinator
~
i Mr. A. Kaupa, Radiation Safety and Chemistry Engineer i
- Mr. J. Lemons, Nuc' lear Plant Engineer (Maintenance)
J Mr. J. Miernick, Performance Engineer (Maintenance)
i Mr. P. Rizzo, Assistant General Foreman, Instrument Control /
.
Electrical i
Mr. M. Roberson, Assitant General Foreman '(Maintenance)
!
- Mr. L. Russell, Nuclear Plant Engineer (Operations)
i Mr. D. Thomas, Senior Training Specialist i
Mr. P. Walsh, Senior Engineer
}
Mr. K. Watkins, Performance Engineer (Maintenance)
!
Mr. J. Watson, Shift Supervisor
'
.
i The inspector also talked with and interviewed several other i
i licensee employees during the ins;)ection.
They included reactor operators, plant operators, technic.al staff and general office j
personnel.
1-'
- denotes those present at, exit interview.
2.
Failure to Fully Comply with Technical Specification Section 3.4.6.1
,
}
The containment particulate radioactivity monitoring system was
"
taker. out of service on August 17, 1978 due to a component failure.
Following corrective action, the monitor was returned to service on August 25, 1978.
Licensee Event Report (LER 78-28/3L) describes j
this event. With the particulate monitor inoperable, Technical
!
Specification Section 3.4.6.1 requires that grab samples of the
containment atmosphere be obtained and analyzed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j Pursuant to this requirement, Radiation-chemistry personnel were i
instructed to begin drawing grab samples on August 17, 1978.
However, due to failure of the licensed operator to verify that the
required samples were taken at the prescribed interval, samples were not obtained on August 19, 1978 and August 20, 1978.
The i
failure to obtain the required samples constitutes' an Item of j
Noncompliance at the Infraction leeel. (318/77-20-01)
.
!
.
~
,.
-
..
.
_-
--
.
.
-
- -
i
'
l
l 3.
Review of Licensee Event Reports (LER'S)
The inspector reviewed LER's to verify that details of the events were clearly reported including the accuracy of the description of cause and adequacy of corrective action.
The inspection determined whether further information was required-from the licensee and whether the event had generic implications.
The following Unit I LER's were reviewed.
LER 78-1/3L, dated January 9,1978; Azimuthal power tilt
--
exceeded limit of 0.02 on several occasions during previous 30 day per? *
LER 78-2/3L, dated January
--
31, 1978; CEA No. 32 dropped fully into the core due to a failed 15 volt power supply.
LER 78-3/lT, dated February 1,1978; RCS unidentified leakage
--
was 1.61 gpm, exceeding the 1.0 gpm T.S. limit, attributed to stem packing leakage on a pressurizer instrument root valve and a spray valve.
LER 78-4/lT, dated February 7,1978; While in cold shutdown
--
mode, shutdown ecoling was secured for 77 minutes due to tube leakage from No.11 Heat Exchanger.
LER 78-5/3L, dated farch 14, 1978; While handling irradiated
--
fuel within the containment, the interlock on the containment air lock doors failed, resulting in a momentary opening of both the inner and outer doors.
LER 78-6/3L, dated February 22, 1978; Failure of the trip
--
actuation lever on the breaker to #12 low pressure safety injection (LPSI) pump preventing tripping of the pump from the control room.
j LER 78-7/IT, dated February 1,1978; Both MSIV's failed to
--
close within the 3.6 seconds T. S. limit during full stroke
testin3 LER 78-8/3L, dated February 1,1978; Azimuthal power tilt
--
exceeded 0.020 T.S. limit on four occasions during past 23-day perio.,.
.
.
LEh 78-9/3L, dated February 2,197P* RCS boron concentration
--
decreased to slightly less than the 1720 ppm T.S. limit while in Mode 5, due to mixing of stagnant water in hot and cold
<
legs with higher boron concentration coolant in the_ vessel.
LER 78-10/3L, dated February 7 1978; Various meteorological
--
instrumenti became inoperable due to freezing weather conditions.
LER 78-ll/lT, dated March 1,1978; During refueling a clad
--
failure was observed on one external fuel rod in fuel bundle 18060. The fuel bundle was removed from the core and will not be reused in the reloaded core.
LER 78-12/1T, dated February 27, 1978; Safety injection tank
--
(S. I. T.) level transmitters were discovered to be indicating erroneous levels.
LER 78-13/3L, dated March 10, 1978; The maximum cooldown rate
--
of the reactor coolant system of 100 F per hour was exceeded by 3*F.
LER 78-14/3L, dated March 21, 1978; During performance of a
--
Technical Specification required surveillance test, it was discovered that the Halon storage tanks on a fire suppression system were less than the required full charge weight.
LER -78-15/3L, dated April 7,1978; While handling irradiated
--
fuel, the personnel air lock doors were momentarily opened at the same time as a result of operator error.
LER 78-16/3L, dated May 1,1978; During normal operation, a
--
slight leak was discovered on the charging pump suction line relief valve.
LER 78-17/3L, dated April 27, 1978; During performance of a
--
surveillance test, nine of the sixteen safety valves were found to be outside the settings allowed by the Technical Specification Table 4.7.1.
LER 78-18/3L, dated May 24, 1978; During a scheduled test of
--
the cable spreading room halon subsystem, #4 halon subsystem was inadvertently discharged.
!
!
.
i
_ _ _ _ - _ _ _ _ _
.
.
_.
.
.
.
,
.
LER 78-19/3L, dated April 28, 1978; During scheduled surveil-
--
lance testing. #12 diesel generator service water supply valve failed to open automatically.
LER 78-20/1T, (Update Report), dated April 27, 1978; Loss of
--
all offsite power.
Diesel generator #11 failed to start and supply emergency power to #114KV bus.
LER 78-21/3L, dated May 1,1978; During norral operation,
--
leakage from a valve stem packing (letdown isolation valve)
exceeded the 10 GPM limit of the Technical Specifications.
LER 78-22/3L, dated April 17, 1978; During normal operation,
--
an unidentified leak was discovered in the reactor coolant system which exceeded the 1 GPM Ifmit of the Technical Speci-fication.
The reactor was shutdown and the leak identified.
LER 78-24/3L, dated May 17, 1978; During surveillance testing,
--
it was discovered that one cli in battery #22 was below the minimum voltage.
The cell was immediately charged.
LER 78-25/3L, dated April 27, 1978; During surveillance
--
testing, #12 diesel generator oversped and tripped when s tarted.
LER 78-26/3L, dated April 27, 1978; Protective relaying auto-
--
matica11y opened breakers in the 500 KV switchyard that resulted in deenergizing vital 4 KV bus 11.
- 11 emergency diesel generator started but the output breaker failed to automatically close.
LER 78-27/3L, dated June 20, 1978; During normal operation,
--
- 12 control room air conditioning unit was discovered in-operable and would not start.
LER 78-28/1P, dated June 5,1978; During normal operation,
--
power tilt limits were exceeded due to a dropped CEA.
LER 78-29/3L, dated June 22, 1978; CEA #20 dropped to the
-
bottom of the core during normal power operation.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
j
LER 78-30/3L, dated June 29, 1978; During surveillance i
--
testing, the contain.,1ent pump isolation valve failed to close '
l within prescribed time limits.
LER 78-31/3L, dated June 29, 1978; A pinhole leak developed on
--
the flange to the charging pump discharge relief.
The leak was a result of a cracked weld.
,
LER 78-32/4T, dated June 26, 1978; A large fish impingement on
--
the travelling screens occurred due to depletions.of oxygen concentrations in bottom water in the intake area.
LER 78-33/3L, dated July 7,1978; During nornal operation, #12
--
control room air conditionte unit stopped.
The cause was a bearing seizure that stopped the motor.
LER 78-34/3L, dated July 27, 1978; During normal operation, an
--
"SIAS Actuated" alarm was received due to a logic module failure.
LER 78-35/4T, dated July 14, 1978; While operating at steady
--
state power, the temperature rise across the main condensers rapidly increased and exceeded the aT limit.
LER 78-36/4T (Update), dated July 27, 1978; The temperature
--
rise reported in LER-35/4T was caused by a rapid drop in circulating water injection temperature.
LER 78-37/3L, dated August 17, 1978; With the reactor in hot
--
standby, #12 MSIV accumulators were found to be depressurized as a result of an oil leak.
LER 78-38/3L, dated August 17, 1978; CEA #60 dropped to the
--
bottom of the core during normal power operation.
LER 78-39/3L, dated August 25, 1978; During normal power
--
operation, CEA pulse counting position indication was lost due to a plant computer failure.
LER 78-40, dated August 31, 1978; During normal operation. #4
--
main turbine control valve failed shut due to a faulty sole-noid and servo valve on the operating cylinder.
.,
.
.
t
LER 78-41, dated August 24, 1978; During normal operation
--
while testing the halon fire suppression system, three halon bottles were found below their minimum allowable weight.
The following Urit 2 LER's were reviewed.
LER 78-1/3L, dated February 2,1978; No. 21 MSIV was inoperable
--
after inadvertent shutting due to a positive ground in its control circuit.
LER 78-2/3L, dated FeLruary 7,1978, No. 21 Emergency Diesel
--
Generator tripped on generator fault during routine testing, due to a reverse power condition with the diesel operating in parallel with the main generator.
LER 78-3/3L, dated February 10,1978; No. 21 Service Water
--
Heat Exchanger salt water outlet valve was inoperable due to jamming of the seat disc.
LER 78-4/lT, dated February 27, 1978; Safety injection tank
--
(SIT) level transmitters were discovered to be indicating erroneous levels.
LER 78-5/3L, dated February 22, 1978; During normal operation,
--
a leak developed via a cracked weld on the reactor coolant charging pump common suction line.
LER 78-6/3L, dated February 1,1978; CEA No.1 dropped fully
--
into the core, while insertin due to undeterminable cause. g its regulating group, LER 78-7/3L, dated February 2,1978; 21B Safety Injection Tank
--
boron concentration was found slightly below the T.S. limit due to operator failure to determine resultant baron con-centration pri~or to filling the tank.
LER 78-8/3L, dated March 14, 1978; Inability to align Channel
--
B wide range neutron detector (WRNI) due to a high capacitance connection at the detector.
LER 78-9/3L, dated March 8,1978; CEA #33 dropped to a full in
--
position.
Power was reduced to 70% and CEA #3 was restored to
,
its group position.
'
I
_
_
_
_
_
.
,-
.
.
LER 78-ll/3L, dated May 25, 1978; During normal power operation,
--
a cracked weld was discovered on #21 charging pump suction header.
LER 78-12/3L, dated May 25, 1978; While performing routine
--
surveillance testing, hydraulic snubber 2-52-7 was found to have a dry reservoir due to a leak.
LER 78-13/3L dated June 15, 1978; While operating in mode I, a
--
reactor coolant system leak was identified caused by a crt ked weld in the sensing line to the reactor coolant pump.
LER 78-14/3L, dated June 6,1978; While at steady state power
--
level, CEA #5 dropped to the bottom of the core when it was being exercised during a surveillance test.
LER 78-15/3L, dated June 29, 1978; During surveillance
--
testing, #21 diesel generator failed to start remotely from the control room.
LER 78-16/31 dated July 7, 1978; During corrective mainten-
--
ance, an isolation transformer was found to be defective in the steam generator low pressure safety features activation system.
LER 78-17/lT, dated June 29, 1978; Due to an operator error,
--
the safety injection tanks were filled above the administra-tive limit of 192".
LER 78-18/3L, dated July 13, 1978; During normal operations, a
--
leak developed on the charging pump suction header due to a cracked weld.
LER 78-19/1T, dated July 13, 1978; A cracked weld was dis-
--
covered on 218 reactor coolant pump seal cooling heat exchcnger.
Pressure boundry leakage necessitated placing the reactor in cold shutdown to effect repairs.
LER 78-21/lT, dated July 27, 1978; Weld repairs on the RCP
--
heat exchanger (reported under LER-19) were inadequate.
Additional weld repair was performed to isolate reactor coolant system leakage.
.s
,
.
.
.
.
LER 78-22/3L, dated August 17, 1978; During performance of
--
monthly surveillance testing, CEA #5 dropped to the bottom of the core.
P LER 78-23/3L, Dated August 25, 1978; During normal power
-
--
operation, all CEA pulse counting position indication was lost due to a plant computer malfunction.
LER 78-24/3L, dated August 24, 1978; Reactor coolarit system
--
leak caused by a cracked weld on the suction line of the charging pumps.
LER 78-25/3L, dated August 17, 1978; During surveillance
--
testing, #21 diesel generator tripped on high jacket coolant temperature when its service water supply valve failed to open.
LER 78-26/3L, dated August 24, 1978; Due to a dropped CEA,
--
azimuthal tilt exceeded Technical Specification limits.
LER 78-31/lT, dated September 8,1978; During normal operation,
--
the boron concentration in both safety injection tanks 218 and 22B were found to be below Technical Specification limits. The reactor was placed in hot standly.
The inspector's findings regarding licensee event reports were acceptable unless otherwise noted below.
The inspector verified by review of representative records and by interviews with licensee personnel that appropriate corrective action has been taken with regard to the above LER's.
However, the inspector pointed out to the licensee (by reference to specific LER's) that corrective actions and measures to prevent recurrence are not always addressed.
The inspector further stated that if the cause of the event is unknown at the time and later. identified, supplemental reports are required to fully describe final resolution of the occurence.
The licensee concurred with the inspector's connents and stated that all future LER's submitted would be reviewed in more detail to ensure the above areas are adequately described.
No items of noncompliance were identified.
>
-
.
.
.
.
4.
Review of Plant Operations (Units 1 & 2)
'
The inspector reviewed the following logs and records:
Control Room Operators Log for the period from August 1,1978
.
--
through September 7,1978.
l Control Room Log Sheets for the period from August 1, 1978
--
through August 31, 1978 Event Log; entries made during July 1,1978 through September
--
1,1978.
Check lists for Non Routine Technical Specification Reports
--
Requiring Timely Reporting; issued during July 8,1978 through September 13, 1978.
The logs and records were reviewed to verify the following items:
Log kee~ing practices and log book reviews are conducted in p
--
accordance with established administrative controls.
Log entries involving abnormal conditions are sufficiently
--
detailed.
Operating orders do not conflict with Technical Specifications.
--
Problem identification reports confirm ccmpliance with Tech-
--
'
nical Specification reporting and Limiting Conditions for Operation requirements.
Log book reviews are being conducted by the staff.
--
Acceptance criteria for the above review included inspector judge-ment and requirements of applicable Technical Specifications and the following administrative control procedures.
CCI-106, "Special Orders by the Chief Engineer," Original,
--
April 24,1972.
CCI-ll4, " Plant Logs," change 8. January 9, 1978.
--
--
.
.
-
.
. =
.-
.
.
.
,
11
,
,
!
CCI-118 "Nonroutine Technical Specification Reports Requiring
--
Timly Reporting," Orginal, September 22, 1977.
}i The inspector's findings regarding shift logs and operating records were acceptable, except as noted below.
The inspector noted during his review of control room log sheets that on five occasions readings above the stated acceptance criteria were recorded with no accompanying annotatiLns as to the reason for the out of specification readings, the rsadings being circled as -
!
required by Calvert Cliffs Instruction 114, attachment (5), Step 4,
f that states, "Each log sheet specifies the high and low limits anticipated for most parameters...any reading outside this normal range will be circled and a comment entry made concerning the reason." Similar occurences of this nature were identified in NRC
,
i Inspection Report 50-317/78-25 and 50-318/78-19 conducted on lj September 5-8, 1978.
The item identified in report 50-318/ 78-19 was cited as an item of noncompliance (318/78-19-03) against Technical Specification 6.8.1 for failure to follow procedures.
The findings of this inspection constitute additional examples of
the same item of noncompliance. The licensee's response to the item j
of noncompliance previously cited will be examined to verify that the corrective measures taken are adequate in regard to the items identified in this report.
t j
5.
New Fuel Receipt and Inspection
]
The inspector reviewed the new fuel inspection checkoff sheets and
verified that they were completed in accordance with procedure FH-
!
1, "New Fuel Assembly and Control Element Assembly Handling, Inspec-tion and Storage."
.
No items of noncompliance were identified.
,
6.
Facility Tour
,
At various times during the period of September 12-15, 1978, the
-
inspector conducted tours of the following accessible plant areas:
Auxiliary Building
--
.
!
,
.
-
-. -
_
_
-.
.
-
-
.
--
-
- __
- __
.
.
.
.
'..
.
Turbine Building
--
Control Room
--
Outside Peripheral Areas
--
New Security Building
--
During the inspection tours, observations relative to the following items were acceptable:
plant housekeeping and cleanliness;
--
posting of radiation areas, access control, and currency of
--
survey; security access controls;
--
control room manning and assignment of licensed operators
--
pursuant to the Technical Specifications; and, selected monitoring instrumentation - operability and para-
--
meters within license limits.
No inadequacies were identified.
7.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on September 15, 1978.
The inspector sunnarized the purpose and scope of the inspection and the findings presented in the details of this report.
,
.
_ _ _ _ _ _ _ _ __
_ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - -
' ~ ~ ~