IR 05000416/1988017
| ML20153F641 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/26/1988 |
| From: | Butcher R, Dance H, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20153F620 | List: |
| References | |
| 50-416-88-17, NUDOCS 8809070380 | |
| Download: ML20153F641 (8) | |
Text
UNITED STATES
/p. [8 tg
'o NUCLEAR HEGULATORY COMMISSION
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.. j 101 MARIETTA STREET.N.W.
- AT L ANTA, G EORGI A 30323 l
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I Report No.:
50-416/23-17 Licensea:
System Energy Resources Inc.
Jackson, MS 39205 Docket No.:
50-416 License No.:
NPF-29 Facility Name:
Grand Gulf Nuclear Station Inspection Cendu-ted: July 16 through August 19, 193.R C-Vw g_2_{ohf_
'a n spectors:
csu u E. C Butcher, Senio Resident Inspector ate Signed
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6ffY J. L Mathisi ident Inspector late signed Approved by:
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. C. Da.ce,' Section Cnief, Oivision D5te igned of Reactor Projects SUMMARY Scope:
This routine inspection was conducted by the resident inspectors at the site in the areas of Licensee Action on Previous Enforcerent Matters, Operational Safety verification, Maintenance Observation, Surveillance Observation. ESF System Walldown, Reportable Occur-rences, Operating Reactor Events, and Inspector Followup and Unresolved items.
Results:
In the areas inspected, violations or deviations were not identified.
In general, the licensee's organization performeo quite effcctivi t in analy:ing the cause of the reactor scram cn August 15, 19*S, and getting the plant back on-line tinly.
BBTS885!8?88l$66
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REPORT DETAILS
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Persons Contacted Licensee Employees J. G. Cesare Director Nuclear Licensing L
0. G. Cupstid, Superintendent, Technical Support
- L. F. Daughtery. Compliance Supervisor
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J. P. Dimmette, Manager, Plant Maintenance
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S. M. Feith, Director, Quality Programs C. R. Hutchinse, GGNS General Manager R. H. McAnultv, Electrical Superintendent
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A. S. McCurdy, Technical Asst., Plant Operations Manager
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L. B. Moulder, Operations Superintendent
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J. H. Mueller, Mechanical Superintendent J. V. Parrish, Chemistry / Radiation Control Superintendent t
J. L. Robertson, Superintendent, Plant Licensing R. F. Rogers, Manager, Special Projects S. F. Tanner, Manager, Quality Services L. G. Temple, I & C Superintendent F. W. Titus, Director, Nuclear Plant Engineering
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"M. J. Wright, Manager, Plant Support J. W. Yelverton, Manager, Plant Operations i
Other licensee employees contacted included technicians, operators, f
j security force members, and office personnel.
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- Attended exit interview
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Acronyms and initialisms used throughout this report are listed in the l
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last paragraph.
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I 2.
Licensee Action on Previous Enforcement Matters (92702)
l Not inspectcd this report period.
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Operational Safety, Radiological Protection and Physical Security Verification (71707, 71709 and 71831)
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The inspectors kept themselves informed on a daily basis of the overall
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plant status and any significant safety matters related to plant operations. Daily discussions were held with plant management and various members of the plan *. operating staff.
L The inspecters made frequent visits to the control room such that is was
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visited at least daily when an inspector was on site.
Observations
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included instrument readings, setpoints and recordings, status of
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operating systems, tags and clearances on equipment controls and switches, j
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annunciator alarms, adherence.to limiting conditions for operation,
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temporary alterations in effect, daily journals and data sheet entries,
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control room manning, and access controls.
This inspection activity j
included numerous informal discussions with operators and their l
supervisors.
Weekly, when the inspectors were onsite, selected Engineered. Safety Feature (ESF) systems were confirmed operable.
Tiie confirmation is made by verifying the following: Accessible valve flow path alignment, power
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supply breaker and fuse status, major component leakage, lubrication,
cooling and general condition, and instrumentation.
t General plant tours were conducted on at least a biweekly basis. Portions l
of the control building, turbine building, auxiliary building and outside j
areas were visited.
Observations included safety related tagout
verifications, shif t turnover, sampling program, housekeeping and general
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plant conditions, fire protection equipment, control of activities in I
progress, problem identification systems, and containment isolation. The
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licensee's onsite emergency response facilities were toured to determine i
facility readiness.
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The inspectors reviewed at least one Radiation Vork Permit (RWP), observed
health physics management involvement and awareness of significant plant
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activities, and observed plant radiation controls. The inspectors verified (
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licensee compliance with physical security manning and access control i
requirements.
Period dally the inspectors verified the adequacy of physical security detection and assessment aids.
i No violations or deviations were identifted.
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Maintenance Observation (62703)
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During the report period, the inspectors observed portions of the maintenance activities listed below.
The observations included a review t
of the Maintenance Work Orders (Md0s) and other related documents for f
adequacy, adherence to procedure, proper tagouts, adherence to technical
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specifications, radiological controls, observation of all or part of the actual work and/or retesting in progress, specified retest requirements, r
and adherence to the appropriate quality controls.
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NO MS25S2 Retorque Starting Air Valve Capscrew for Division 2 Diesel i
Generator.
WO M33316 Charge with Nitrogen Standby liquid Control Pulsation Campers.
WO M31963 Inspect Flange Holes; Remc.e Cut-of f Stud and Refurbish MSRVs as Required for Shipment to Wylie Li.boratory.
Vd0 M33347 Rework SLC Test Connection Valve PPN402.
No violations or deviations were identifie _ _ _ _
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5.
Surveillance Observation (61726)
The inspectors observed the performance of portions of the surveillances listed below.
The observation included a review of the procedure for technical adequacy, conformance to technical specifications, verification of test instrument calibration, observation of all or part of the actual surveillances, removal from service and return to service of the system or components affected, and review of the data for acceptability based upon the acceptance criteria.
06-0P-1P75-M-0001, Revision 34, Standby Diesel Generator (SDG) 11 Functional Test.
06-IC-1E12-M-0001, Revi sion 23, LPCI System C Discharge Line High/ Low Pressure Functional Test.
06-EL-1821-M-0002, Revision 27, ADS Timers Functional Test and Cali-bration.
06-0P-1PS1-M-0002 Revision 31 HPCS Diesel Generator 13 Functional Test and Calibration.
06-EL-1E12-M-0002, Revision 25, Containment Spray Time Delay Relay.
06-0P-1821-V-0001, Revision 24, MSI'l Operability Test.
06-IC-1821-M-1005, Revision 23, Main Steam Line Low Pressure Channel B Functional Test.
No violations or deviations were identified.
6.
Engineered Safety Features System Walkdown (71710)
A complete walkdown was conducted on the accessible portions of the High Pressure Core Spray (HPCS). The walkdown consisted of an inspection and verification, where possible, of the required system salve alignment, including valve power available and valne locking where required, instrumentation valved in and functioning; e'ectrical and '.nstrumentation cabinets free f rom debris, loose materials, jptpers and evidence of rodents, and system free from other degrading condisons.
No violations or deviations were identified.
7.
Reportable Occurrences (90712 & 92700)
The below listed event reports were reviewed to determine if the information provided net the NRC reporting requirements. The determina-tion included adequacy of event description and corrective action taken or planned, existence of potential generic problems and the relative safety significance of each event. Additional inplant reviews and discussions
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I with plant personnel as appropriate were conducted for the reports l
indicated by an asterisk. The event reports were reviewed using the
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guidance of the general policy and procedure for NRC enforcement actions,
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l regarding licensee identified violations.
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The following License Event Reports (LERs) are closed.
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LER No.
Event Date
, Event
'S7-016 October 1, 1937 Area Radiation Survey Exceeced t
LCO Time Limit.
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- S7-013 December 14, 1987 Late Surveillance During Core f
Alterations.
a No violations or deviations were identified.
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8.
Operating Reactor Events (93702)
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The inspectors reviewed activities associated with the below listed
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reactor events.
The review included cetermination of cause, safety
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significance, performance of. personnel and systems, and corrective action, r
The inspectors examined instrument recordings, computer printouts,
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operations journal entries, scram reports and had discussions with (
operations, maintenance and engineering support personnel as appropriate.
At 4: 17 a. m., on July 27, 1938, the control room operators observed
approximately a 3*. decrease in reactor power with a corresponding decreast:
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in reactor vessel water level, feedwater flow and steam flew, Core
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thermal power deceeased from 3831 Pd at 4:17 a.m.,
to 3706 K4 at
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4:20 a.m., and roturned to 3331 Kd at 4:25 a.m.
The B loop recirculation
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j flow dropped from 41,000 GPM and then returned.
Incident Report 88-7-3 (
was written to docurrent this event. A Maintenance Work Order (KdO) S3422
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was initiated to trouble shoot the B recirculation flow control system.
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At 10:49 a.m.,
on July 27, 1983, another perturbation in the B j
recirculation flow was observed and reactor thermal power decreased from
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j 3333 F4 to 3S03 Rd.
The perturbations were severe enough to cause the B
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recirculation flow control valve Hydraulic Power Unit (HPU) to lock up at i
approximately the 60'. open. position.
There was approximately a 3 '.
j mismatch between recirculation loops so the HPU was unsecured for flow j
adjustment and then resecured.
Chart recorders were then connected to monitor the HPV panel.
No safety features or TS requirements were
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affected. The licensee's troubleshooting could not identify the cause of I
the certurbations and discussions with GE and Foxboro indicated the most
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likel t component to cause such events would be the ficw control valve t
i runback relay card.
The licensee replaced the runback relay card as a l
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precautionary measure and is continuing to r onitor the HPU panel.
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i July 28, the licensee put the B recirculation loop thru the perturbations
j experienced on July 27, 1933, with na abnorralities noted.
Since the l
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noted perturbations are intermittent and no cause could be cetermined l
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4 during troubleshooting the licensee is continuing to monitor the flow control system.
Followup of 'icensee's investigation of B recirculation loop perturbations will be Inspector Followup Item 416/SS-17-01.
On July 31, 1988, at approximately 4:03 A.M. a control room operator observed recirculation pump A motor bearing oil level low alarm.
The alarm in the control room was followup by initiation of Maintenance Work-Order (WO) IS3459 to troubleshoot, verify and add oil. I&C verified that the alarm was valid. Thrust hearing upper and lower temperatures were monitored on panel P6SO trend recorders for temperature.
The upper bearing temperature averaged 112" F and 160* F on the lower bearing.
Standing Order SS-0005 was written to provicie additional requirements for continued operation of the recirculation pump with a lube oil low level annuciator.
Standing Order 88-0005 directed operators to secure the affected recirculation pump if at any time a bearing temperature increases to 190' F.
Temperatures of pump A motor bearing and cooling water are recorded shiftly. Further evaluation will be made during shutdown by the licensee.
This item will be followup as Inspector Followup Item
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416/88-17-02.
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On August 15,19S8 while at 100's reactor power the reactor scrammed at
approximately 3:52 p.m. due to ApRM C,0,G and H tripped on a high neutron
flux indication. Approximately 3-4 seconds prior to the scrim signal, the GETARs system indicated a voltage spike on the 500 KV systea. At the time
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of the scram several personnel onsite observed large ligh.ening strikes.
l The licensee concluded that the most probable cause of the trip was that
lightening struck plant structures or close by, causing at least 4 APRM upscale trips.
Incident Report SS-S-3 was written to document this
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incident.
Two previous events that occurred on July 12, 1932 and i
July 27, 1933, caused the reactor to scram due to lighteni.ig were j
documented in Incident Reports 82-7-10 and 83-3-100 respectively.
The i
PSRC reviewed the completed on shift post-trip analysis and outlined j
testing to be completed prior to restart. No unreviewed safety questions i
or equipment operability concerns were identified. At approximately 10:57 p.m. the plant had recovered and the mode select switch was placed in mode
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2. Criticality was achieved at 5:34 a.m. on August 16, 1988 on Group 7, l
Gang 2 rod position S.
The following actions were being taken by the licensee to prevent similar trips in the future:
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GE will poll other plants to determine if they have had similar occurrences, and if so what changes were made to prevent them.
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NPE-0AS will provide a report of this event to the industry through INP0s Nuclear Network,
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An Engineering study will be performed to determine the adequacy of the GCNS grounding system.
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9.
Action on Previous Inspection Findings (92701)
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(Closed)
Inspector Followup Item 416/86-32-02, System Operating Instruction (501) for Standby Service Water (SSW) has inappropriate action i
step.
The procedure 501-04-1-01-P41-1 prescribes the venting of the
siphon to ensure operability following a Icw level condition in the SSW (
basin.
In order to assure proper levels in the vent line, the licensee
has revised the procedure to inform the Shift Superintendent when levels are not as expected.
(Closed)
Inspector Followup Item 416/$7-26-02, Revise Surveillance
procedures to incorporate steps for placing Standby Service Water (SSW)
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Motor Operated Valves (MOV) in test mode.
The licensee revised i
Surveillance Procedure 06-0P-1P75-M-0001 and M-0002 for SDG 11 and SDG 12, i
respectively, to incorporate steps for placing SSW Division 1 and 2 MOVs
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in test position and returning the test switch back to normal when
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performing diesel surveillance.
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i (Closed) Inspector Followup Item 416/87-29-03, Analysis to determine if Silicone filled and Magnetrol/ Transmitters response times are acceptable.
This item relates to IE Notice 87-17. The inspector reviewed the analysis
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performed by the licensee which concluded that GGNS has adequate scram discharge volume available such that the response time of the transmitters I
does not present any concerns.
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f (Closed) Inspector Followup Item 416/87-10-03, Failure of nechanics to properly assemble a relief valve.
The licensee issued two Quality l
Deficiency Reports (QDRs) 144-87 and 145-87 to address the problems
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associated with the reassembly of safety valves and inadequate instruc-
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tions on M40s.
The inspector reviewed the documentation on QDR 144-87 I
which identified a weakness in the journeyman in dealing with relief /
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safety valve typed / selection and general maintenance.
The training
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l department established appropriate lesson olans to address this area. The l
inspector reviewed the documentation on ODR 145-87 which identified the
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deficiencies of certain M40s not providing specific details in the work t
packages.
Interim controls IPC S7/0977 were established and final
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disposition was accomplished by retraining the maintenance planning I
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personnel on the importance of detail work instructions as delivered per l
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procedure 07-5-01-205.
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(Closed) Inspector Followup Item 416/87-10-07.
The licensee modified Surveillance Procedures 06-0P-1P75-M-0001, Standby Diesel Generator (SDG)
l 11 Functional Test, and 06-0P-1P75-M-0002, Standby Diesel Generator (SDG)
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12 Fonctional Test, to modify the method to reduce starting air pressure p
in the isolated air start lines.
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(Closed) Inspector Followup Item 416/87-28-03.
The licensee's off-shiit
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analysis of scram number 45 also identified some of the discrepancies
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I noted by the inspector. Procedure 01-5-06-26 was revised to include the f
l parameters computer point number and description to prevent any misunderstanding by review personnel. Also, definitions of Cause and Root
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Cause have been included with the Cause being determined during the on
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shift analysis and the Root Cause being determired during the off shif t
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(Closed) Inspector Followup Item 416/88-03-02.
The licensee issued Maintenance Work Order M6335 to install Hilti bolts to secure the cover on the forced balance strong motion accelerometer (SCS5-N004).
10.
Exit Interview (30703)
The inspection scope and findings were summari:ed on August 19, 1930, with those persons indicated in paragraph I above.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection, The licensee had no comment on the following inspection findings:
50-416/38-17-01, Inspector Followup Item, Investigation of B Recirculation Lo'op Perturbation.
50-416/83-17-02, Inspector Followup Item, Investigation of Recirculation Pump A Motor Bearing 011 Level Low Alarm.
Licensee management was informed that the seven IFI's discussed in paragraph 9 and two LERs in paragraph 7 were considered closed.
11. Acronyms and Initialisms Automatic Depressuri:ation System ADS
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Average Power Range Monitor APRM
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GETARS - General Electric Transient Analysis Recording System Gallon Per Minute GPM
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Grand Gulf Nuclear Station GGNS
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Hydraulic Power Unit HPV
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Instrumentation and Control I&C
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Inspector Followup Item IFI
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Institute of Nuclear Power Organi:ation INPO
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Internal Plant Correspondence IPC
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Kilovolt KV
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Limiting Condition of Operation LCO
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Motor Operated Valve MOV
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Main Steam Isolation Valve MSIV
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Main Safety Relief Valve MSRV
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Mega Watt MW
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Maintenance Work Order MWO
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Nuclear Plant Engineering NPE
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Operation Analysis Section OAS
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Plant Safety Review Committee PSRC
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Quality Deficiency Report QDR
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Standby Diesel Generator SDG
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Standby Service Water SSW
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Technical Specification TS
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