IR 05000416/1989027
| ML19332D885 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/17/1989 |
| From: | Cantrell F, Christensen H, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19332D884 | List: |
| References | |
| 50-416-89-27, NUDOCS 8912050386 | |
| Download: ML19332D885 (8) | |
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UNITE 3 ST ATES NUCLEAQ RECULATCRY COMMisslON y
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101 MARIETTA STREET.N.W.
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Repart No.: 50-416/89-27 J
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Licensee:
. System Energy Resources, Inc.
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Jackson, MS 39205
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.Y. Docket No.: '50-416 License No.:
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Facility Name: GhandGulfNuclearStation
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Inspection Conducted: September 31 through October 20; 1989
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' Inspectors:
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pa-H. 0. Christensen, Senior Resident Inspector Date Signed
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%.;l.. Mathis, Resident Inspector Date Signed
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' Approved by:
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F. 5. Cantrell, Sect [9W Chief,
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Division of Reactor Projects.
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' SUMMARY,
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_ Scope:
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! The.' resident inspectors conducted a routine inspection in the following areas:
i operational safety verification, maintenance observation, surveillance i
- observation,' engineering safety features (ESF) system walkdown, and action on-previous inspection findings.
The inspectors conducted backshif t inspections
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on October 9, 1989.
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Results:
No'violationa'or deviations were identified during this inspection period, h,
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REPORT DETAILS
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1.
Persons Contacted
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Licensee Employees J. G. Cesare, Director, Nuclear Licensing
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W. T. Cottle, Vice President of Nuclear Operations
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M. L. Crawford, Manager, Nuclear Licensing D. G. Cupstid. Manager, Plant Modifications and Construction
- L. F. Daughtery, Compliance Supervisor L
- J. P. Dimmette, Managee, Plant Maintenance S. M. Feith, Director. Quality Programs
- C. R. Hutchinson, GGNS General Manager j
F. K. Mangan, Director, Plant Projects and Support
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R. H. McAnuity, Electrical Superintendent A. S. McCurdy Technical Asst., Plant Operations Manager
- L. B. Moulder, Operations Superintendent
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W. R. Patterson, Technical Asst., General Manager
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- J. C. Roberts Manager, Plant & System Engineering G. Smith, Superintendent, Chemistry
- S. F. Tanner, Manager Quality Services L. G. Temple Superintendent, I & C
T.- G. Tinney, Superintendent, Mechanical F. W. Titus. Director, Nuclear Plant Engineering
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- M. J. Wright Manager, Plant Support
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- J. W. Yelvert.on, Manager, Plant Operations G. Zinke, Superintendent, Plant Licensing Other licensee employees contacted included technicians, operators, security force members, and office personnel.
- Attended exit interview Commissioner K. Rogers and E. Merschoff, Deputy Director, Division Reactor Safety, toured the site on October 3,1989, and met with the resident
'ia.spectors and plant management.
2.
Plant Status The unit operated in Mode 1, power operations, throughout the inspection period.
3.
Operational Safety (71707)
I-The inspectors were cognizant of the overall plant status, and of any significant safety matters related to plant operations.
Daily discussions were held with plant management and various members of the plant operating staff. The inspectors made frequent visits to the control room.
Observa-tions included the verification of instrument readings, setpoints and recordings, status of operating systems, tags and clearances on equipment
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l controls and switches, annunciator alarms, adherence to limiting i
conditions for operation, temporary alterations in effect, daily journals and data sheet entries, control room manning, and access controls.
This p,
'l inspection activity included numerous informal discussions with operators
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and their supervisors.
On a weekly basis selected engineered safety feature (ESF) systems were confirmed operable.
The confirmttian was made by verifying that
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k accessible valve flow path alignment was correct, power supply breaker and
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fuse status was correct and. instrumentation was operational.
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following systems were verified operable:
RCIC, HPCS, SPMU, and CRD system.
General plant. tours were conducted on a weekly basis. Portions of the control building, turbine building, auxiliary building and outside areas were visited.
The observations included safety related tagout verifica-tions, shift turnovers, sampling programs, housekeeping and general plant conditions, the status of fire protection equipment, control of activities in progress, problem identification systems, and containment isolation and the readiness of the onsite emergency response facilities.
The inspectors observed health physics management involvement and awareness of significant plant activities, and observed plant radiation controls.
Periodically the inspectors verified the adequacy of physical security control.
The inspectors reviewed the following tagouts,
"B" Service air compressor (893684); HPU "B" subloop 2 fan motor (893675); Domestic water supply to clean lab valve (893554), to ensure that the tagouts were properly prepared, and performed.
Additionally, the inspectors verified that the tagged components were in the required position.
The inspectors verified that the following containment isolation valves were in the required position:
RCIC Turbine Exhaust E51F077A Aux. Bldg. F1r & Equip DRN TKS to Supp Pool P45F274B RHR Heat Exchanger "A" to LPCI E12F027AA RHR Heat Exchanger "B" to LPCI E12F042BB Reactor Recire. Post Accident Sampling B33F127A Reactor Recire. Accident Sampling B33F125A Containment Hydrogen Analyzer Sample Return E61F5988 Drywell Hydrogen Analyzer Sample Return E61F597B Supp. Pool Level E30F592AA RHR Shutdown Suction Relief Valve Discharge E12F005 Component Cooling Water Return P4?F067A The -inspectors noted that senior plant management makes routine tours to the plant and the control room.
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The inspectors reviewed the activities associated with the event listed
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On September 1,1989, the recirculation flow control valve ' A' moved in the closed direction without operator action.
.The licensee began troubleshooting the Foxboro circuits and installed a six-pen recorder to monitor future events.
On September 8,1989, a temporary alteration was installed to. provide _a '11 miter on valve opening via the position demand
signal.
After extensive troubleshooting and several valve movement i
events, the licencee located a problem in the power distribution module.
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.This module was replaced on October 12, 1989.
Additionally, FCV ' A'
i subloop 2 exhibited servo error problems, the licensee is troubleshooting.
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The inspectors will continue to monitor the licensee's progress in resolving FCV problems.
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No violations or deviations were identified.
4.
Maintenance Observation (62703)
During the report period, the inspectors observed portions of the maintenance activities. listed below.
The observations included a review-i of.the MW0s and other related documents for adequacy; adherence to
procedure, proper-tagouts, technical specifications, quality controls, and radiological controls; observation of work and/or retesting; and specified j
retest requirements.
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'MWO-DESCRIPTION j
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IN3018 Calibrate engine A/B jacket water i
outlet temperature high.
IN3025 Calibrate engine B jacket water heater controller.
IN5846 Calibrate engine B fuel oil pressure low switch (N003B).
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IN6025 Calibrate temperature indicator (T1-R004B) for engine 8 jacket water
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outlet temperature.
IN7953 Calibrate condensate booster pump G axial vibration.
IN9590 Calibrate (NO33B) pressure switch.
ME1018 Inspect HPCS Listor SR diesel engine.
ME2195 Take oil sample - HPCS motor driven start air compressor.
No-violations or deviations were identifie m(
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. Surveillance Observation (61726)
The inspectors observed the performance of portions of the surveillances listed below.
The observation-included a review of the procedure for
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technica1 ' adequacy, conformance to technical specifications and LCOs;
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. verification of test instrument calibration; observation of all or part of
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the' actual surveillances; removal and return to service of the system or
- component;; and review of the data for acceptability based upon the acceptance criteria.
t 06-RE-1C51-0-0001, Local Power Range Monitor Calibration, Attachment I.
~06-0P-1P81-M-0002, HPCS Diesel Generator 13 Functional Test.
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06-IC-1821-M-1012, ATWS-Reactor Vessel Level / Reactor Pressure Functional Test.
06-IC-1E31-M-0022, Drywell Air Cooler Condensate Flow Rate Monitoring Functional Test.
06-RE-1J11-V-0001,' Power Distribution Limits Verification.
No violations or deviations were identified.
6.
Engineered Safety Features System Walkdown (71710)
The inspectors conducted a complete walkdown on the accessible portions of the main steam isolation valve leakage control system and the feedwater leakage control system.
The walkdown consisted of the following:
confirm that the system lineup procedure matches the plant drawing and the as-built configuration; identify equipment condition and items that might degrade. plant performance; verify that valves in the flow path are in correct positions as required by procedure and that local and remote position indications are functional; verify the proper breaker position at local electrical boards and indications on control boards; and verify
'that' instrument calibration dates are current.
The inspectors walked down the system using system operating instructions 04-1-01-E32-1, N'SIV Leakage Control System and 04-1-01-E38-1, Feedwater Leakage Control System.
Piping and instrument diagrams (P&ID) M-1097 and M-1112 were used in the walkdown.
The' fo11owing minor discrepancies were noted during the walkdown:
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1.
' Electrical lineup checksheet in 501 04-1-01-E32-1 Revision 19 (Attachment III) indicates that breaker 52-1P52117 is located on panel 1H13-P655.
This breaker is actually located on panel 1H13-P654.
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-The automatic-timer did not' include the timer description labels on
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.the. panels. (i.e. Dilution Air Flow Alarm Bypass).
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The-configuration in the plant for a 4 ~ inch line (HBD-169) is not i
reflected correctly on P&ID (M-1097), Revision 15.
Correction.of the walkdown discrepancies will be tracked as IFI 89-27-01.
No violations or. deviations. were identified.
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( Action on Previous Inspection Findings (92701,92702)
(Closed)IFI 89-12-02, Correct ADHRS walkdown items.
All items identified in the walkdown were corrected with the exception of-painting: the system.
A MWO was written to track the completion of the painting. This item is closed.
(Closed) Violation 88-03-01, Failure to follow procedure, which resulted in the auto-start of a RHR pump and the failure to document work accomp-lished for ir. stalling of a nitrogen blanket on the offgas system.
The licensee admitted the violation in a letter dated May 5,1988.
The corrective action. listed in the above letter have been completed.
This
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.(Closed)1P2188-08, Defective intercooler inlet' adapter provided as part of IMO Delaval standby diesel engine generator. The licensee discovered this condition September 15, 1988.
Both diesel generator intercoolers were replaced and the inlet adapters repaired. This item is closed.
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(Closed) P2187-01, False RPS trip signal caused by BBC Brown Boveri 27N undervoltage relays.
Four-27N relays were installed on the HPCS diesel generator second level undervoltage protection scheme.
The relays were replaced under MW0's E94578, E85243. E90830 and E90841.
This item is
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(Closed)P2188-04, Reinstalling Foxboro contro1 ice circuit cards may cause
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- 100% output and. subsequent transient to occur, th13 controller has-been identified in BWR recirculation flow control system.
To preclude a similar problem, the card removal and insertion of recirculation flow controller is done with the controller in maintenance mode. Additionally the recirculation flow control system is operated in loop manual mode only. This item is closed.
(Closed)- P2188-09, Xomox assembled limitorque actuators with H0BC, H1BC, H2BC, H4BC and HSBC gear boxes on plug and butterfly valves may become disengaged and render the valve inoperable.
The licensee does not have any Xomox valve in use in safety related systems. This item is closed.
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E (Closed)P2189-01, Brown Boveri'K-line, K-225 thru K-2000 circuit breakers.
delivered prior to'1974 need rebound springs added to slow close lever.
The K-line circuit breakert, utilized by the licensee were all manufactured after the time frame of concern.
This item is closed.
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(Closed). Unresolved' Item 86-29-01, Pump and valve testing criteria.
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inspector's concerns with regard to the -licensee's inservice testing described in -(a) through (d) of inspection report unresolved item 416/86-29-01 was reviewed for closeout.
Item (b) of the above unresolved item concerns not testing RHR valves as part of the IST program.
The licensee deleted valves Q1E12-F094, F096 and F098 since these valves do not perform _a safety function.
These valves are part of the containment flooding portion-of RHR.
Therefore these valves are not required to be i
tested in accordance with the IST program.
Item (c) of unresolved item 86-29-01 concerned whether the licensee had implemented procedures to verify proper functioning of valve position indicators on their remote shutdown - panel.
Procedures 06-0P-1C61-R-0002 and 06-0P-1E51-R-0005 are
'used by the licensee to stroke each valve at the remote shutdown panel and
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check the remote indication of valve movement.
Item (d) of unresolved item 88-29-01 concerns exercising of testable check valves as required by ASME Section XI, IWV-3522.
Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, was received by the licensee and an extension request to the Generic letter was submitted on October 3,1989.
-This' letter response will be evaluated at a future time.
Part (d) will be administratively closed.
(Closed)'IFI 87-06-02, Testable Check Valves. The inspector was satisfied that the licensee exercised the testable check valves to the full open position.
However the inspector determined that, while his original concern appeared'satisiied, he intended to perform a more detailed review
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of the functioning and testing of these valves in a subsequent inspection.
This -item will be closed administratively since Generic letter 89-04 requires a response on testing check valves.
The licensee respense will be evaluated at a later time,
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(Closed) Violation 89-04-05, Failure to perform a written safety evaluation prior to storage of ECODEX resin in containment. The licensee admitted the violation in a letter dated April 14, 1989.
The corrective
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This item is
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Exit Interview (30703)
L The inspection scope and findings were summarized on October 20, 1989, with those persons indicated in paragraph I above.
The licensee did not
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identify as proprietary any of the materials provided to or reviewed by
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the' inspectors during this inspection. The licensee'had no comment on the
.following inspection finding:
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Item Number Descriptian and Reference
'IFI 89-27-01 Correction of MSIV Leakage Control System Walkdown discrepancies, Paragraph 6.
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. Acronyms and Initialisms
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ADHRS-Alternate Decay Heat Removal System ADS Automatic Depressurization System
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APRM -
-Average Power Range Monitor
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ATWS -
Anticipated Transient Without Scram-Boiling Water Reactor BWR
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CRD-Control Rod Drive
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iDCP- --
Design Change Package
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DG Diesel Generator
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ECCS -
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ESF Engineering Safety Feature
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'FCV -
Flow Control Valve j
HPCS.-
High Pressure Core Spray HPU -
Hydraulic Power Unit j
I&C Instrumentation and Control
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IFI Inspector Followup' Item
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Inservice Test
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LC0i -
Limiting Condition for Operation
' LER ' -
Licensee Event Report
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LLRT >
Local Leak Rate Test LPCI--
. Low Pressure Core Injection LPCS -
Low Pressure Core Spray
'MNCR
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Material Nonconformance Report
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MSIV --
Main Steam Isolation Valve Maintenance Work Order l
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NPE~ -
Nuclear Plant Engineering
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NRC Nuclear Regulatory Commission l
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PDS. -
Pressure Differential Switch P&ID:-
Piping and Instrument Diagram Plant Service Water PSW
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.QDR Quality Deficiency Report
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RCIC -
Reactor Core Isolation Cooling RHR Residual Heat Removal
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Reactor Water Cleanup RWP Radiation Work Permit
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SBLC -
Standby Liquid Control SERI --
System Energy Resource Incorporation
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S0I System Operating Instruction
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SPMU -
Suppression Pool Makeup System
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-SRV Safety Relief Valve
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SSW Standby Service Water
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Temporary Change Notice TCN
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Technical Specification TS
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