IR 05000416/1988017

Insp Rept 50-416/88-17 on 880716-0819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Enforcement Matters,Maint & Surveillance Observations,Operational Safety Verification & ESF Sys

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: IR 05000416/1988017 ML20153F616
References
50-416-88-17, NUDOCS 8809070380
Download: ML20153F641 (8)

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UNITED STATES

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NUCLEAR HEGULATORY COMMISSION

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Report No.: 50-416/23-17 Licensea: System Energy Resources In 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, 19 'a n spectors: : C csu u -Vw g_2_{ohf_

E. C Butcher, Senio Resident Inspector ate Signed

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6ffY J. L Mathisi ident Inspector late signed Approved by: b > (Luu

. C. Da .ce,' Section Cnief, Oivision

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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 item Results: In the areas inspected, violations or deviations were not identifie 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 tinl BBTS885!8?88l$66

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REPORT DETAILS

Persons Contacted Licensee Employees J. G. Cesare Director Nuclear Licensing L 0. G. Cupstid, Superintendent, Technical Support  :

• L. F. Daughtery. Compliance Supervisor ,

J. P. Dimmette, Manager, Plant Maintenance  !

S. M. Feith, Director, Quality Programs C. R. Hutchinse , GGNS General Manager R. H. McAnultv, Electrical Superintendent "

A. S. McCurdy, Technical Asst., Plant Operations Manager

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L. B. Moulder, Operations Superintendent  !

J. H. Mueller, Mechanical Superintendent J. V. Parrish, Chemistry / Radiation Control Superintendent J. L. Robertson, Superintendent, Plant Licensing t 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 personne ]

• Attended exit interview  ;

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. Acronyms and initialisms used throughout this report are listed in the l last paragrap !

I Licensee Action on Previous Enforcement Matters (92702) l Not inspectcd this report perio . Operational Safety, Radiological Protection and Physical Security i Verification (71707, 71709 and 71831) l

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The inspectors kept themselves informed on a daily basis of the overall !

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 staf L

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The inspecters made frequent visits to the control room such that is was !

visited at least daily when an inspector was on site. Observations  !

included instrument readings, setpoints and recordings, status of  !

, operating systems, tags and clearances on equipment controls and switches, j

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annunciator alarms, adherence .to limiting conditions for operation, temporary alterations in effect, daily journals and data sheet entries, ,

control room manning, and access controls. This inspection activity j included numerous informal discussions with operators and their l supervisor Weekly, when the inspectors were onsite, selected Engineered . Safety Feature (ESF) systems were confirmed operabl Tiie confirmation is made by verifying the following: Accessible valve flow path alignment, power ,

supply breaker and fuse status, major component leakage, lubrication, ;

cooling and general condition, and instrumentatio t

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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 visite Observations included safety related tagout ;

verifications, shif t turnover, sampling program, housekeeping and general ,

plant conditions, fire protection equipment, control of activities in I progress, problem identification systems, and containment isolation. The [

licensee's onsite emergency response facilities were toured to determine i facility readines :

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The inspectors reviewed at least one Radiation Vork Permit (RWP), observed :

health physics management involvement and awareness of significant plant !

. activities, and observed plant radiation controls. The inspectors verified (

licensee compliance with physical security manning and access control i requirement Period dally the inspectors verified the adequacy of physical security detection and assessment aid ;

i No violations or deviations were identifte (

f 4. 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 '

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 control l l

NO MS25S2 Retorque Starting Air Valve Capscrew for Division 2 Diesel i Generato WO M33316 Charge with Nitrogen Standby liquid Control Pulsation Camper WO M31963 Inspect Flange Holes; Remc.e Cut-of f Stud and Refurbish MSRVs as Required for Shipment to Wylie Li.borator Vd0 M33347 Rework SLC Test Connection Valve PPN40 No violations or deviations were identifie _ _ _ _ - _ - . _ - - _ - - - _ - - - - _ - - _ - - - - - - - - _ - - - - - - - - - - - - _ _ - - - - - -

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3 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 criteri P-1P75-M-0001, Revision 34, Standby Diesel Generator (SDG) 11 Functional Tes IC-1E12-M-0001, Revi sion 23, LPCI System C Discharge Line High/ Low Pressure Functional Tes EL-1821-M-0002, Revision 27, ADS Timers Functional Test and Cali-bratio P-1PS1-M-0002 Revision 31 HPCS Diesel Generator 13 Functional Test and Calibratio EL-1E12-M-0002, Revision 25, Containment Spray Time Delay Rela P-1821-V-0001, Revision 24, MSI'l Operability Tes IC-1821-M-1005, Revision 23, Main Steam Line Low Pressure Channel B Functional Tes No violations or deviations were identifie . 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 condison No violations or deviations were identifie . 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 '

guidance of the general policy and procedure for NRC enforcement actions, [

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regarding licensee identified violation ;

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The following License Event Reports (LERs) are close l

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LER N Event Date , Event

'S7-016 October 1, 1937 Area Radiation Survey Exceeced t LCO Time Limi l f

• S7-013 December 14, 1987 Late Surveillance During Core f Alteration :

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8. Operating Reactor Events (93702) i'

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The inspectors reviewed activities associated with the below listed {

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reactor event The review included cetermination of cause, safety

significance, performance of. personnel and systems, and corrective action, r

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The inspectors examined instrument recordings, computer printouts, .

operations journal entries, scram reports and had discussions with (

operations, maintenance and engineering support personnel as appropriat 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: 7

! in reactor vessel water level, feedwater flow and steam flew, Core ,

thermal power deceeased from 3831 Pd at 4:17 a.m., to 3706 K4 at  !

4:20 a.m., and roturned to 3331 Kd at 4:25 a.m. The B loop recirculation  !

j flow dropped from 41,000 GPM and then returned. Incident Report 88-7-3 (

1 was written to docurrent this event. A Maintenance Work Order (KdO) S3422 1 was initiated to trouble shoot the B recirculation flow control syste !

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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 {

j 3333 F4 to 3S03 Rd. The perturbations were severe enough to cause the B -

1 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 pane No safety features or TS requirements were .

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

precautionary measure and is continuing to r onitor the HPU panel. On l 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

! 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-17-0 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 temperatur The upper

bearing temperature averaged 112" F and 160* F on the lower bearin 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

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licensee. This item will be followup as Inspector Followup Item 4 416/88-17-02.

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On August 15,19S8 while at 100's reactor power the reactor scrammed at

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52 p.m. due to ApRM C,0,G and H tripped on a high neutron 1 flux indication. Approximately 3-4 seconds prior to the scrim signal, the

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GETARs system indicated a voltage spike on the 500 KV systea. At the time

! 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

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upscale trip Incident Report SS-S-3 was written to document this inciden 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

! 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 t licensee to prevent similar trips in the future: 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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l NPE-0AS will provide a report of this event to the industry through

' INP0s Nuclear Network, i

{ An Engineering study will be performed to determine the adequacy of i the GCNS grounding syste No violations or deviations were identifie _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

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9. Action on Previous Inspection Findings (92701) ,

(Closed) Inspector Followup Item 416/86-32-02, System Operating Instruction (501) for Standby Service Water (SSW) has inappropriate action i ste 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 (

basi 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 expecte (Closed) Inspector Followup Item 416/$7-26-02, Revise Surveillance ;

procedures to incorporate steps for placing Standby Service Water (SSW) -

Motor Operated Valves (MOV) in test mod 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 !

! in test position and returning the test switch back to normal when ,

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performing diesel surveillanc I i

(Closed) Inspector Followup Item 416/87-29-03, Analysis to determine if Silicone filled and Magnetrol/ Transmitters response times are acceptabl This item relates to IE Notice 87-17. The inspector reviewed the analysis <

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 concern ,

f (Closed) Inspector Followup Item 416/87-10-03, Failure of nechanics to properly assemble a relief valv 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-

! tions on M40s. The inspector reviewed the documentation on QDR 144-87 I which identified a weakness in the journeyman in dealing with relief / l

! safety valve typed / selection and general maintenance. The training !

l department established appropriate lesson olans to address this area. The l inspector reviewed the documentation on ODR 145-87 which identified the ,

deficiencies of certain M40s not providing specific details in the work t package Interim controls IPC S7/0977 were established and final !

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disposition was accomplished by retraining the maintenance planning I

! personnel on the importance of detail work instructions as delivered per l

! procedure 07-5-01-20 l i

(Closed) Inspector Followup Item 416/87-10-0 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) [

12 Fonctional Test, to modify the method to reduce starting air pressure p in the isolated air start line ;

! (Closed) Inspector Followup Item 416/87-28-0 The licensee's off-shiit '

I analysis of scram number 45 also identified some of the discrepancies i

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I noted by the inspector. Procedure 01-5-06-26 was revised to include the parameters computer point number and description to prevent any f l 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).

1 Exit Interview (30703)

The inspection scope and findings were summari:ed on August 19, 1930, with those persons indicated in paragraph I abov 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 Perturbatio /83-17-02, Inspector Followup Item, Investigation of Recirculation Pump A Motor Bearing 011 Level Low Alar Licensee management was informed that the seven IFI's discussed in paragraph 9 and two LERs in paragraph 7 were considered close . Acronyms and Initialisms ADS -

Automatic Depressuri:ation System APRM -

Average Power Range Monitor GE -

General Electric GETARS - General Electric Transient Analysis Recording System GPM -

Gallon Per Minute GGNS -

Grand Gulf Nuclear Station HPCS -

High Pressure Core Spray HPV -

Hydraulic Power Unit I&C -

Instrumentation and Control IFI -

Inspector Followup Item INPO -

Institute of Nuclear Power Organi:ation IPC -

Internal Plant Correspondence KV -

Kilovolt LCO -

Limiting Condition of Operation MOV -

Motor Operated Valve MSIV -

Main Steam Isolation Valve MSRV -

Main Safety Relief Valve MW -

Mega Watt MWO -

Maintenance Work Order NPE -

Nuclear Plant Engineering OAS -

Operation Analysis Section PSRC -

Plant Safety Review Committee QDR -

Quality Deficiency Report SDG -

Standby Diesel Generator SLC -

Standby Liquid Control SSW -

Standby Service Water TS -

Technical Specification

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