IR 05000416/1990012
| ML20058M424 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/25/1990 |
| From: | Cantrell F, Chrisrensen H, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058M421 | List: |
| References | |
| 50-416-90-12, NUDOCS 9008100113 | |
| Download: ML20058M424 (9) | |
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'o NUCLEAR REGULATORY COMMISSION
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REGION il
-y 101 MARIETTA STHEET, N.W.
- ATL ANT A, G EORGI A 30323
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'E Rep *o*rYNo. : 50-416/90-12
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Licensee:-
Entergy Operations, Inc.
Jackson, MS 39205 Docket No.:
50-416 License No.:
NPF-29 Facility Name:
Grand Gulf Nuclear Station Inspection-Conducted: June 16 through July 20, 1990
' j Inspectors:
&A 7-25-90
. O. Christensen, Senior Resident Inspector Date Signed f&
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~7 - 2 5 - 90
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. L. Mathis, Resident Inspector Date Signed l
Approved by:
4-M[.h-
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F 5. Cantrell, Section 9Mief Date Signed Reactor Projects Branch1
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Division of Reactor Projects
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l SUMMARY i
Scope:
n The resident inspectors conducted a routinc ;aspection in the following areas:
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operational safety verification, maintenanc, observation, surveillance observa-tien, licensee-self-assessment capability, action on previous inspection findings, installation and testing of modifications, and reportable occurrences.
-The inspectors conducted backshift inspections on June 27, 29, July 8, and 10,
1990.
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Results.
During this inspection period no violations or deviations were identified.
One I
unresolved item was identified concerning the vital area requirements for the
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. control building area, paragraph 3.
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.The engineering staff continues to demonstrate thoroughness in their review of design issues.
An example'is the identification of the high pressure core ci:
spray room cooler. minimum flow condition, paragraph 3.
The Safety Review
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Committee performs its intended function and has open and informative
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Jiscussions on plant probiams and trends.
The licensee met safety objectives s
in. the areas of maintenance observation, surveillance observation, and installation and testing of modifications.
I During the last -three months a negative trend was noted in " attention to detail", NRC Inspection Reports 90-08 and 90-11.
Senior plant management it aware of this trend and is taking positive steps to reverse the trend.
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9000100113 900725 PDR ADOCK 05000416 Q
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i REPORT DETAILS
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Persons Contacted e
Licensee Employees
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J. G.-Cesare, Director, Nuclear Licensing
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W. T. Cottle, Vice President, Nuclear Operations D. G. Cupstid, Manager, Plant' Projects-
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- L. F. Daughtery, Compliance Supervisor i
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- M. A. Dietrich, Director, Quality Programs J. P. Dimmette, Manager, Plant Maintenance j
C. W. Elisaesser, Operations Superintendent
- C.LR. Hutchinson, GGNS General Manager
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F. K. Mangan, Director, Plant Projects and Support
- L. B. Moulder, Acting Manager, Plant Support
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U J. V. Parrish, Manager, Plant Operations.
J. C. Roberts, Manager, Plant & System Engineering
J. E. Reaves, Manager, Quality Services F. W. Titus, Director, Nuclear Plant Engineering (
G. W. Vining, Manager, Plant Modification and Construction
- G. Zinke, Superintendent, Plant Licensing Other licensee employees contacted included superintendents, sunervisors,
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technicians, operators, security force members. and office personnel.
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- Attended exit interview
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Plant' Status'
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The plant ' began and ended the inspection period in mode one, power operations, j
The General Panager conducted ' discussions with the plant staff on the developing trend of inattention to detail. -He stated that the trend appears to involve all departments and that experienced persons are making mistakes.
He stressed the importance of self-verification and the need for all personnel to ensure correct job performance.
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Operational Safety (71707, 93702)
i The inspectors were aware of the overall plant stant, and of any signi-
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ficant safety matters related to plant operations.
Daily discussions wers held with plant management and various members of the plant operating staff. The inspectors made frequent visits to the control room. Observa-tions included:
verification of instrument readings, setpoints and recordings; review of operating system status and tagging of equipment
- controls; verific e on of annunciator alarms, limiting conditions for
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operation, and temporary alterations; and review of daily journals, data sheet entries, control room manning, and access controls.
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g 0n a weekly basis, selected engineered safety feature (ESF) systems were.
- confirmed _ operable.
The inspectors verified that accessible valve flow L
path alignment was correct, power supply breaker and fuse status was a
correct' and instrumentation was operational.
The inspectors verified the following systems operable:
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The ' inspectors conducted-plant tours weekly Portions of the control
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building, turbine. building, auxiliary building and outside areas-were
visited.
The' observations included safety related tagout verifications,
shift turnovers, sampling programs, housekeeping and general plant
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conditions.
Additionally,'the inspectors observed _the status of fire q
protection equipment, the control of activities -in progress, the problem
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identification systems, and the readiness of the onsite emergency response
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facilities.
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I The inspectors observed health physics managements involvement and awareness of: significant plant activities, and observed plant radiation controls.- Periodically the inspectors verified the adequacy of physical l
security control.
Additionally, senior plant _ management was observed
making routine tours of the plant.
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The inspectors reviewed safety related tagouts 900890.(TIP machines) and 901051 [Drywell chiller flow reversing valve) to ensure that the tagouts
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ware properly prepared, and performed.
Additionally, the inspectors
verified _ that the tagged components were in: the required position, I
The inspectors reviewed the activities associated with the events listed below.
During the recent rebuilding of Hydraulic Control Units (HCus) 36-45 and
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-36-21, the scram pilot valves were rebuilt under work request 12711 and
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12712,.respectively.
Following the rebuilding, the-post _m m tenance test l
revealed that the valves' leaked.. Further investigation revealed that I
the-refurbish kits used on the leaking pilot scram solenoid valves i
consisted of a red urethane rubber disc and not the required Viton A
-disc.
A subsequent investigation by quality programs of over 400 kits in._ the warehouse found five more kits with red urethane rubber discs.
l These kits were removed from stock and destroyed. QDR 90-126 was written I
' to determir.e why the urethane kits were not removed from stock originally.
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The licensee has verified that all scram pilot solenoid valves in the
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plant have the correct material.
On July 3,1990, the Board of Alderman of the city of Port Gibson,.
f Mississippi, passed a resolution stating that the city would be able to l
provide adequate protection to its citizens in the event of a radiological h
emergency.
Additionally, the board rescinded a May 7,1990, resolution
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l-its citizens.
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On July 6,1990,. the licensee determined that the HPCS room cooler may
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not provide adequate long term room. cooling for the HPCS pump.- During a
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review of HPCS calculations, the licensee discovered that the 22 gallon per minute SSW flow to the room cooler would result in a room temperature of 163 degrees-F. The equipment is qualified to: operate in a 150 degrees F environment.
The increased temperature would allow the HPCS pump to operate for approximately 80 days, which is less the 100 day long term cooling requirement.
The licensee stated the condition is bounded by a new LOCA analysis, documented in LER 90-003, which demonstrates that the
ECCS criteria are met assuming no credit for: spray cooling after the
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initial 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> of_HPCS operations.
The licensee is preparing a design modification to address the-HPCS SSW issues.
This modification will be installed during refueling outage 4 scheduled for October 1990. The long tem resolution of this issue will be by followup on the LER.
On July 17, 1990,- during a tour of the control building the inspector
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noted' a door to an area propped open without a security officer being-
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stationed.
.Further investigation by the inspector determined that the H
area may contain vital equipment but was not considered a vital area.
'The licensee secured the area and-is reviewing the security requirements
for the room.
The status of the equipment in the unsecured' area will be-
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an unresolved item pending a complete review of security requirements by j
the licensee and subsequent review by Region II security-inspectors
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(90-12-01).
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No violations or deviations were identif ad.
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'4 Maintenance'0bservation(62703)
During-the. report period
- he inspectors observed portions of ' the s
maintenance activities listed below.
The observations included a review-l of the MW0s: and other related documents : for. adequacy;. adherence to j
l procedures, proper tagouts, technical specifications, quality controls, i
L and radiological controls; observation of work and/or retesting; and specified retest requirements.
MWO DESCRIPTION q
03655 Replace 1E3. battery bank.
13608 E12F074A MOVATS testing.
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14169 Install temporary inlet and outlet piping to drywell chillers.
14194 Temporary pipe tie-in to support P44F925 removal.
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14206 Rebuilt starting air after cooler B0130 outlet relief valve.
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14945 Furmanite SA feedwater manway diaphragm.
No violations or deviations were identified. The results of the inspection in this area indicate ~ that the maintenance program was effective.
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observed activities were conducted in a satisfactory manner and the work was properly performed in accordance with approved maintenance work orders.
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Surveillance Observation (61726)
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The' inspectors observed-the performance of portions of the surveillances
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listed below.
The observation included a review of the procedures for technical adequacy, conformance to technical specifications and LCOs; verification of test instrument calibration; observation of _ all or part
of the actual surveillances; removal and return to service of the system or component; and review of the data for acceptability based upon the
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acceptance criteria.
04-1-03-T46-2-B ESF Switchgear Room Cooler Flow Test.
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'06-1C-1821-M-2004 Reactor Vessel Water Level (PCIS) Level 2 i
and 1 Functional Test. Channel B.
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06-0P-1C41-M-0001 Standby Liquid Control Operability, Pump B.
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0'6-0P-1E51-Q-0003 RCIC System Quarterly Pump Operability a
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Verification.
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i-L 06-0P-IP75-M-0001 Standby Diesel Generator II Functional-Test.
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No violations or deviations were identified. The surveillance tests were
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performed in a satisfactory mar.ner and met the requirements of TS.
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Licensee Self-Assessment Capability (40500)
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The inspector reviewed selected Safety Review Committee (SRC) meeting minutes and observed the July-10,1990 quarterly meeting.
The SRC is
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the. TS required offsite review committee.
Technical Specification u.
6.5.2.2 states, the SRC shall be composed of a chairman and nine voting
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Two or more additional voting members shall be consultants.
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Tne SRC had 11 primary members, two were consultants. Additionally, nine
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alternate members were assigned.
One additional primary member was required, the Manager, Nuclear Training was appointed.
A review of resumes of selected primary and alternate memb?rs indicated that they met the qualifications requirement of TS.
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A review of the past two quarters of meeting minutes and'the observation of the July meetinj indicate that required review items were covered.
T'ie meeting discussion was open' and informative.
Plant problems and trends were discussed and SRC members asked - probing questions.
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consultant members appear beneficial to the SRC, they brought a fresh
prospective to the issues reviewed.
Events;at other nuclear facilities i
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were also discussed.
The SRC has an adequate tracking mechanism for committee open: items and-the items are pursued at each meeting. The SRC appears to be fulfilling its intended function.
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Installation and Testing of Modifications (37828)
The inspectors examined ~ selected modifications to verify that work was
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performed by qualified workers and according to approved instructions, procedures and drawings.?
Additionally, the inspector reviewed the post-modification testing to ensure that tests adequately addressed the
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modification and~ established appropriate acceptance criteria.
The licensee noted that four-way valve P44F925, PSW flow reversal valve t
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to the drywell chillers, was obstructing' PSW chiller flow.
A teeporary s
PSW modification was installed to bypass the four-way-valve and allow for the this valves removal.
Minor Change Package-(MCP) 90-1073 was implemented to-remove -the valve and replace.it with a flanged branch line,-
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.The MCP was performed 'in accordance with. the modification work permit.
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All: required reviews and approvals were obtained. The inspectors verified
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that qualified welders performed the work and that the correct welding material was used.. Upon completion of the work a system leak test was successfully performed.
Following installation of the temporary bypass
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to the four-way valve and MPC 90-1073, Containment temperature dacreased
2 to 3 degrees F indicating the diagnosis of'the problem was correct.
l 8.
Reportable Occurrences (90712 & 92700)
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h The-event reports listed below were reviewed to determine if the informa-L tion provided met the NRC < reporting requirements.
The determination included adequacy of event description, the corrective action taken or planned, the existence of -potential generic problems and the relative safety significance of each event. The inspectors used the NRC enforcement-guidance to determine if the event met the criteria for licensee identified violations.
On. July 18,1990, the licensee made a 10 CFR 26.73 report on a confirmed l
positive drug test.
The individual was a licensed reactor operator.
After being interviewed by the site medical review officer and plant management, the individuals site access was pulled and his employment terminated.
The licensee is reviewing recent assignments for this individual for any abnormal problem i x;,
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(Closed)'LER 89'-07, RWCU Isolation Due to Flow Perturbations.
On May 8, J1989, the RWCU system.: isolated. on a leak detection differential ' flow signal.
This event was documented in NRC Inspection Report 89-14.
The licensee revised' the integrated operating instruction to change the
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f required shifting point for the pre-pump to post-pump modes of operations.
Additionally, the system operating instruction was revised to modify the
. blowdown lineup.
These procedure revisions appear to have. prevented RWCU
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isol ations.- This item is closed.
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.(Closed)' LER 89-12, Reactor Scram Due to Condenser Joint Failure.
This event was documented in. NRC Inspection Report 89-19.
The licensee
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completed the following _ corrective actions:
the expansion joints on all
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three condensers were replaced; control rod 32-25 was stroked, timed and friction tested with no. abnormal results; the control rods hydraulic
control unit and scram pilot valve was replaced; and the air throttle-valve to the scram discharge. volume was. lock wired open.
This item is-
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closed, j
(Closed) LER 89-13, MSIV Failed to Close Due to Extruded Elastomer Seat Material.
This event was documented in NRC Inspection Report 89-'19.
The' licensee replaced or-refurbished all eight MSIV dual solenoid valves
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prior to' plant restart following the scram on August 14, 1989.-
The licensee has scheduled'the rebuild of the solenoid valves during refueling outage four. This item is closed.
(Closed) LER 90-09, LPCS Pump Start Due to Personnel Error, This event was documented in NRC Inspection Report 90-11, paragraph 3.
A non-cited
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violation was issued (90-11-02)- and corrective actions have-been com-
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pleted. This item is closed.
(Closed) LER 90-07, Failure to Comply wit' ' Technical Specifications Due h
to Personnel Error.
On May' 16,1990, 'an Operations Shift Supervisor determined that-the actions taken by the previous:shif t. for an inopera-blei reactor' water level transmitter were not adequate 'to comply with the
requirements of TS.
This event was documented in Inspection Report 90-08.
q The corrective actions will be-tracked' under violation response 90-08-03.
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.i (0 pen) LER 90-08, Fire Doors not Surveilled.Due to Inadequate. Procedure.
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-This issue was documented in NRC Inspection Report 90-11, paragraph 7.
This LER will be closed after the licensee completes a fire door review.
-i owhich is scheduled to be completed by July 31, 1990.
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Action on Previous Inspection Findings (92701, 92702)
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(Closed) P21-89-16, KSV Standby Diesel / Generator Crankcase Explosion.
This 10. CFR 21 report is not applicable to Grand Gulf.
The plant has DSRV-16-4 diesels.
This item is closed.
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(Closed)l P21-89-20,, Potential. Interference Between the Connector Push Rod.and End Socket of the Rocker Arm for the Standby Diesel Generators.
This: problem is for replacement parts only.
Tue plant determined that two' intake rocker arms were in stock that did not meet the acceptance l
criteria noted'in the.10 CFR 21-report.
The licensee issued a Deficient
- Material 1 Report (DMR).to correct the interference problems. This item is cl osed ~.
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- (Closed) P21-90-04, Premature Long Term Degradation of Rosemount Model l
'710 Trip / Calibration Units and 414 E/F Resistance Bridpas.- The licensee
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determined that two potentially defective 710 units were 'in stock as dedicated spares for Rosemount Model 510 trip units.
A.DMR was issued and the units were removed from stock.
The plant does not have 414 E/F
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resistance bridge units.
This item is closed.
q (Closed) - TMI Item II.B.3, Post-accident Sampling Capability.
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licensee has a PASS system-installed and procedures on how to operate the-system and take samples.
Additionally, the licensee. takes routine samples _ from the system to demonstrate system operability and to train-
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. chemistry personnel.- The PASS system is capable of taking samples from seven locations.
In NRC letter dated February 19,1986, the~NRC staff concluded that the design cf the post-accident sampling system met all.the
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requirements of item II.B.3.
This item is closed.
(Closed) TMI Item II.B.4.2.A, Training for Mitigating Core Damage.
Training has been conducted for mitigatingicore damage.
This item is-
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(Closed). TMI Item III.D.3.4.3, Control room habitability-implement.
modifications.
The licensee must assure that control room operators
will_.- be adequately protected against the effects of. radioactive gases
.and that the plant can be safely operated or shut down 'under design basis
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accident conditions.
In Grand Gulf's Safety Evaluation. Report,
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Supplement 6, the NRC staff concluded that the control-room habitability
. system.is: adequate to provide safe, habitable conditions under both. normal and accident conditions. This item is closed.
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Exit' Interview (30703)-
l The inspection scope and findings were summarized on July 20, 1990, with
those persons indicated in paragraph 1 above.
The licensee did not 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
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Item Number Description and Reference j
.90-12-01 Inspector follow up item - Review the long' term-resolution to inadequate HPCS room cooling,
.i paragraph 3.
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90-12-02 Unresolved item - Resolve control building vital
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area issue, paragraph 3..
11. Acronyms and Initialisms
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BWR Boiling Water Reactor
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Control Rod Drive
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Design Change Package l
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Diesel-Generator DG:
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Emergency Core Cooling System a
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Engineering Safety Feature -
i Hydraulic Control Unit l
.HCU --
HPCS'
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Instrumentation and Control
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Inspector Followup Item
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Limiting Condition for. Operation LER-.-
-Licensee Event Report LOCA -
Loss of Coolant Accident LPCS -
Low Pressure Core Spray f
MNCR
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Material Nonconformance Report MSIV'-
, Main Steam Isolation Valve-MWO Maintenance Work Order
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Nuclear Plant Engineering NPE
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Nuclear Regulatory Commission NRC
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PASS -
Post = Accident Sampling System
'PSW Plant Service Water
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Quality ~ Deficiency Report RCIC --
Reactor Core = Isolation Cooling
.RHR Residual Heat. Removal
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RWCU -
Radiation Work Permit SBLC -
Standby Liquid Control S01 _ -
System Operating' Instruction-SPMU -
Suppression Pool Makeup System Standby Service Water SSW
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. Temporary Change Notice TCN
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Traversing Incore Probe TIP
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Technical Specification TS
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