IR 05000321/1987022
| ML20235V550 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/05/1987 |
| From: | Conlon T, Hunt M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235V529 | List: |
| References | |
| 50-321-87-22, 50-366-87-22, IEB-80-16, IEB-84-02, IEB-84-2, NUDOCS 8710150217 | |
| Download: ML20235V550 (10) | |
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- R800 UNITED STATES
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NUCLEAR REGULATORY CCMMISSION
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7g REGION 11 g.
j 101 MARIETTA STREET.,N.W.
- r ATLANTA, GEORGl A 30??3
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Report Nos.:
50-321/87-22 and 50-366/87-22 I
Licensee: Georgia Power Company I
P. O. Box 4545
Atlanta, GA 30302
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Docket Nos.:
50-321 and 50-066 License Nos.:
DPR-57 and NPF-5 Facility Name:
Hatch 1 and 2 Inspection Conducted: August 31 - September 4,1987 Inspector:
N
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/b ]/b M. O. Hunt-'~
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~Date 71gned Accompanying Personnel:
M. N. Millery Approved b
/FicFF W
/C ' I' Y [
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E. Conlbn, Chief Date Signed Plant Systems Section Division of Reactor Safety SUMMARY Scope:
This routine, announced inspection was in the areas of electrical maintenance, instrumentation maintenance, heat shrinkable tubing, inspector followup items and IE Bulletins.
Results:
One violation was identified.
Inadequate Acceptance Criteria for Pressure Switch 2E41-N752 Calibration
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T REPORT DETAILS-
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" Persons !Coritactec(
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Licensee Employeesh
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- G.I arber, I&C. Superintendent B
Fry
- K. Breitenbach; B0P. Engineering Supervisor
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- I.cBuchans, I&C Supervisor
'*E. M. Burkett,: Engineering Project Supervisor
'*R. Chandler, Planning and Control Superintendent
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- G.tCreightor, Regulatory Specialist
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- P. Fornel,'Manageriof. Maintenance
- A.1Fraser.-QA Site Manager-
- R,:Godby, Superi.ntendent of Maintenance j
.. R. Hayes -Deputy Manager of Operations
L*K. King, Site EQ Coordinator
- H. Mirzakhani, Senior. Plant Engineer
- H. Nix, Plant Manager
- J. Ponder, NSC Engineer
' *T. Powers, EngineeringLManager
- S Tipps,- NUC. Safety and Compliance Manager
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. Other. licensee employees contacted included construction craftsmen;
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engineers, technicians, operators, mechanics, security'ferce members, and office personnel.
NRC Resident Inspector
- P. Holmes-Ray.
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- Attended' exit interview
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' Exit' Interview The inspection scope 'and findings were summarized on' September 4,'1987,
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with' those ' persons ' indicated in paragraph 1 above.
The. inspestor
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described the areas inspected and discussed in detail the inspection
' findings.
No' dissenting comments were received from the' licensee.
The following new item was identified during this inspection:
S0-366/67-22-01, Inadequate Acceptance Criteria for Pressure. Switch
.l-2E41-N752 Calibration (paragraph 6).
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'The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
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3J Licensee Action on Previous Enforcement Matters
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'This1 subject was-not addressed in the inspections 4.-
- Unresolved; Items
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Un' resolved items were not identified during this inspection.
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Electrical Maintenance.(Components and Systems) OM,ervation of Work, Work.
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Activities, and Quality Records -(62705)
The E inspector ' observed Lthe performance of Surveillance Procedure i
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No. 52SV-R42-002-15, Battery. ~ Individual Cell Surve111ance-~for 125 VDC-
. Diesel.. Generator (D/G). Batteries, IR42-5002A, IR42-5002B and 1R42-5002C
' and the 24VDC Fire Pump Diesel Batteries 1R42-5018 and.1R42-5019..This procedure.is ' performed monthly to. meet Technical Specifications and Fire Protection Equipment Operating and Surveillance Requirements. The' proce-dure contained requirements for the use of calibrated test equipment
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'(fluke. meter).and the acceptance criter b for each battery / cell.
Instruc-
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i tions for temperature. compensation calculations of the specific gravity -
i readings and electrolyte minimum / maximum levels were defined in the i
L procedure.
The instructions for adding electrolyte and the requirements /
restrictions for placing either Station Service Battery A or B on equaliz-
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ing charge are well defined. The-equalizing charge' time requirements for lead antimony and lead calcium batteries are listed in this procedure.
- The'. procedure; required the documentation of observed defects, deficienc-ies, malfunctions... etc. in the comments section of-the test log sheet.
The. test results are reviewed by the responsible maintenance foreman and forwarded to the systems engineer for review.
The. individuals performing this surveillance were knowledgeable of the requirements for performing this task and displayed an interest in performing these tests in a safe operational and personnel manner.
During the ob'servation of these tests.. it was noted that a junction box
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containing terminations for test cables which monitor the individual cell voltages during battery discharge / load tests had been installed in each 'of the D/G and ' station service battery rooms.
The test cable from each junction box'was installed in~a temporary and exposed manner.
In.the D/G rooms, the test cables were attached by ty-raps to the wall mounted conduits and in the station service battery rooms the test cables were.
attached to HVAC duct supports by ty-raps.
The inspector questioned the licensee as to what evaluation <. had been performed which permitted these
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test cables. to be installed in the aanner observed.
The licensee presented a request for ensincerir.g evaluation for installing the test cable in; tray or conduit and the inspector was advised that an engineering
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ovaluation had been initiated.
The inspector was further advised that
.these test cables.would be removed from the conduits and stored under the junction boxes when not in use until such time as a more permanent installation can be made, k
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Numerous ' surveillance and maintenance procedures were reviewed and are discussed briefly as follows:
Maintenance Procedure No. 52CM-MME-016-0S, Limitorque Valve Operator
Type SMC-03 Mechanical Maintenance; 52CM-MME-010-0S, Limitorque
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Manual Unit Models H0BC through H7BC Mechanical Maintenance and, j
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52CM-MME-009-0S,. Limitorque Valve Operator Model SB-0 thru SB-4, Mechanical Maintenance identify supporting electrical procedures to be -used in conjunction with these procedures; identifies.QC hold points, required permits, clearances and retesting after reassembly.
These procedures contain full manufactures assembly diagrams, parts identification and instructions.
Additionally, the gear grease type required to meet the Equipment Qualification (EQ) requirements is specified.
Maintenance Procedure No. 52GM-MNT-016-0S, Limitorque Valve Operator Troubleshooting, contains a failure cause corrective action table for troubleshooting purposes.
Additionally, the return to service for diagnostic testing is controlled by procedure 30 AC-0PS-055-0, Temporary Bypass, Jumper and Lifted Lead Control.
Maintenance Procedure 52GM-HEL-022-05, Limitorque Valve Electrical Maintenance, contains all the previously mentioned applicable requirements for M0V's qualified and identified as meeting 10 CFR 50.49 requirements.
Maintenance Procedure Nos. 52CM-R22-001-05 4160 Volt AC Switchgear and Associated Electrical Component Maintenance and 52PM-R22-001-0S 4160 Volt AC Switchgear and Associated Electrical Component Preventative Maintenance identify the applicable 4160 volt switchgear, the cleaning materials, tools and test equipment required and identifies special requirements and precautions for the tasks described in the. procedurcs.
These procedures contain a troubleshooting chart.
It was noted that these procedures did not identify QC holdpoints or preparation of maintenance Work Orders (MW0).
Discussions with the licensee revealed that no safety-related switchgear is removed for maintenance without an MWO.
The MWO requires a QC signoff to indicate if hold points are required.
QC personnel advised the inspector that 'QC holdpoints are not usually required during the performance of each breaker preventative maintenance due to the large number involved.
Instead, periodic audits are performed to observe procedure compliance.
Maintenance Procedure No. 52 PM-MNT-005-0S Limitorque Valve Operator Inspection contains instructions for both 18 and 36 month inspections.
A table is included which identifies the 10 CFR 50.49 qualified MOVs. This procedure contains a caution note regarding the addition of grease to the limit switch gear boxes which states "when adding grease, it must be replaced with the type in the operator, either Beacon 325 or Mobil 28. DO NOT MIX the two types of grease."
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The inspector questioned the use of Beacon 325 grease in MOV's that
are listed' on the 10 CFR 50.49 Equipment Qualification (EQ) List..
I The licensee. advised that the Beacon 325 grease was no longer used at l
this plant.
However, the licensee advised that repair / replacement limit switchgear boxes 'in warehouse stock may contain the Beacon 325
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grease. The inspector noted that no written instructions existed for l
insuring that the grease is replaced in a replacement limit
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switchgear box taken from stock before it is installed. The licensee i
took inmediate action to revise this procedure to require the-replacement of the Beacon 325 grease in any unit removed for stock
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The inspector reviewed MW0 2-86-442 which was written for repair of Unit 2 HPCI M0V local' starter 2E41-F008.. The MW0 required replacement of damaged control wire lugs at the' local starter. QC holdpoints were identified as were the use of -QC materials and calibrated tools and test equipment.
It was not clear to the inspector that the work performed was that which was described by the work description in that the internal (manufacturers)
wiring was relugged when it seemed that the field cable was described as damaged.
The licensee stated that procedure 52GM-MEL-003-0S Cable and
Cableway Installation permitted work to be performed on either side of the l
tenninal block.
The licensee did write an additional explanation to clarify the actions' taken in this MW0.
The licensee is. in the process of upgrading plant procedures to insure that procedural instructions are clear, concise and meet the intent of the procedure.
Several proposed revisions were displayed to the inspector and appeared adequate.
Within the area examined, no violations or deviations were identified.
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Instrumentation Maintenance (Components and Systems) Observation of Work, Work ' Activities, Program Review, Procedure Review and Quality Review (62'/04)
The inspector reviewed Chapter 7 in the FSAR - Instrumentation and Control, and the Technical Specifications to determine the licensee's requirements and commitments for instrumentation maintenance activities.
Administrative Control Procedure 10AC-MGR-004-0S titled Deficiency Control
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System was reviewed to determine the requirements and the responsibilities for the identification and correction of deficiencies as related to I
l instrumentation maintenance.
Administrative Control Procedure 50AC-MNT-001-0S Maintenance Program was reviewed to determine the
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j requirements and responsibilities for controlling the instrumentation
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maintenance activities.
The Maintenance Program procedure includes the j
use of a Maintenance Work Order (MW0) which is used to initiate and i
control corrective maintenance.
The calibration program for instrumentation is controlled in the Maintenance Program except for the
calibration of instrumentation covered by Technical Specifications. This i
is covered in the Technical Specifications Surveillance Program addressed j
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- in1. procedure.40AC-REG-001-0.o Administrative ' Control Procedure.
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50AC-MNT-002-05,. Control of Measuring andL Test Equipment and General
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Maintenance Procedure 51GM-T0L-002-05, Control of I&C Measuring,and Test
~l Equipment ' were f reviewed to determine' if they meet the requirements l committed. to by the ;1icensee.. These procedures were found adequate 'for the : activities _they addressed within the areas examined.
- The inspector Jselected the following two categories of maintenance activities performed by the Instrumentation and Control Section' in the-Maintenance Department;for review:
Corrective maintenance using the Maintenance Work Order (MW0) and the-
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calibration l procedure specifie:1 in it.
Calibration of instrumentation covered in the Technical Specification
' Surveillance: Program.
The. inspector reviewed ' and observed the performance nf surveillance
- procedure 57SV-C71-006-1, RPT Initiation Logic F.T. & MG' Set Breaker Time Response Test = for 'the Reactor Protection System.
The' initiation logic j
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section is. performed ' monthly to meet Technical Specifications and was the section observed..The procedure clearly stated the purpose was to provide instructions 'forLperforming a trip initiation logic test for the RPT trip channe'Is as required by Technical Specification Table 4.2-9(3.a.) and
.3.2-9(3).
The procedure-required approval.from the Shift Supervisor and listed the plant conditions for performing.the test.
The' required test
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equipment was specified.
The procedure contained requirements for independent l verification for lifting and restoring leads. A sign off for each step. performed was required.
.The procedures requires the
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documentation of?the test results in the comment section and the Shift Supervisor be notified of the results when the test is completed.
The technicians performing this test used the. latest approved procedure and drawings from. Document Control.
Permission from the Shift Supervisor and' assistance from Operation was requested and received.
During the performance of the test, each step was signed off as required.
All switches were operated' by the control room operators.
The lif ting and.
restoration of leads was controlled and independently verified. When the
- test was completed the comment section was completed stating the test was acceptable and the Shif t Supervisor was notified. The _ procedure was then
' reviewed by the I&C Foreman.
The inspector reviewed and observed the partial performance for validating L
Surveillance Procedure 57SV-C82-008-15, Remote Shutduwn Suppression Chamber Water Temperature Loop Calibration.
The plant performs a preliminary test run for a procedure to ensure it can be performed.
This preliminary performance is called validation and the procedure is identified " Approved for Validation Use Only."
The validation procedure eppeared to be adequate, however, the technicians could not complete the
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requirements due to an inaccessible RTD.
The purpose of the procedure and the Technical Specification requirements Table 4.2-15, item 4 were clearly g
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a stated.- Theifrequency;for Performance was listed..The required test equipment was, listed and Ethe special L requirements 4were' stated.
Shift
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independent l verification.'for lifting-and restoringr leads' is required.
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o The-instructions in?the' procedure were clear and concise. The acceptance
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criteria; was. specific., A section ' requires the documentation of-the results and corrective action needed.'
The individuals performing both surveillancejtests were knowledgeable of-
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the requirements. fore performing their? tasks. and did so. in a safe and -
professional manner. Both. surveillance procedures'were found adequate for
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= the activities. they addressed within the areasfexamined.
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The~ inspector re' viewed and observed the work' performed by three different-Maintenance Work Orders (MWO): and the' calibration procedure specified on.
each.MWO. The NW0s were used for corrective maintenance. Each MW0. stated the work requested, the master parts listJ (MPL) number, the. required calibration. procedure, the' required clearances and permits needed and the safety classification. ' Each MWO was reviewed by QC and hold points were specified when. required.
The required' approvals were signed and Good Housekeeping work instructions per procedure 51GM-MNT-002-0S was listed.
MWO 1-87-6331 requested the RSDP Rx Water Level Indicator 1821-R070 on the Remote. Shutdown Panel be repaired or replaced.
The MWO.specified Calibration' Procedure 57CP-CAL-064-15, Yarway Level Indicators / Switches Calibration. lDuring the performance ~ of.the-calibration procedure, the
. senior technician -experienced some-difficulty and had to refer to the Technical Manual specified in the procedure to understand the requirements for locating the zero. and span adjustments.
It was determined that the procedure was vague in this area.
The licensee agreed to clarify the procedure, 57CP-CAL-064-1S, for locating and adjusting the zero and span adjustment.
MW0.2-87-2016 and MWO 2-87-1383 both specified using Calibration Procedure
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57CP-CAL-067_-25, Square D Pressure Switch 9012 and 9013 Calibration. MWO 2-87-2016 requested the HPCI Oil Filter DP Switch 2E41-N753 be repaired or replaced.
The switch was found to be defective and was replaced as
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required. The Work Performed Section of the MWO was completed stating the
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problem and the corrective-action taken.
The Material Required Section i
.for the replacement switch was completed.
The MW0 was signed by the technician performing the work and turned in for review and signing by the I&C Foreman.
i MWO 2-87-1383 required the HPCI Turbine Bearing Oil Pressure low Switch j
2E41-N752 be calibrated.
The MWO requested the cause for the associated j
alarm be determined and corrected.
The pressure switch was calibrated and
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I fSond to be within tolerances.
The MWO specified a functional Test be performed by Operations to confirm the low pressure alarm should not be
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received unless the condition exist.
The ISC Foreman and Supervisar reviewed the MWO at the reouest of the inspector to determine what further action is required, l
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The technicians performing the work for the three MW0s were knowledgeable of requirements for performing their tasks-and did so in a safe and t
profession manner.
The inspector reviewed the training.and qualification records for the six technicians who performed the surveillance procedures and the work for the MW0s.
The records were found adequate and the technicians certified to perform the work assigned to them.
The inspector reviewed calibration procedure 57CP-CAL-067,25,. Square-D Pressure. Switch 9012 and 9013 Calibration and found there is overlap in the acceptance criteria for 2E41-N752.
The acceptance criteria for the l
Low Setpoint is 6.0 to 8.0 psig and the High Setpoint is 7.0 to 9.0 psig.
The only setpoint is. the Low Setpoint which is 7.0 psig.
The reset function is incorrectly identified as the High Setpoint. The HpCI turbine manual appears to specify the reset function should be 1.0 psig greater than the Low Setpoint of 6.0 to 8.0 psig.
The overlap of the acceptance criteria ' is categorized as a Violation, 50-366/87-22-01:
Inadequate Acceptance Criteria for Pressure Switch 2E41-N752 Calibration.
7.
Inspection of Heat Shrinkable Tubing The licensee has included the requirements for inspection of any repairs requiring splicing of wiring in the following general maintenance procedures:
52GM-MEL-014-0 Installation and Maintenance of Valcor Solenoid Valves and Sealing of Target Rock SOVs 52GM-MEL-007-0S Installation and Maintenance of NAMC0 Limit Switches 52GM-MEL-011-0S Installation and Maintenance of ASCO Solenoid Valves 52GM-MEL-003-0S Cable and Cableway Installation During this inspection, the inspector was advised that all splicing and sealing of wiring to meet 10 CFR 50.49 requircaents was to be incorporated into one procedure.
The inspector reviewed training reports for personnel training in the applicati,on of Ray Chem splices.
The training was a
" hands-on" type training conducted by the vendor's instructors.
Certificates were issued to indicate successful completion in the techniques of selection, application and inspection of low voltage Nuclear Splicing Products. The training was conducted April 28, 1981. A total of 44 technicians took the training, 23 are still at the plant.
It should further be noted that the foreman making work assignments is required to insure the personnel assigned a task are qualified to perform the assigned-duty.
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InspectorFollowupItem(IFI)
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I (Closed) IFI 321/86-38-01, Licensee to Develop Procedures to Control the i,
Change-out and Replacement of Safe Shutdown / Appendix R Fuses:
The licensee i
has issued. Corrective Maintenance Procedure No. 52CM-MEL-002-IS,
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Replacement Control of Safe. Shutdown Appendix R Fuses.
This procednre
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applies to Unit 1 only and contains a table that identifies the fuse j
il location, replacement-type, size and manufacturer for indicated Spendix R fuses.
The licensee has estat,11shed a 10 year service life for these fuses.
All fuse involved were replaced in Unit i during the last refueling cutage.
Due to certain modifications reouired by design change requests86-099, 86-100 an 86-101, the Unit 2 fuses will be replaced as part of the next
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refueling outage maintenance scheduled for early 1988.
This item is
closed for Unit 1 only.-
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IE Bulletins (IEB)
l (Closed) IEB 84-02, Wilures of General Electric Type HFA Relays in Class l
IE. Safety Systems.
A review of records at the plant revealed that the required change out of HFA coils or relay units was accomplished in Unit 2 i
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durir4: the 1986 refueling outage.
The Unit 1 changeout was completed May 27, 1987, during the early portion of the 1987 refueling ontage. This bulletin is closed, j
(Closed) IEB 80-16, Potential Misapplication of Rosemont INC Models 1151 and 1152 Pressure Transmitters with Either "A" or "D" Output Cards. The licensee's letter dated December 14, 1982 stated as follows:
" Justification for continued operation is based on the following discussion.
Hatch Unit I was not licensed with a MSIV leakage
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control system.
In response to NUREG-0737, we have completed an j
analysis which assesses the dose to the control room operators
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following a design basis loss of coolant accident assuming a realistic leakage rate through the MSIVs.
The results of the
calculation demonstrated that all of the dose values are within the i
dose limits set forth in SRP 6.4 and GDC-19. Although this analysis j
has been completed for Unit 1, it is equally applicable to Unit 2 i
since the units are almost identical.
Further, a comparison between the Unit 1 and Unit 2 offsite dose i
calculations has been completed and has provided assurance that no l
offsite dose limits will be exceeded assuming no operation of the
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MSIV ' Leakage Control System.
J Based on the above, continued operation is justified.
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As part of the upcoming Unit 2 outage, we intend to replace the Model
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1151 transmitters with Model 11538 transmitters."
-j Plant documents indicate that the Unit 2 transmitters.in question were
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replaced as of August 28,'1984. This bulletin is closed.
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