IR 05000313/1987034
| ML20236G133 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/20/1987 |
| From: | Greg Pick, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236F888 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-313-87-34, 50-368-87-34, NUDOCS 8711020433 | |
| Download: ML20236G133 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION l
REGION IV
NRC Inspection Report: 50-313/67-34 Licenses:
DPR-51 50-368/87-34 NPF-6 Dockets:
50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)
P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (AN0)
Inspection At:
Russellville, Arkansas Inspection Conducted:
September 28 through October 2,1987 Inspector:
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b2 20l'7f7 G.' A. Pifk Reactor Inspector, Operational Date
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Proggis S ction, Operations Branch l
ON#/f7 Approved:
W. C. Seidlel Chief, Operational Programs Date
Section, Operations Branch Inspection Summary Inspection Conducted September 28 through October 2, 1987 (Report 50-313/87-34; 50-368/87-34)
Areas Inspected:
Routine, announced inspection of verification of Regulatory Guide (RG) 1.97 conformance for Unit 2 and followup of previously identified items.
Results: Within the areas inspected, no violations or deviations were ldsntified, e matB M ho
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DETAILS
- 1 Persons Contacted AP&L
- J. M. Levine, Executive Director, AN0 Site Operations (
- D. Howard, Special Projects Manager
- R. Lane, Engineering Manager
- E. C. Ewing, General Manager, Plant Support
- H. Greene, Quality Assurance (QA) Superintendent
- D. B. Lomax, Plant Licensing Supervisor
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- G. D. Provencher, QA Supervisor
- P. Michalk, Plant Licensing Engineer G. Sullins, Instrument & Control (I&C) Engineer G. H. Kendrick, I&C Supervisor R. D. Bussey, QA Engineer
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- W. D. Johnson, Senior Resident Inspector
- C. C. Harbuck, Resident Inspector
- Attended the exit interview.
2.
Followup on Previously Identified Items (Closed) Violation (313/8614-05):
The violation concerned inadequate drawing control.
The NRC inspector verified that the corrective actions were conducted as proposed in the licensee's response dated September 30, 1986.
It was determined that seven design control packages (DCP) out of the original set (approximately 320 DCPs) were still outstanding.
The design drawings had been corrected.
The 1986 design control audit findings and evaluation resulted in the creation of an isometric update program as described in Procedure 1409.42, Revision 0, " Isometric Drawing Update," with a target completion date of September 1989.
The QA review consisted of two separate system walkdowns to verify the accuracy of 26 hanger drawings in the service water system and 15 hanger drawings in the emergency feedwater system.
The results of the walkdowns are explained below.
This item is considered closed.
A result of the QA walkdowns, conducted as corrective action to Violation 313/8614-05, was the identification of inaccuracies in three Bechtel supplied drawings.
Quality Action Request (QAR)-312 was issued requiring correction of the three Bechtel drawings:
HBD-14-H6, Revision 3; HBD-21-H2, Revision 2; and HBD-14-H16, Revision F2-1 and a seismic reanalysis.
The NRC inspector determined that the drawings will be corrected as part of the isometric update program mentioned in the previous paragraph.
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DETAILS 1.
Persons. Contacted AP&L
- J. M. Levine, Executive Director, AN0 Site Operations
- D. Howard, Special Projects Manager
- R. Lane, Engineering Manager
- E. C. Ewing, General Manager, Plant Support
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- H. Greene, Quality Assurance (QA) Superintendent
- D. B. Lomax, Plant Licensing Supervisor
- G. D. Provencher,.QA Supervisor
- P. Michalk, Plant Licensing Engineer G. Sullins, Instrument & Control (I&C) Engineer G. H. Kendrick, I&C Supervisor R. D. Bussey, QA Engineer NRC
- W. D. Johnson, Senior Resident Inspector
- C. C. Harbuck, Resident Inspector
" Attended the exit interview.
-2.
Followup on Previously Identified Items (Closed) Violation (313/8614-05):
The violation concerned inadequate drawing control.
The NRC inspector verified that the corrective actions-were conducted as proposed in the licensee's response dated September 30, 1986.
It was determined that seven design control packages (DCP) out of the original set (approximately 320 DCPs) were still outstanding.
The design drawings had been corrected.
The 1986 design control audit findings and evaluation resulted in the creation of an isometric update program as described in Procedure 1409.42, Revision 0, " Isometric Drawing Update," with a target completion date of September 1989.
The QA review consisted of two separate system walkdowns to verify the accuracy of 26 hanger drawings in the service water system and 15 hanger drawings in the emergency feedwater system.
The results of the walkdowns are explained below.
This item is considered closed.
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A result of the QA walkdowns, conducted as corrective action to
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Violation 313/8614-05, was the identification of inaccuracies in three Bechtel supplied drawings.
Quality Action Request (QAR)-312 was issued
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requiring correction of the three Bechtel drawings:
HBD-14-H6, Revision 3; H8D-21-H2, Revision 2; and HBD-14-H16, Revision F2-1 and a seismic reanalysis.
The NRC inspector determined that the drawings will be corrected as part of the isometric update program mentioned in the previous paragraph.
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h I-The NRC inspector asked the QA department the status of QAR-312 and, it subsequently, determined that the QAR was not on the punchlist as L
described in QA operating Procedure QAO-10,. Revision 0, " Corrective L
Action."
The licensee committed to comparing the QA punchlist to the i.
various types of corrective action vehicles described in QA0-10,
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Revision 0, which are outstanding and may not be documented on the punchlist.
This open item (313;368/8734-01) will be reviewed in a subsequent inspection.
3.
Instrumentation Used to Assess Plant Conditions During and Following an Accident (RG 1.97 Implementation) - Unit 2 The NRC inspector verified that' AP&L had instrumentation systems for
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assessing plant conditions during and following the course of an accident that met the licensee's commitments to RG 1.97, Revision 3.
The NRC inspector compared installed plant instrumentation with the commitments contained in an AP&L letter dated April 13, 1984, and the SER concerning that letter dated October 23, 1986.
The NRC inspector utilized the following documents and correspondence related to Unit 2 during conduct of the inspection:
" Environmental Qualification Master List," Revision 4, dated April 15, 1987
" Numerical Instrument Index List," M-2501, Revision 33, dated August 19, 1986
" Environmental Qualification - Regulatory Guide 1.97 Interface,"
0LC-125-29, dated December 13, 1985 Submittal, NUREG 0737 Su J. R. Marshall, Manager,pplement 1 " Regulatory Guide 1.97," from Licensing, AP&L, to D. G. Eisenhut, Director, Division of Licensing, NRR, dated April 13, 1984 Safety Evaluation Report, " Emergency Response Capability - Regulatory Guide 1.97," from R. S. Lee, Project Manager, PWR PD-7, NRR, to T. G. Campbell, Vice President, Nuclear Operations, AP&L, dated October 23, 1986 Submittal, " Regulatory Guide 1.97 SER - Response to Open Items," from J. T. Enos, Manager, Nuclear Engineering and Licensing to R. S. Lee, Project Manager, PWR PD-7, NRR, dated December 23, 1986 In ten Category 1 systems (as defined in RG 1.97), the NRC inspector verified the following:
the environmental qualification (EQ) master list addressed environmental qualification of instrumentation; the licensee's Q-list confirmed seismic qualification and confirmed that the system was covered by the licensee's QA program; redundant instrument circuits were utilized with the required separation and the power supplies were
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The NRC~ inspector asked the QA' department the' status 'of QAR-312 and, subsequently, determined that the QAR was not:on the punchlist as?
described in QA operati.ng Procedure QA0-10' Revision 0, " Corrective
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' Action."_ The licensee committed to comparing the QA punchlist to.the-
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'various types of corrective actioncvehicles described in QA0-10,~
Revision 0, which are outstanding and may not:be documented on the Lpunchlist.
This open item (313;368/8734-01) will be rev4wed in a subsequent ins ~p'ection.
3.
. Instrumentation Used to Asses's Plant' Conditions During and Following an-
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Accident (RG 1.97 Implementation) - Unit 2
.TheNRC inspector verifi.ed that'AP&L had instrumentation. systems for assessing plant conditions during and following the course of an accident
'that. met the licensee's commitments-to RG.1.97, Revi_sion 3.
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l The'NRC inspector compared installed plant. instrumentation with the-commitments contained.in an'AP&L letter dated April 13, 1984, and the SER
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concerning that letter dated October 23, 1986.'
The NRC inspector utilized the following documents and correspondence.
related to Unit 2 during conduct of the inspection:
" Environmental Qualification Master List," Revision 4, dated
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April'15, 1987 L
" Numerical Instrument Index List," M-2501, Revision 33,' dated August 19, 1986
" Environmental Qualification - Regulatory Guide.1'.97 Interface,"
OLC-125-29, dated December 13, 1985
Submittal, NUREG 0737 Supplement 1
" Regulatory Guide 1.97," from J. R. Marshall, Manager, Licensing, AP&L, to D. G. Eisenhut, Director, Division of Licensing, NRR, dated April 13, 1984
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Safety Evaluation Report, " Emergency Response. Capability - Regulatory Guide 1.97," from R. S. Lee, Project Manager,- PWR PD-7, NRR, to T. G. Campbell, Vice President, Nuclear. Operations, AP&L, dated October-23, 1986 Submittal, " Regulatory Guide 1.97-SER - Response to Open Items," from j
J. T. Enos,' Manager, Nuclear Engineering and Licensing to R. S. Lee, j
Project Manager, PWR PD-7, NRR, dated December 23, 1986-
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'In ten Category 1 systems-(as defined in RG 1.97), the NRC inspector H
verified the following:
the environmental qualification (EQ) master list addressed environmental qualification of instrumentation; the licensee's Q-list confirmed seismic qualification and confirmed that the system was covered by the licensee's QA program; redundant instrument circuits were
utilized with the required separation and the power supplies were LL
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l safety-related and redundant; one indication per division and one
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recording of r'eadout information existed in the control room as determined
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by visual observation of the instrumentation monitors; the range of the instrumentation, including overlapping for extended ranges met the commitments; the parameters of interest were being monitored by a direct
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sensing device and all interfaces with unqualified portions of the circuit
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were isolated; and the testing / calibration frequency met the requirements in RG 1.97.
In seven Category 2 systems, the NRC inspector verified the following:
the EQ master list confirmed environmental qualification and the Q-list
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_j confirmed the instrumentation was covered under the QA program; the
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instrument signal was displayed in the control room or processed for display on demand; the. range met commitments, including overlap, if required; the parameters of interest were directly sensed and any interfaces within the instrument circuit between qualified / unqualified or sensing circuitry / monitoring circuitry had isolation devices; and the testing / calibration frequency met RG 1.97 provisions.
The ten Category 1 and seven Category 2 systems inspected are listed below:
Category 1 RCS Hot Leg Water Temperature RCS Pressure Containment Hydrogen Concentration l
Steam Generator Level Steam Generator Pressure Containment Pressure Containment Area Radiation Monitors Refueling Water' Storage Tank Level Pressurizer Level Emergency Feedwater Flow Category 2
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Degrees of Subcooling I
Safety Injection Tank (Accumulator) Level Bottom to Top
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Safety Injection Tank Isolation Valve Position
Boric Acid Charging Flow Pressurizer Heater Status Safety / Relief Valve Positions or Main Steam Flow Volume Control Tank Level Top to Bottom The documentation utilized during this inspection included functional diagrams showing redundancy, electrical separation, related electrical power sources, and isolation interface points.
The diagrams consisted of the below listed piping and instrument drawings (P& ids) and schematic diagrams (electrical schematics).
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M'-2204, Sheet 4, Revision 27, "Emergenay Feedwater"
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M-2206, Sheet 1, Revision 78',J" Steam Generator Secondary System'.'
.M-2230, Sheet 1, Revision,45,~" Reactor CoolantLSystem"
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M-2230, Sheet 2, Revision 2,"ReactorCoolanhSystem":
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- M-2231, Sheet 11, Revision 57, " Chemical &. Volume Control. System"'
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M-2232,~ Revision 54-3, " Safety Injection System"
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.M-2236,-Sheet =1, Revision 34, " Containment Spray System"
-M-2236, Sheet:2, Revision 2, " Containment Spray System" M-2261, Sheet 3,-Revision 18, " Air Flow & Control Diagram HVAC Post-Accident Hydrogen Analysis: System" Schematic-Diagrams E-2006,.-Revision.16. " Low Voltage Safety" Systems Power Supplies" E-2191, Revision 15, " Pressurizer Proportional. Heater Bank Control"'
E-2202, Revision l15-1, " Safety Injection Tanks Discharge MOVs"'
E-2433, Sheet 5, Revision 3, " Post-LOCA'High Range Containment Area Radiation Monitors"
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E-2524, Revision 11, "Uninterruptible Power Supply. Interconnections"
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E-2576, Sheet 6, Revision 1, " Containment Atmosphere Radiation &
Hydrogen Monitoring System" E-2701, Sheet 5, Revision 3, " Reactor Coolant Loop Temperature Protection"
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E-2701, Sheet SA, Revision 3, " Reactor Coolant Loop Temperature Protection" E-2701, Sheet 6, Revision 3, " Reactor Coolant-Loop Temperature l
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Protection" E-2701, Sheet 9, Revision 4, " Steam Generator 2E24A and 2E24B Hot Leg L
Coolant Temperature Scheme"
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E-2701,' Sheet 10, Revision 3, " Steam' Generator 2E24A and 2E24B Hot
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l Leg Coolant Temperature Scheme" e
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, E-2702, Shiet'1,JRevision 8, " Reactor Coolant Loop Temperature-
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Control" E-2702,cSheet.2, Revision 14,." Reactor Coolant Loop-Temperature Control" E-270_2, Sheet [4LRevision16,"ReactorCoolantLoopTemperature-E Control
E-2702,, Sheet 5, Revision 1, " Reactor Coolant Loop #1 Hot Leg'
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Temperature Control"'
E-2702r Sheet _6, Revision-1,." Reactor Coolant Loop #2 Hot Leg Temperature Control" E-2703, Sheet 1, Revision 12, " Pressurizer Pressure Protection" l
i E-2703, Sh et 2, Revision 13, " Pressurizer Pressure Protection'.'
E-2703,-Sheet 3, Revision 10, " Pressurizer Pressure Protection" E-2703, Sheet 4,-Revision 10, " Pressurizer Pressure Protection" E-2704, Sheet 3, Revision 22-1, " Instrumentation Pressurizer Level
- Loop" E-2704, Sheet 4, Revision N-1, " Instrumentation Pressurizer Level Loop" E-2707, Sheet 3, Revision 2-1, " Reactor Coolant System Pres'surizer" E-2711, Revision 8, " Charging Pump' Pressure and Flow"
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'E-2715, Sheet 2, Revision 11, " Chemical and Volume Control Tank 2T4" l
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E-2719, Sheet 1, Revision 8,-" Safety Injection Tank Level"
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~E-2719, Sheet 2, Revision 7, " Safety Injection Tank Level" E-2719, Sheet 3, Revision 7, " Safety Injection Tank Level" E-2719, Sheet 4, Revision 7," Safety (InjectionTankLevel" E-2723, Sheet 1, Revision 9, " Refueling Water Tank" E-2723, Sheet 3, Revision 7, " Refueling Water Tank"
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E-2724, Sheet 1, Revision 17, " Steam Generator Pressure Protection" j
E-2724, Sheet 2, Revision 12, " Steam Generator Pressure Protection" l
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E-2724,-Sheet 2A, Revision 1, " Steam Generator. Pressure' Protection" E-2733,-Sheet 1, Revision 4, "DC Power Supplies" E-2733, Sheet 2, Revision 3,'"DC. Power Supplies"
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E-2751, Sheet 21, Revision 2-1, " Steam Generator Wide Range Level"
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E-2751, Sheet-22, Revision N, " Steam Generator Wide Range Level" E-2752, Sheet 11, Revision 13, " Miscellaneous Flow Loops" E-2753, Sheet 31, Revision 1, " Instrumentation Miscellaneous Pressure Loop" E-2759,' Sheet 1, Revision 0, " Main Steam Safety Relief Valve Position Indicating System" E-2759, Sheet 2, Revision 0, " Main Steam Safety Relief Valve Position Indicating System" E-2995, Sheet 1, Revision 11, " Connection Diagram - Auxiliary Equipment Panel" I
E-2995, Sheet 3, Revision 11, " Connection Diagram - Auxiliary
Equipment Panel" The NRC inspector, as part of verifying that the instrumentation was part i
of AP&L's testing / calibration program, determined through review of (
selected procedures that the surveillance had been conducted since the instruments were installed. -The instruments selected were:
volume control tank level, reactor coolant system pressure, charging flow, and refueling water tank level, q
During review of the correspondence between AP&L and NRR and conduct of l
the inspection, the NRC inspector determined that the licensee met their commitments as proposed in the submittals dated April 13, 1984.. Until l
final acceptance by NRR, there exists some uncertainty on whether the i
installed instrumentation related to these two systems is sufficient.
This is an open item (368/8734-02) which is awaiting final NRR acceptance of AP&L's instrumentation system and subsequent inspection.
No violations or deviations were identified.
4.
Exit Interview l
The inspection scope and finaires were summarized on October 2, 1987, with those persons indicated in paragraph 1.
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