IR 05000338/1989027
| ML20246M548 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/22/1989 |
| From: | Conlon T, Ruff A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20246M546 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-338-89-27, 50-339-89-27, GL-86-10, GL-88-12, NUDOCS 8909070189 | |
| Download: ML20246M548 (6) | |
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, UNITED STATES.
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'101 MARIETTA STREET,N.W :
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' (Report Nosi:. -.50-338/89-27(and' 50-339/89-27
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':Licenseef. Virginia. Electric and: Power Codipany,
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- 50-338:and'50-339
,' License Nos.:L NPF-4 and NPF-7A WM IDscketNos.:
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Fability.Name: North Anna"1 and 2 S
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. Inspection Conducted:'EJuly.311 " August.4,11989? T
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-r fate Jigned
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Date Signed y
T. Conlon,. Chief
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Plant' Systems:Section V
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Division of. Reactor. Safety
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SUMMARY L-D.
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q This routine, unannounced inspection.was : conducted to followup on licensee's -
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' action in regard to previous inspection findings.
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Certain items -(Violation; and Deviation) discussed.. in this report. required..
licensee' written responses.
These were prompt and/ complete 'and ~were received beforen the inspection.
During the -inspection, flicensee representatives?
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responsible and professional manner.
The inspection;of these' licensee actions
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identified. However, some weaknesses.were observed-as indicated below:
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l(1)" An internal. licensee memorandum No. GOV 0-54-02.was issued on -
March 31, 1986; -as:: Interim Deportability and Action Statement -
Guidelines for: Appendix R Systems and. Equipment. 'This document has?
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.not been factored into ' station procedures to-date.
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(2)1 Labelling of instruments for RG 1.97 criteria in the control room also-appears to be 'taking an < inordinate amount of ti.ne.
This item falls-under. the licensee s CRDR project Corrective Action (CA) 29E discussed in VEPC0's letter 85-268C of June 30, 1986 to the NRC.
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8909070189 890822
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PDR ADOCK 05000338
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i REPORT DETAILS
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1.c Persons Contacted Licensee Employees l
- G. Kane Station Manager
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- M. Bowling,_ Assistant Station Manager
'*P. Kemp,LSupervisor of Licensing
- J. Leberstion, Engineer
- A. Stell, = Superintendent of Operations G. Mocarski, Loss Prevention Coordinator D. Roberts, ShiftLiechnical Adviser-C. Zalesiak,' Staff Engineer Innsbrook
- R. Driscoll, Manager QA Other licensee employees contacted during this inspection included engineers, operators, security force. members,- technicians, and administrative personnel.
NRC Resident Inspectors
- J. Caldwell, Senior Resident Inspector L. King, Resident Inspector J. Monroe, Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.
2.
Action on Previous Inspection Findings (92701)'
.a.-
(Closed) Violation 50-338/87-26-01, Failure to Generate a Nonconformance Report for Nonconforming Equipment.
The above violation was cited in that terminal lugs in panel 1-EI-CB-05. were damaged, and grinding was done on. a remote multiplexer instrument rack 1-EI-CB-300. Neither of these items were identified by an NCR.
The license responded to this violation in a
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letter dated October 23, 1987.
By letter, dated November 13, 1987, the NRC acknowledged the licensee's response.
The NRC inspector reviewed the licensee's actions and had discussions with ' responsible licensee representatives.
These actions and the information during the discussions were considered to be sufficient and
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acceptable to close this item.
The licensee replaced the damaged terminal lugs on Work Order 064666 and the grinding on the panel was evaluated and considered not to be detrimental.
A calculation.
SE0-992, showed that the panel was seismically qualified.
These documents were examined and areas of concern were inspected.
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2 The license stated that the process of documenting nonconformances identified during installation of a design change has been in their training program and that station personnel are regularly instructed to report defects in accordance with ADM 16.1 Section 5.
This action is intended to insure that deficiencies are identified and placed in the corrective action process.
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(Closed) Violation 50-338,339/89-11-04, Failure to Identify Deficiency Conditions.
The above violation was cited for.four deficient ccnditions i.e.,
heavy dust in control panels, improperly spared cables (not properly identified), loose floor boards, and - broken or missing halon barriers.
The licensee transmitted his response to the violation in a letter, dated July 14, 1989.
This response has been reviewed and considered acceptable. The inspector reviewed the licensee's actions and had discussions with responsible licensee personnel.
These actions and information obtained during discussions with licensee representatives were considered acceptable and sufficient to close this item.
The licensee action was to clean panels, identify and tape spared cables (W. O. 091123 and 091124), replace loose floor boards, and repair and/or replace missing halon barriers.
These actions were verified by the NRC inspector in the field as being completed.
In addition, ADM 20.48 was revised to identify the Superintendent of Operations as the individual responsible for the material condition of the control room.
The licensee indicated that subsequent inspection of the CR shows that corrective actions are being identified and addressed in a timely manner.
No new deficient conditions were observed during the NRC Inspection of this area.
c.
Deviation (U-2) 50-339/87-37-04, Installed Fire Detection System in Quench Spray Pump House Not in Conformance to Commitments for Full Coverage.
The licensee provided responses to this deviation in letters dated February 5,1988 and April 29, 1988.
These responses were acknowledged, reviewed and considered acceptable by the NRC.
The inspector reviewed the licensee's actions and had a discussion with responsible licensee personnel. These actions and the information l
obtained during the discussion were considered acceptable and sufficient to close this item.
The licensee's action was to install additional new fire (smoke)
detectors in Quench Spray Pump Houses and Main Steam Valve Rooms.
Installation was accomplish by Design Change (DC) 83-18, (FC-22, 23).
The completed packages were reviewed by the inspector and the field
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installation 'was' inspected. Both were ' considered to be satisfactory.
As a result of this modification, chapter 6 of the Appendix'R report has been revised.
The modification also affects the Q List, FSAR and TS.
L The Q List change requested has been issued.
The. FSAR will be updated-in a future FSAR up-date and the TS change is being evaluated p,
t as part 'of G/L 88-12, Removal of Fire Protection Requirements from TS, guidelines.
d.
(Closed) Deviation 50-338,339/89-11-03, Deviation from RG 1.97 for Neutron Flux..
The' above deviation 'is with regard to the display and; recording criteria that _is specified in item 6 of Table'1 in RG 1.97, and.that is, recording of instrumentation readout information should be provided-for. at least one redundant channel.
Otherwise, it may be continuously updated, stored in computer memory, and displayed on demand.
The licensee transmitted his response for this' deviation in a letter dated July 14, 1989. This response has been reviewed by NRC and considered acceptable.
The licensee stated the ERFCS has been modified to include historical recording for RG 1.97 Neutron Flux instrument.
The NRC inspector-verified this when the licensee gave a demonstration of. the ERFCS with regard to Neutron Flux and other parameters.
With the modification indicated above, the licensee stated that their. review showed that all Category I equipment was now capable of being historically recorded on the ERFCS.. In addition, the licensee made a revision, which was reviewed by the NRC inspector,.to Engineering Standard STD-GN-0028, Engineering Guidelines for ERFCS.
STD-GN-0028, ERF Design Checklist, now addresses RG l' 97' criteria in the ' ERF impact questions section.
This checklist is used by the preparer of a Design Change' Package. This item is closed e.
(Closed) URI.50-338,339/85-24-01, Review of North Anna Power Station Appendix R Reanalysis and Fire Protection Program.
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Revision 3 to the North Anna 10 CFR 50, Appendix R, report was submitted to NRC by letter, dated March 21, 1986. The initial report L
was submitted in May 1984 and revised in October 1984 and 1985. An NRC Safety Evaluation Report for technical exemption requests from
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Appendix R for North Anna Power Station was issued on November 6,1986.
NRR's evaluation of the revised post-fire safe shutdown methodology is continuing for North Anna Power Station. Any action out of that review will be handled independently of this URI.
Region'II's review for this URI is, therefore, completed and this item is closed.
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(Closed) IFI 50-338,339/85-24-10, Appendix R Plant shutdown Components are Not Included in the Technical ~ Specifications.
Additional guidance in this area has been given to the licensee in Generic letter 86-10 and 88-12.
Review of licensee action for G/L 88-12, Removal of Fire Protection Requirements from TS, will be examined in a future NRC inspection.
In the interim, the licensee.
internal memorandum GOV-02-54-02 was issued March 31, 1986 as Interim Deportability and Action Statements Guidelines for Appendix R Systens
. and Equipment.
This guidance has been reviewed and is considered acceptable.
The licensee is in the process of factoring these guidelines into a station procedure. However, because an inordinate period of time has passed since. the memorandum was issued and it still has not been factored into station procedures, the NRC inspectors considers this as a weakness in the licensee's program.
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URI 50-338,339/89-11-02, Specific Identification of RG 1.97 Indicators.
RG 1.97, Revision 3, states that instruments designated as types A, B and C, and Categories 1 and 2 should be uniquely identified on
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control panels so that the operator can easily discern that they are intended' for use under accident conditions.
The licensee indicated in April 1989 (See NRC Report No. 50-338,339/89-11) that this item was covered by their CA 29E and discussed in VEPCO's Letter 85-268C of June 30, 1986 to the NRC.
CA 29E is still being evaluated by VEPCO's CRDR group.
The labelling of instruments for RG 1.97 criteria appears to be taking an inordinate amount of time and may possibly not meet Vepco's time table established in the above referenced letter.
This is considered a weakness in the licensee's program for implementing labelling criteria for post accident monitoring instruments.
3.
Exit Interview The inspections scope and results were summarized on August 4,1989, with those person indicated in paragraph 1.
The inspectors described the areas inspected and discussed in detail the inspection results as described in paragraph 2.
Proprietary information is not. contained in this report and l
no dissenting comments were received from the licensee.
4.
The following documents were reviewed and used to verify statements and conditions concerning item discussed in paragraph 2.
a.
ADM 16.1 (5/25/89), Station Deviation Reports b.
Memorandum GOV-02-54-02 (3-31-86), Interim Deportability and Action Statement Guidelines for Appendix R Systems and Equipment c.
ADM 20.48 (4-13-89), Station Material Condition and Housekeeping
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STD-GN-0028 (Rev.1), Engineering Guidelines for ERF Computer System.
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VEPC0 Letter 85-268C of June 30, 1986, Control Room Design Review f..
ADM-20.44 (6-1-89),' System and Component Labelling 5.
Acronyms and Initialisms CRDR Control Room Design Review CTS Commitment Tracking System DCP Design Change Package ERF Emergency Response Facility ERFCS Emergency Response Facility Computer FC Field Change FSAR Final Safety Analysis Report G/L Generic Letter NCR'
Nonconformance Report IFI Inspector Followup Item RG Regulatory Guide SER Safety Evaluation Report TS Technical Special URI Unresolved Item VEPC0 Virginia Electric and Power Company Y
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