IR 05000410/1986057
| ML17055C637 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/07/1986 |
| From: | Briggs L, Marilyn Evans, Florek D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055C636 | List: |
| References | |
| 50-410-86-57, NUDOCS 8611170358 | |
| Download: ML17055C637 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/86-57 Docket No.
50-410 License No.
CPPR-112 Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Nuclear Station Unit 2 Inspection At:
Scriba New York Inspection Conducted:
Octob r 20-24 1986 Inspectors:
D.
r Lea Reactor Engineer ((rS d te M. Evans, Reactor E gineer Approved by:
L. Briggs, Chic
, Test Program Section, OB, DRS a
e date Ins ection Summar
Ins ection on October 20-24 1986 Re ort No.
Areas Ins ected:
Routine unannounced inspection by two region based inspectors of licensee actions on previous inspection findings, power ascension test program, surveillance review, QA/QC interfaces, independent verification and plant tours.
'esults:
No violations were identified.
NOTE:
For acronyms not defined, refer to NUREG-0544 "Handbook of Acronyms and Initialisms."
8611170358 861110 PDR ADQCK 05000410
I ",)'
DETAILS
'ersons Contacted Nia ara Mohawk Power Cor oration
"R. Abbott, Station Superintendent G.
Car lisle, Lead STD and A Engineer
"J.
Conway, Power Ascension Manager G. Corbin, Training Supervisor
"J.
Cushman, Engineering
"G. Doyle, Quality Assurance (QA), Engineering
"M. Jones, Operations Superintendent L. Lagoe, Unit Instrumentation and Controls Supervisor
"J. McKenzie, QA Supervisor
- T. Perkins, General Superintendent
"A. Pinter, Site Licensing Engineer J.
R. Robles, GE Site Operations Manager
"K. Tyger, QA Engineer
- R. Warren, Surveillance Coordinator P. Wielde, QA Surveillance Supervisor Other NRC Personnel W. Cook, Senior Resident Inspector
- Denotes those present at the exit meeting conducted on October 24, 1986.
The inspector also contacted other members of the licensee's QA, operations and technical staff.
2.0 Licensee Actions on Previous Ins ection Findin s
(Closed)
Unresolved Item (410/86-50-01).
This item deals with issuance of Surveillance Procedure N2-OSP-RMC
001 CRD Scram Insertion Time Testing which would be used to support testing defined in SUT-5-0V, Control Rod Testing.
The inspector reviewed issued Procedure N2-OSP-RMC 9 001, Revision 0, dated October 24, 1986.
This item is closed.
(Closed)
Unresolved Item (410/86-50-02).
This item deals with the standby liquid control system valve lineup.
This item was previously reviewed in inspection report 50-410/86-51.
Based on review of changes to procedures N2-OSP-101A and N2-OP-36A dated October 10, 1986 and field inspection of the locked position of valve 2SLS-VS this item is closed.
3.0 Power Ascension Test Pro ram
V y
References Regulatory Guide 1.68, Revision 2, August 1978 "Initial Test Program for Mater Cooled Nuclear'Power Plants".
"Administration Controls and guality Assurance for the Operations Phase of Nuclear Power Plants".
Nine Mile Point Unit 2 (NMP-2) Technical Specifications Final Draft, June 25, 1986.
NMP-2 Final Safety Analysis Report ( FSAR)
Chapter 14 "Initial Test Program NMP-2 Safety Evaluation Report.
3.1 Power Ascension Test Procedure Review
~Scn e
The procedures of Attachment A'ere reviewed for the attributes identified in Inspection Report 50-410/86-38, Section 4.3.
Discussion The procedures reviewed were considered generally acceptable.
Many of the procedures reviewed were drafts of new revisions of the pro-cedure to reflect the licensee followup review of issued procedures for consistency with other issued operating procedures.
Licensee final reviews and approval activities needed to be completed and are ongoing.
The inspector held discussions with licensee personnel following his review of procedures N2-SUT-28-2 and N2-SUT-31-2 to discuss necessary prerequisites and permissible operator actions considered acceptable during the conduct of these tests and which would not impact on satisfying the acceptance criteria.
While the licensee procedure was in general consistent or more restrictive, this =discussion assured that any future changes to the procedure would not invalidate the test or test objectives.
~Findin s
No violations were identified.
3.2 Trainin in the Power Ascension Pro ram The inspector reviewed training lesson plans and discussed with the Training Supervisor on the scope of training provided to station
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personnel other than test engineers.
The inspector reviewed five training modules provided to plant operators on the power ascension test program.
Included as part of the training was use of the plant simulator to run the startup test.
This activity was very beneficial in that it provided feedback to the procedure writers.
In addition, familiarization training on the overall program was provided to general station personnel.
The inspector also witnessed portions of the technical training provided to test engineers on the aspect of control system tuning.
The purpose of this training was to provide a
general overview of control system tuning for test engineers, even though many would not be directly involved in this specific activity.
No unacceptable conditions were observed in this activity.
4.0 Surveillance Activities The inspector reviewed the licensee status of surveillance tests, reviewed the current surveillance test results of N2-ISP-SNP-R103 and N2-ISP-CSL-MOOl and witnessed portions of the performance of N2-ISP-CSH-M007 as part of the continuing review of surveillance activities to support fuel load.
Based on review of the surveillance test schedule some previously performed survei llances require reperformance to be current to support fuel load.
Surveillance test witnessed N2-1SP-CSH-M007 was one such test.
The surveillance test results reviewed were acceptable.
The inspector noted no unacceptable conditions in the surveillance witnessed op the test results reviewed.
. 0 gAA/
The inspector reviewed the gA Power Ascension Surveillance Program dated August 19, 1986.
The licensee plans for surveillance of selected test activities and for review of all startup test results and plateau reviews.
Manpower to perform the gA activities was allocated and assignments defined.
No unacceptable conditions were noted in the gA plans.
During discussions with the gA Surveillance Supervisor, the inspector became aware of a gA finding concerning the effect of two events of "rusty water" coming in contact with the fuel stored in the fuel storage racks.
The event occurred when, with the fuel storage pool gates out, starting of the RHR and feedwater system introduced
"rusty water" into the vessel which came in contact with the fuel storage racks.
The inspector further pursued this item and found that the licensee dechanneled two fuel assemblies, wiped them down and analyzed the smears.
Based on the analysis, the fuel manufacturer indicated that no deleterious effects on the fuel would result.
Normal operation of the cleanup system would acceptably clean up the water.
The licensee's actions were acceptable to the inspecto g
6.0 Inde endent Verification During the course of this inspection the inspector independently verified standby liquid control system valve position and assessed the test methodology of several of the startup test procedures.
'.0 Plant Tours and Meetin s
~Sco e
The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls, status of construction and testing activities.
In addition, the inspector randomly attended the licensee's morning Startup Plan of the Day meeting during which the current status of preoperational testing activities and any holds or delays are discussed.
Other items such as surveillance and outage activities are also discussed.
No unacceptable conditions were observed.
8.
Exit Interview A
management meeting was held at the conclusion of the inspection on October
- 24, 1986, to discuss the inspection scope, findings and observations as detailed in this report (see Paragraph 1 for attendees).
No written information was provided to the licensee at any time during this inspection.
The licensee did not indicate that any proprietary information was contained within the scope of this inspection.
P
4l
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+
A
ATTACHMENT A POWER ASCENSION TEST PROCEDURE REVIEW N2-SUT-03-0V, Fuel Load, Revision 2, SORC reviewed October 15, 1986.
N2-SUT-05-0V, Control Rod Drive, Revision 1,
SORC reviewed September 3,
1986.
N2-SUT-04-HU, Full Core Shutdown Margin Demonstration, Revision 1,
SORC
- reviewed October 6, 1986.
N2-SUT-06-HU, SRM Performance, Revision 0, SORC reviewed September 25, 1986.
N2-SUT-74-HU, Off Gas, Revision 1, draft dated October 1986.
N2-SUT-02-1, Radiation Measurements, Revision 1, draft dated October 1986.
N2-SUT-10-1, IRM Performance, Revision 1, draft dated October 1986.
N2-SUT-11-1, LPRM Flux Response, Revision 1, draft dated October 1986.
N2-SUT-12-1, APRM Calibration, Revision 1, draft dated October 1986.
N2-SUT-13-1, Process Computer, Revision 0, SORC reviewed July 17, 1986.
N2-SUT-14-1, RCIC System, Revision 0, SORC reviewed September 12, 1986.
N2-SUT-17-1, System Expansion, Revision 1, draft dated September 1986.
N2-SUT-19-1, Core Performance, Revision 0, SORC reviewed July 25, 1986.
N2-SUT-23-1, Feedwater System, Revision 0, SORC'eviewed August 20, 1986.
N2-SUT-26-1, Relief Valve Testing, Revision 0, SORC reviewed September 12, 1986.
N2-SUT-29-1, Recirculation Flow Control, Revision 0, SORC reviewed September ll, 1986.
N2-SUT-33-1, Drywell Piping Vibration, Revision 0, SORC reviewed July 25, 1986.
N2-SUT-76-1, ESF Area Cooling System, Revision 0, SORC reviewed August 20, 1986.
N2-SUT-14-2, RCIC System, Revision 0, SORC reviewed September 12, 1986.
N2-SUT-28-2, Shutdown from Outside Control Room, Revision 0, draft dated August 1986.
N2-SUT-31-2, Loss of Turbine Generator and Offsite Power, Revision 0, draft dated October 198 \\-
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