IR 05000410/1986068
| ML20212G798 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/06/1987 |
| From: | Marilyn Evans, Petrone C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212G781 | List: |
| References | |
| 50-410-86-68, NUDOCS 8701210167 | |
| Download: ML20212G798 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/86-68 Docket No.
50-410 License No.
NPF-54 Licensee: Niagara Mohawk Power Corporation 301 Plainfield Road Syracuse, New York 13212 Facility Name: Nine Mile Point Nuclear Station, Unit 2 Inspection At:
Scriba, New York Inspection Conducted: December 8-12, 1986 Inspector: W
/!6!$7 M. Evans, Reactor Engineer date Approved by:
C.
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//G [87 C. Petrone, Chief, Test Programs Section date 08, DRS Inspection Summary:
Inspection on December 8-12, 1986 (Report No. 50-410/86-68).
Areas Inspected: Routine unannounced inspection by one region based inspector of preoperational test results review, overall power ascension test program, power ascension test procedure review, power ascension test results evaluation, surveillance test activities, scram discharge volume valves, QA/QC interfaces, independent measurements and verifications, and plant tours and meetings.
Results: No violations were identified.
NOTE:
For acronyms not defined, refer to NUREG-0544 " Handbook of Acronyms and Initialism."
8701210167 870113 PDR ADOCK 05000410
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DETAILS 1.0 Persons Contacted Niagara Mohawk Power Corporation
- R. Abbott, Station Superintendent
- M. Boyle, Nuclear Compliance and Verification
- J. Conway, Power Ascension Manager
- S. Cook, Special Projects
- W. Drews, Technical Support
- M. Jones, Superintendent Operations
- A. Pinter, Site Licensing Engineer
- N. Rademach, Quality Assurance (QA) Program Manager
- P. Wielde, QA Surveillance Supervision Other NRC Personnel
- W. Cook, Senior Resident Inspector
- W. Schmidt, Resident Inspector
- Denotes those present at the exit meeting on December 12, 1986.
The inspector also contacted other members of the licensee's technical, QA and operations staff.
2.0 Preoperational Test Results Review Scope The completed test p ocedures listed below were reviewed during this inspection to verify that adequate testing had been conducted to satisfy regulatory guidance, licensee commitments and FSAR requirements.
These preoperational tests were completed after the issuance of an operating license because the licensee had been granted an exemption permitting completion of these systems to be delayed until initial criticality.
N2-POT-82, Containment Atmosphere Monitoring System, Revision 1,
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System Operational December 3, 1986.
N2-POT-85, Leak Detection System, Revision 0, System Operational
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November 16, 1986.
Discussion The inspector reviewed the test results and verified the licensee's evaluation of test results by review of test changes, test exceptions, test deficiencies, "As-Run" copy of the test procedures, acceptance
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3 criteria, performance verification, recording conduct of test, QC inspection records, restoration of system to normal after test, independent verification of critical steps or parameters, identification of personnel conducting and evaluating test data, and verification that the test results have been approved.
During review of N2-P0T-85, the inspector questioned a
licensee representative concerning the testing of drywell air cooler temperature monitoring, as required in FSAR Table 14.2-112.
It appeared to the inspector that this testing was not conducted in N2-POT-85 nor was it noted in N2-POT-85 that the testing had been conducted in another preoperational test. Following a discussion with the licensee represent-ative, it was determined that adequate testing of drywell air cooler temperature monitoring had been conducted in preoperational test N2-P0T-60, Drywell Cooling.
Findings No unacceptable conditions were identified within the scope of this review.
3.0 Power Ascension Test Program (PATP)
3.1 References
Regulatory Guide 1.68, Revision 2, August 1978 " Initial Test Program for Water Cooled Nuclear Power Plants".
ANSI N18.7-1976 " Administrative Controls and Quality Assurance for Operations Phase of Nuclear Power Plants".
- Nine Mile Point Unit 2 (NMP-2)
Technical Specifications, Revision 0, October 31, 1986.
- NMP-2 Final Safety Analysis Report (FSAR) Chapter 14 " Initial Test Program".
- NMP-2 Safety Evaluation Report.
3.2 Overall Power Ascension Test Program The inspector held discussions with the Power Ascension Manager, (PAM) the Lead Startup Test Design and Analysis Engineer and other members of the PATP staff to determine the status of test results evaluations, test procedure reviews, and the overall readiness to begin low power testing.
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All open vessel (OV) testing is completed.
All OV test result packages are currently in the review cycle.
The licensee is continuing its review of test procedures for test condition heat up (TC-HU) through TC-6.
Presently, several procedures are being run on the plant simulator and revisions are being made as needed.
During discussions with the PAM concerning the progress of the test results review, he noted that some reviewers had commented on the documenting of reverification of test prerequisites following a hold in testing.
For most of the testing conducted to date, there are several signoffs for each of the prerequisite steps in the procedures.
The numerous signoffs could tend to make review of the test results difficult.
The PAM stated that a change to site administrative procedure AP-1.4,
"Startup Test Phase" allowing reverification of prerequisites following a
test hold to be documented only in the Shift Startup Test Log and not in the test procedure,was being considered.
The inspector informed the PAM that
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since the Shift Startup Test Log was not an official part of the test procedure, this would not be acceptable.
The PAM acknowledged the inspector's concern.
3.2 Power Ascension Test Procedure Review Scope The procedures of Attachment A were reviewed for the attributes identified in Inspection Report 50-410/86-38, Section 4.3.
Discussion The procedures reviewed were generally acceptable.
All of the procedures reviewed were new revisions of the procedures which reflect an ongoing licensee followup review of issued procedures for consistency with other issued operating procedures.
Findings No violations were identified.
3.3 Power Ascension Test Results Evaluation Scope The power ascension test results discussed below were evaluated for the attributes identified in Inspection Report 50-410/86-6.
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Discission-N2-SVT-13-0V Process Computer, completed December 10, 1986 This test successfully verified the proper functioning of the OD-1 computer program and the interface between the process computer and the traversing incore probe (TIP) system.
-N2-SUT-5-0V Control Rod Drive (CRD) System This start up test procedure includes friction, functional and scram time testing of all CRDs at a reactor pressure of 0 psig.
The inspector reviewed the preliminary test result package and independently evaluated CRD system performance as documented in this test.
All acceptance criteria were satisfied.
The maximum scram insertion time for each control rod was well within the acceptance
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criteria of 57.0 seconds. The inspector also reviewed the three test exceptions generated during testing, and noted that they had been properly dispositioned.
The test exceptions did not impact the acceptance criteria.
Findings i
Within the scope of the review, no violations were identified. All test acceptance criteria were satisfied.
None of the above test result packages had completed the review and approval cycle.
The results had not been reviewed by Quality Assurance or accepted by
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management. The completion of these reviews and approvals will be verified in a subsequent routine inspection.
4.0 Surveillance Test Activities Scope The inspector reviewed various surveillance activities of the Instrument-ation and Control and Operations Departments, as part of the continuing
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review of surveillance activities to support initial criticality and plant heat up.
Discussion The inspector reviewed the surveillance procedures listed in Attachment B to assess whether the surveillance procedures satisfied technical specifi-cation requirements to support initial criticality and plant heat up.
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addition, three licensee surveillance activities were monitored by the inspector to insure that technical specification surveillance requirements were being adequately met.
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The following surveillance tests were witnessed by the inspector:
N2-OSP-R05-Q001, SDV Vent and Drain Valve Operability Test.
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N2-0SP-DFR-0001, Drywell Floor Drain Valve Operability Test.
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N2-ISP-ISC-M004, Monthly Functional Test and Trip Calibration of ECCS
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Actuation on Rx Vessel Low Low Low, Level 1 and RCIC Actuation on Rx Vessel Low Low Level 2 and High Level 8.
Findings No violations were identified within the scope of this review.
5.0 Scram Discharge Volume Valves The inspector held discussions with a licensee representative concerning the failure of scram discharge volume (SDV) vent and drain valves (Hammel-Dahl) as discussed in IE Information Notice (IN) No. 86-62 dated September 16, 1986.
The valve failure was due to automatic actuation of the valve while the manual handwheel was partially engaged (off the neutral position).
The 2" SDV drain valve and the 1" SDV vent valve discussed in the Information Notice are both installed at NMP Unit 2.
The licensee representative informed the inspector that IN 86-62 had not yet been formally addressed at the site due to its recent issuance.
However, the representativa was in the process of addressing GE service information letter (SIL) 422 which informed GE customers of the potential for failure of the valve and the recommended actions. Action taken by the licensea thus far includes the addition of a note in both operator train-ing procedures and valve maintenance procedures stating that the hand-wheels of the valves are to be in the neutral position to prevent inadvertent engagement of the handwheel during automatic actuation of the valves.
Since IN 86-62 had not been formally addressed by the licensee, the inspector discussed with the licensee representative the additional infor-mation provided in the information notice.
Subsequent to the issuance of GE SIL 422, two operating plants experienced valve failures caused by partially engaged handwheels.
The inspector expressed the concern that possibly the actions recommended in the SIL were not sufficient.
The inspector informed the representative that to assure neutral position these plants provided lock wires to lock the manual handwheels in the neutral inspector' position.
The licensee representative acknowledged the s concern.
Findings No unacceptable conditions were identifie _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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6.0 QA/QC Interfaces The inspector reviewed two QA Surveillance Reports during this inspection.
One report covered the review of the test results package for power ascension test N2-SUT-02-0V, Radiation Measurements while the other covered the review of the test results for preoperational test N2-POT-85, Leak Detection System.
The inspector noted that each QA surveillance report included checklist's which detailed critical attributes to be manitored. All QA inspector concerns identified were adequately resolved.
Findings No unacceptable conditions were identified.
7.0 Independent Measurements and Verifications The inspector independently evaluated CRD system performance during results review of power ascension test N2-SVT-5-0V.
In addition, the inspector independently verified valve positions in the control room during witnessing of surveillance tests N2-OSP-RDS-Q001 and N2-0SP-DFR-Q001 as discussed in paragraph 4.0.
Findings No unacceptable conditions were identified.
8.0 Plant Tours and Meeting The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls and startup testing ' activities.
In addition, the inspector randomly attended the licensee s morning Startup Plan of the Day meeting during which the current status of testing activities and any holds or delays are discussed.
Other items such as remaining preoperational testing, surveillance, and outage activities are also discussed.
No unacceptable conditions were observed.
9.0 Exit Interview A management meeting was held at the conclusion of the inspection on December 12, 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 inspectio ___
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ATTACHMENT A Power Ascension Test Procedure Review N2-SUT-4-HU, Full Core Shutdown Margin Demonstration, Revision 1, SORC reviewed October 6, 1986.
N2-SVT-6-HU, SRM Performance, Revision 1, SORC reviewed October 20, 1986.
N2-SUT-10-HU, IRM Performance, Revision 1, SORC reviewed October 6, 1986.
N2-SUT-17-HU, System Expansion, Revision 1, SORC reviewed October 6, 1986.
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ATTACHMENT B N2-0SP-ADS-M001 ADS Manual Inhibit Functional Test, Revision 0, Final Surveillance performed November 21, 1986.
N2-0SP-CCP-Q001 RBCLC Water System Valve Operability Test, Revision 0, Final Surveillance performed October 23, 1986.
N2-0SP-GTS-Q001 SBGTS Valve Operability Test, Revision 0, Final Surveillance performed October 23, 1986.
N2-0SP-RCS-R004 Recirculation Flow control Valve Operability Test, Revision 1, Interim Surveillance perforrid September 25, 1986.
N2-ISP-ADS-M005 Monthly Functional Test of ADS Accumulator Backup Compressed Gas System Low Pressure Alarm Instrument Channels, Revision 0.
N2-ISP-CNS-M004 Monthly Functional Test of Suppression Pool Water Temperature Indication Channels 2 CMS * TE51B, 53B, 55B, 578, 59B, Revision 0, Final Surveillance approved October 25, 1986.
N2-ISP-CSH-M003 Monthly Functional Test of the HPCS Pump Discharge Flow Instrument Channels, Revision 1, Final Surveillance performed November 19, 1986.
N2-ISP-ICS-M007 Monthly Functional Test and Trip Unit Calibration of RCIC Suction Transfer on Condensate Storage Tank Level Low Instrument Channels, Revision 0, Final Surveillance performed November 26, 1986.
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