IR 05000423/1985027
| ML20133F710 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/21/1985 |
| From: | Bettenhausen L, Cheh U, Nicholas H, Van Kessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20133F682 | List: |
| References | |
| 50-423-85-27, NUDOCS 8508080399 | |
| Download: ML20133F710 (13) | |
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I U S. NUCLEAR REGULATORY COMMISSION
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REGION I
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Report No. 50-423/85-27
. Docket No.
50-423 l
License No..CPpR-113 Priority Category B
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' Licensee: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station Unit 3 Inspection At: Waterford, Connecticut Inspection Conducted:. June 3 - 7, 1985 Inspectors-A f) f 7-ff-8[
'H. H. Nlch s, Leap,ReactorEngineer date T/)
7*/f'E3 If. F. Tan sel, Rea EngTifeer date
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lf. Cheh, Rea r Engineer date l-Approved by:
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/8T L. H. B tienhausen, Chief, date Operation Branch, DRS t
l Inspection Summary:
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Inspection on June 3 - 7, 1985 (Inspection No. 50-423/85-27)
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Areas Inspected:
Routine t.nannounced inspection of the pre-operational test program including program implementation, emergency diesel generator status, proposed technical specifications status and review, test procedure review and verification, engineered safety features test status, pre-core hot functional test status; valves and valve problems; turbine building hot functional test status; containment HVAC status; witnessing of new fuel receipt inspection and storage; quality assurance and quality control interface; and, tours of the facility. The inspection involved 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> on s'ce by three NRC region-based inspectors.
Results:
No items of noncompliance were identified.
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PDR ADOCK 05000423 G
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DETAILS 1.0 Persogs Contacted Northeast Nuclear Energy Company (NNECO)
G. Bohn, Startup Engineer G.~Closius, QA-QC Supervisor
- J. Crockett, Superintendent Unit 3 A. Elms, Reactor Engineer E. Frieze, Startup Engineer M. Gentry,-
Assistant Startup Supervisor R. Grebasch, Startup Engineer N. Hulme, Startup Engineer K. Jensen, Reactor Engineer
- D. Miller Jr., Startup Manager J.-McConnell, Reactor Engineer D. McDaniel, Reactor Engineer M. Potkin, Startup Engineer W. Richter, Assistant Startup Supervisor W. Rose, QC Technician R. Sachatello, Startup Engineer A. Stengel, Startup Engineer S. Sudigala, Assistant Startup Supervisor P. Vasil, Startup Engineer Northeast Utilities Service Company (NUSCO)
D. Blumenthal, NQA Engineer R. Busch, Project Manager
- K. Gray, NQA Staff Assistant
- J. La Ware, Engineering Technologist
- L. Nadeau, AP Engineer
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Orifice, Project Engineer V. Popadopoli, 0QA Supervisor Stone and Webster Engineering Corporation (SWEC)
- W. Matejek, Project Advisory Engineer
- R. Scannell, QA Program Administrator
- W. Vos, Senior Engineer U. S. Nuclear Regulatory Commission (USNRC)
- R. Paolino, Lead Reactor Engineer,
- T. Rebelowski, Senior Resident Inspector
- denotes those present at exit interview on June 7,1985.
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2.0 Licensee Actions on Previous Inspection Findings 2.1 (0 pen) Unresolved Item, Valve Position Indication (VPI) Problems The valve Position Indication Problem Matrix, as previously described in inspection report 50-423/85-10, has been completed except for the systems which have not completed their phase-1 tests.
The inspectors urged the licensee to identify the potential VPI problem valves of the remaining systems and to expedite the engineering decisions on the individual VPI problems.
3.0 Preoperational Test Program References References for the preoperational test program are documented in inspection report number 423/85-05.
3.1 Test Program implementation Scope The inspector reviewed the licensee's implementation efforts in the areas of plant maintenance during pre-operational testing.
Discussion The inspector had discussions on corrective and preventive maintenance during pre-operational testing with the Operations Supervisor, the I&C Supervisor, and the Mechanical / Electrical Maintenance Supervisor. All of these personnel were familiar with the administrative controls covering the conduct of afore said maintenance. The licensee, recently, has developed a computerized program for plant maintenance.
It is called the Production Maintenance Management System (PMMS).
The PMMS tracks all maintenance activities.
It stores all salient maintenance information for the equipment including the frequency of preventive maintenance and the history file for such maintenance. Work orders for maintenance activ-ities are produced automatically by the computer program.
The inspector selected and reviewed a number of work orders for I&C, elec-trical and mechanical maintenance. The inspector verified that existing pre-opertional test results were not invalidated or that retesting was conducted, as appropriate.
The inspector reviewed the training records of personnel involved in the selected samples of maintenance activities and verified that these personnel were qualified to perform these maintenance activitie Jo
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The.PMMS maintains a history file for each plant component on its main-tenance.
The computer program can correlate this historical information for identical or similar plant components to produce generic failure type
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-listings.
The -inspector verified that the maintenance supervisors are aware of this ability of the PMMS to review the records for generic failure-implications.
The plant maintenance staff does all initial calibrations of instruments.
The equipment is turned over by construction without any calibration. The turnover packages, therefore, do not contain calibration records.
The initial calibration data fron plant maintenance become the baseline data for the PMMS historical filr on the equipment involved.
For the PMMS of mechanical equipment, there is a backlog on computer input activities. Much o' the maintenance work in this area is carried on manually prepared work orders to give the PMMS time to catch up.
The inspector verified that plant components subject to periodic replace-ment, on account of environmental qualification service time limits, are scheduled for such replacement via the PMMS. Automatic replacement orders will be printed out automatically by the PMMS computer program.
Findings No violations, deviations, or discrepancies were observed by the inspector in connection with the pre-operational test program implementation review within the areas examined.
3.2 Emergency Diesel Generator (EDG) Status Scope The final diesel runs for the EDGs are still waiting on the final fuel oil system flushing operations. The inspection was limited to the review and witnessing of the flushing operation.
Discussion The inspector examined the new filter housing cover for dirt in the casting cavity.
No particulate matter appeared to be present in the accessible area of the cavity. These new covers will be cleaned ultrasonically prior to installation.
The licensee plans to replace the entire fuel oil filter including the filter housing, filter cartridge, and filter internals.
Filter design improvements, as introduced by the manufacturer, and found by the inspector on the previous inspection, are detailed in inspection report 50-423/85-24. The Day Tanks were hand cleaned.
Very few micro size particles of foreign matter were foun.
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Flushing was' resumed. Analysis of the filter effluent showed all found l
particles to be declining in size and quantity. The analytical data revieyed by the inspector showed particle size to be below 25 micron.
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The licensee has already met the Vendor requirements but wants to set new, more stringent, acceptance criteria.
These criteria have not been set yet. After the completion of the fuel oil system flushing,.the licensee plans to resume the diesel test runs.
i The inspector received the exception list for the EDGs. This list iden-tifies the open work items of any kind, which must be completed prior to the ESF tests.
The schedule target start date for the ESF test presently is July 5, 1985.
Findings No violations or deviations were observed by the inspector within the scope of inspection as defined above.
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3.3 ' Technical Specifications The inspector discussed the review status of the proposed technical specifications with the licensee. The NRR review of the licensee's first draft, a marked up copy of the standard technical specifications, has been completed.
It should be available at the site at the end of the i
week of June 8,1985. The inspector received the licensee's listing of-
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open licensing items. This listing is a part of the Commitment Follow System.
3.4 Test Procedure Review and Verification Scope The test procedures listed in ATTACHMENT A were reviewed for technical and administrative adequacy and to verify that test planning satisfies regu-latory guidance and licensee' commitments.
Discussion The procedures were examined for management review and approval; procedure format; clarity of stated test objectives; prerequisites; environmental conditions; acceptance criteria; source of acceptance criteria; refer-ences; initial conditions; attainment of test objectives; test performance documentation and verification; degree of detail for test instructions; restoration of system to normal after testing; identification of test personnel; evaluation of test data; independent verification of critical steps or parameters; and, quality control and quality asjurance involve-ment. The review indicated that the procedures,
c?n!!istent with regulatory requirements, guidance, and with the licensee's coamitments.
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Fin' dings No discrepancies or unacceptable conditions were identified. The inspector had no further questions on these procedures.
3.5 Engineered Safety Features (ESF) Preparation Status Scope The inspector held discussions with cognizant startup engineers as to the status of preparations being made for the ESF test including procedures and prerequisites required to be completed in order to accomplish the test.
Discussion The test will be conducted in two parts; ESF without loss of normal power, and, ESF with loss of normal power.
The inspector received Revision 1 to the procedures titled, "3-INT-2003, ESF Without Loss of Normal Power", and "3-INT-2004, ESF With Loss of Normal Power", for review and comments. Discussions were held on meeting schedules, prerequisites and adequate coverage of test phases.
Findings No violations or deviations were identified. The inspector had no further
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questlons at this time.
3.6 Pre-Core Hot Functional Test (HFT) Preparation Status Scope The inspector followed up on this item with discussions of the status of preparations, procedures, and designated manpower for coverage of the pre-core hot functional test which will take approximately 3 weeks to conduct.
Discussion The inspector completed reviews of the controlling procedure as well as reviewing 25 of the sub section procedures to the test. There are 10 procedures that have not been received by NRC for review and comment.
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Findings No violations or deviations were identified. The inspector had no further questions at this time.
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4.0 Valve Problems Scope, More potential valve problems, other than those mentioned under section 2 above, have been identified. The inspector reviewed the information available and discussed this information with the licensee.
Discussions IE Information Notice 84-10 identified some problems with motor operated valves where the valve torque switches were set below the manufactures recommended value. These torque settings are important to assure proper valve closure or opening under static and dynamic fluid conditions. The licensee made a commitment (38400080) to address IN 84-10 for Millstone 3.
The inspector reviewed the actions taken by the licensee to meet this commitment.
In reference 4-1, the licensee responds to IN 84-10. This reference instructs maintenance to use FU form 524 to document switch settings in the "as found" and "as left" conditions with the acceptance criteria used.
In addition, a procedure is to be developed for use during surveillance / maintenance testing.
The licensee informed the inspector that each motor operated valve will be provided with a torque switch calibration level. The torque switch settings can be adjusted within a max./ min. band as set by the manufacturer.
If the valve operates p,roperly during the initial setting, the "as found" value becomes the "as left" value.
If the valve experiences problems during pre-operational testing, on account of the dynamic fluid conditions, the torque switches can be adjusted within the max./ min, band.
If settings outside of this band are required, the vendor will be contacted to obtain approvals.
The torque switch settings done to date have not been put into the PMMS (Production Maintenance Management System).
Fields are available in the Computer printout program for this information.
The licensee plans to use these fields but will not do so until Fuel Load time.
Some problems have been experienced at other sites with sheared pinion keys on limitorque SB-025 operators on Westinghouse EMD motor operated valves.
This is a vendor action item.
The vendor is to supply repair parts and instructions to fix the problem. The inspector inquired about the application of this type of Limitorque operator at Millstone 3 and whether or not the vendor has taken care of the problem. The Licensee indicated that they would look into it within the next three months.
The inspector indicated that this timing may not be compatible with the pre-operational test program schedule.
Findings No violations or deviations were observed by the inspector in connection with the review of the potential valve problems as identified above.
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References 4-1 Letter North East Utilities, NNEC 3-2304, "IE Information Notice No. 84-10:
Motor Operated valve torque switches set below the manufacture's recommend-ed value (CR 0484-10), dated June 1, 1984.
5.0 Turbine Building Hot Functional Test (HFT) Status Scope The inspector interviewed the cognizant licensee technical staff, reviewed the draft of Millstone Unit 3 Phase 2 Test Program No. 3-INT-2006 for the Turbine Building Hot Functional Test and made a tour of the TB Hot Functional Test Facilities.
Discussions The Carbon Steel Guide Shafts which were suspected to have rusted (E&DCR No. T-W-00022) on the INFILC0 DEGREMONT, INC. " TYPE F" Air operated valves were replaced with Stainless Steel Shafts.
It was due to carbon steel be-ing used in the valves. Otherwise, no physical work has been done since the previous inspection of 423/85-18, May 6-10, 1985. The TB Hot Function-al Procedures have gone through the Plant Operations Review Committee (PORC)
and the comments were incorporated. The Procedures are ready for approval by the Unit 3 Superintendent.
The procedures are expected to be released before June 10, 1985 and implemented for the scheduled TB Hot Functional Test presently scheduled for June 10, 1985.
Findings No violations or deviations were identified. The inspector had no further questions.
6.0 Containment HVAC Status References:
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Section 9, Millstone Unit 3 Final Safety Analysis Report (FSAR)
Amendment 4, September 1983 2.
Section 3 (3.6.1.5), Millstone Unit 3 Draft Tcchnical Specification Drawings:_
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Millstone Unit 3 P&ID 153 A-2, Containment Building 2.
Millstone Unit 3 P&ID 150 A-28, Turbine Building
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Procedures 1.
T3313B1E01, Containment Recirculation Fan Motors 3HVU-FNIA, 1B & 1C, Rev. 0, dated December 6, 1982
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Test Performed on May 28, 1985 and not yet approved.
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T3313F1E01, Containment Vacuum Pumps 3CVS-PIA & P1V, Rev. O dated December 6, 1982 Test Performed on June 4,1985.
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T331381M01, Containment Recirculation Fan 3HVU-FNIA, 1B & 1C, Rev. O dated December 6, 1982 Test Performed on June 1,1985, not yet approved.
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T3313E1M03, Containment Purge Damper and Valve, Rev. O, Test Performed on June 4, 1985, not yet approved.
Scope The inspector interviewed the cognizant licensee technical staff, reviewed the above-mentioned references, drawings, and procedures selectively, and observed the HVAC facilities and equipment for the Containnient Recirculation Air System, Control Rod Drive Mechanism (CRDM),
filters ano fans.
The inspector also witnessed the Air Balancing Test of the Containn.ent Air Recirculation System.
Discussion The inspector concluded that the test procedures are technically adequate and consistent with regulating requirements, guidance and licensee commit-ments. The tests were performed accordingly.
Findings No violations or deviations were identified, the inspector had no furhter questions.
7.0 New Fuel Receipt Inspection and Storage References References for the receipt of new fuel, its inspection and storage are documented in inspection report 423/85-14.
Scope The object of this inspection is to ascertain whether nuclear fuel received at the construction site, is properly accepted, safeguarded, inspected and stored in accordance with the NRC license requirement.
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Discussion The witnessing of fuel receipt was accomplished by the inspector and in-cluded the arrival of the transportation truck and unloading of fuel casks (14 new fuel assemblies) in the fuel building.
Documentation reviewed dur-ing this 'nspection included the security log; material transfer log; mate-rial accountability log; visitor control access list area authorization;
.. daily log of access and exposure control; radiation permit; shipping con-tainer receipt and inspection sheet; transportation fuel truck from West-inghouse Electric Company to Northeast Utilities. The 14 newly arrived fuel assemblies, plus 4 fuel assemblies from the preceding shipment, con-stitute a total of 18 fuel assemblies that have not been inspected or stored in the spent fuel pool because of problems with the spent fuel bridge crane loading monitor.
Finding No violations or deviations were identified.
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8.0 QA anu QC Interface S_E4ile The inspector interviewed the cognizant licensee QA/QC staff. The licensee has an independent audit program which includes test witness and test ve-rification for the Startup Program and is 'a member of JUMA (Joint utility ManagementAudit).
The inspector observed QA/QC inspector's work in pro-gress during the tours of the plant and reviewed the selected QA documents, as Itsted in Attachment B, since the previous inspection of 85-18/50-423, May 6-10, 1985.
Findings The inspector noted that QA/QC and the NUSC0/NNECO management continue to be actively involved in the test program.
No violations were identified.
9.0 Plant Tours The inspector made several tours of the facility including the control room, auxiliary building, containment, turbine building, service building, ESF l
building, control building, EDG rooms, fuel building, and circulating and service water pump house.
l Particular attention was given to the preparations being made for TB hot
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functional test, ESF test, pre-core HFT test, EDG set problers and resolu-l tion, and fuel.
Inspection also included observations of housekeeping, l
cleanliness and protection of components, piping and systems. No items l
of noncompliance were observed during these tours.
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ii 10.0 Exit Interview At the' conclusion of the site inspection, on June 7, 1985, an exit meeting
.was conducted with_the Licensees Senior Site representatives (denoted in
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Paragraph 1).
Previous inspection items were discussed.
At no time during this inspection was written material provided to the licensee by the inspecta,-_.
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i ATTACHMENT A TEST PROCEDURE REVIEW
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(1) 3-INT-3000, Appendix 3005, Approved February 11, 1985 Ventilation System Tests (2) 3-INT-3000, Appendix 3017, Approved June 3,1985 Reactor Coolant Loop Isolation Valves (3) 3-INT-3000, Appendix 3026, Draf t Copy Loose Parts Monitoring System (4) 3-INT-3000, Appendix 3037, Draft Copy RCS Heat Loss (5) T3303-P002 Revision 0, Draft Copy Polar Crane I
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i ATTACHMENT B QA/QC DOCUMENT REVIEW 1.
TC3615 Operations, New Fuel Handling dated May 29, 1985 and approved May 29, 1985.
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TC3624 Operations, New Fuel Handling dated May 31, 1985 and approved May 31, 1985.
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PC-3611 NNCEO Engineering, QC & Maintenance, J-Tube Replacement to replace chrome content.
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PC-3602 NUSCO, Instrumentation / Electrical EEQ dated May 20, 1985 and approved May 23, 1985.
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PC-3596 NNEC0, Tagging on Valves and Handles dated May 21, 1985 and approved May 22, 1985.
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PC-3573 NNECO, Electrical QA dated May 14, 1985 and approved May 17, 1985.
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PC-3573 NNEC0, Electrical QA dated May 14, 1985 and approved May 17, 1985, 8."
PC-3567 NNECO, Mechanical QA dated May 13, 1985 and approved May 14, 1985.
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TC-3540 Startup Engineering, New Fuel Handling dated April 29, 1985 and approved April 30, 1985.
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TC-3539 NNECO, Mechanical QA dated April 29, 1985 and approved April 30, 1985.
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