IR 05000443/1986037
| ML20212A110 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/21/1986 |
| From: | Eselgroth P, Nicholas H, Van Kessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212A108 | List: |
| References | |
| 50-443-86-37, NUDOCS 8607280116 | |
| Download: ML20212A110 (18) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
i Report No.
50-443/86-37 Docket No.
50-443 License No. CPPR-135 Category B
Licensee: Public Service of New Hampshire P.O. Box 330 Manchester, New Hampshire 03105 Facility Name:
Seabrook Station, Unit No. 1 Inspection At: Seabrook, New Hampshire Inspection Conducted: May 10-17 and June 9-13, 1986 Inspectors 7-2/~ %
H.
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,ReactprEngineer date j
7" Ef *5
. H. Nichol Startup Consultant date Approved by:
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7-2/~ ffd P' W. Esel ppf.h, Chief, Test Programs date Section,M, DRS Inspection Summary:
Inspection on May 10-17 and June 9-13, 1986 Report No. 50-443/86-37 Areas Inspected: Routine unannounced inspection of the Preoperational Test Program irciuding tFe test witnessing of preoperational tests, the review of preoperational test procedures, the evaluation of the test results, the independent verification of test measurements and the review of test exceptions and the results of retests. Unresolved items identified by the inspector in previous inspections were also reviewed.
Results: No violations were identified.
NOTE: For acronyms not defined, refer to NUREG-0544, " Handbook of Acronyms and Initialisms".
0 [ kogh 05000443 860722 PDR
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1.
Persons Contacted Public Service of New Hampshire
- S. H. Dunphy, Startup Technical Support Supervisor - STD (NHY)
R. W. Gregory, Licensing Engineer (UE&C)
- G. A. Kann, Test Group Manager (NHY)
G. Kingston, Compliance Manager (NHY)
- D. C. Lambert, Project Field QC Manager (UE&C)
- W. T. Middleton, QA Staff Engineer (YAEC)
- T. G. Pucko, Licensing Engineer (NHY)
- V. W. Sanchez, Site Licensing Supervisor (YAEC)
J. W. Singleton, Assistant QA Manager (YAEC)
A. Smith, Startup Engineer - STD (NHY)
S. Stasek, Licensing Engineer (NHY)
J. J. Warnock, Nuclear Quality Mana9er (NHY)
U.S. Nuclear Regulatory Commission
- R. S. Barkley, Resident Inspector
- A. C. Cerne, Senior Resident Inspector
- D. Ruscitto, Resident Inspector
- Denotes those present at exit interview on June 13, 1986.
2.
Licensee Actions on Previous Inspection Findings (Closed) Unresolved Item 50-443/86-01-01, " Test Exceptions reviewed in 50-443/86-01".
All of the open items have been closed with exception of:
Proc. No.
Title Test Exc.No./IILNo.
PT-17.2 Spent Fuel Cleanup 3/SF-0161 PT-5.1 CVCS Charging System 2/CS-1012 PT-14.2 Emergency Feedwater 3,4/FW-1270,1223 PT-40.7 Condenser Steam Dump 1,2,3/MS-1140,1320,1335 This item is hereby closed. The remaining test exceptions will be tracked under new unresolved item 50-443/86-37-01.
(Closed) Unresolved Item 50-443/86-13-01, " Test Exceptions reviewed in 50-443/86-13" All of the open items have been closed, with exception of:
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Proc. No.
Title Test Exc.No./IILNo.
PT-9 ECCS 5/SI-0666 PT-14.2 Emergency Feedwater 3,4/FW-1270,1223 PT-16.1 Primary Comp. Cooling Water 1/CC-1651 PT-40.1 Pressurizer Press, and Level 2,11/RC1752,1726 PT-40.7 Cond. Steam Dumps 1,2,3/MS-1140, 1320, 1335 AT-6.2 CW Transients 1/CW-223 AT-10.2 SG Sampling 1/SS0069 AT-10.3 Aux. Sampling 1/SS0067 AT-13.8 Transformer Fire Protection 1,2,3/FP-309,310,311 AT-66 125 VDC Non Vital Distr.
1/ED7-0083 This item is hereby closed.
The remaining test exceptions will be tracked under new unresolved item 50-443/86-37-01.
(Closed) Unresolved Item 50-443/86-17-01, " Test exceptions reviewed in 50-443/86-17" All of the open items have been closed with exception of:
Proc. No.
Title Test Exc.No./IILNo.
PT-27.1 Fuel Building HVAC 01/FAH-0199 PT-27.2 Fuel Building Exit Filter 07/FAH-0197 PT-38 ESF Actuation System 03,10,11/ML-0014, FW-1396, to PT-14.4 AT-19.2 S.G. Blowdown 05/ST-54 AT-19.3 S.G. Blowdown Recovery 03/SB0764 AT-33 Communications 01,11,18,19,20,23/ PAC-0099;
-78;-94;-95, -96; PAC-91; SPC-40;-41 This item is hereby closed.
The remaining test exceptions will be tracked under new unresolved item 50-443/86-37-01.
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(Closed) Unresolved Item 50-443/86-19-01, " Test Exceptions reviewed in 50-443/86-19" All of the open items have been closed with the exception of:
Proc. No.
Title Test Exc No./IIL No.
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PT-3.2 Piping Vibration Testing 01,02/N/A (Ebasco Report)
PT-31 125 VDC Distribution System 03,05/ED2E-0161, ED7E-0295
PT-26 Containment Air 01/CAH-0341
PT-37.2 Rx Containment, type B&C 01/N/A (B&C tests)
i tests PT 33.1 Emergency Diesel Generators 07/N/A (Fuel Cons.)
AT 59.1 Chlorination 02/CL-0111,0109 L
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This item is hereby closed.
The remaining test exceptions will be tracked under new Unresolved Item 50-443/86-37-01.
(Closed) Unresolved Item 50-443/84-05-01 (and 86-00-01), " Emergency Diesel Generator (EDG) - Engine overspeed trip due to design deficiency in air start system."
Scope During preoperational testing the diesel engine tripped on overspeed caused by inadequate venting of the air start system after startup of the EDG. This design deficiency was written up as a 10 CFR 50.55(e) report.
References
1.
Letter J. DeVincentis of PSNH to Region I office of the NRC, "10 CFR 50.55(e) Final Report: Deficiency in the Design of the Diesel Generator Air Start System (CDR-86-00-01)," dated March 31, 1986.
2.
Deficiency Report DR 82-335, issued 2-26-86 3.
Letter W. J. Cloutier of YAEC to J. Beall of NRC Region I, dated February 20, 1986.
Discussion
" Investigation of the problem indicated that the primary vent path, the starting air distributor, bled the fuel rack booster air pressure too slowly to prevent engine overspeed. This required the lube oil shuttle valve, a secondary vent path, to bleed residual booster air in order to prevent overspeed" (ref. 1). The EDG supplier, Colt Industries, revised the starting air design to vent booster air via the pilot air connection.
They also reset the Electric Governor (EG). The voltage gain of the EG control is now set higher than before.
The EG will now react more quickly and should reduce the chances for over-speed. The design modifications described above were completed for both EDGs. Both EDGs were retested and no overspeed tripping occurred.
The inspector witnessed automatic starts after the modification completion and observed no problems with the starting air system resulting in overspeed trips.
Findings This CDR is considered closed.
(Closed) Unresolved Item 50-443/85-26-02, " Operating Restrictions on Cooling Towers"
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Reference 1.
NRC Inspection Report 50-443/86-17 Scope The applicant was to perform an engineering evaluation of the Service Water System to determine if operating restrictions must be imposed on the cooling towers (the ultimate heat sink).
Discussion The engineering aspects of this problem have been reviewed earlier (Ref.1)
by the NRC. The final corrective action would consist of a general upgrad-ing of the Service Water Cooling Tower Operating Guide, which was issued in draft form on January 30, 1986 (Ref. 1). This upgrading was accomplished recently through the issue of the final version of the above referenced guide.
Findings The inspector has no further questions on this item.
(Closed) Unresolved Item 50-443/85-30-01, " problems with EFW Pump-Turbine Steam Supply Line (Water hammer), MSIV Bypasses, and Steam Dump Valves" Scope Since this item represents six independent problems on different systems the inspector decided to assign new open item numbers to the 6 items so that each item can be tracked independently.
Discussion The following 6 problems have been given new open item numbers:
85-30-11 Steam Dump Valve Problems 85-30-12 MSIV Problems 85-30-13 Water Hammer Problem in EFWP-Turbine Steam Supply Line 85-30-14 Air Operated Steam Supply Valve Problems (EFWP-Turbine Steam Supply)
85-30-15 EFW Recirculation Line Problem 85-30-16 EFW Pump Performance Problem
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l The status of all of these items was reviewed in inspection 50-443/86-19 t
l under the old open item number 85-30-01.
l The inspector agrees with the corrective actions taken by the licensee for all of the above open items.
Retesting, however, has to be
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accomplished for 5 of the 6 items. These items, therefore, cannot be closed until the retest has been completed successfully.
(Closed) Unresolved Item 50-443/86-13-02, " Emergency Diesel Generators
[EDG)LubeOilStrainerDesign"
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Scope The two Colt Pielstick diesel engines each have simplex, rather than duplex, lube oil strainers.
This item concerned the desirability of a duplex strainer arrangement from the standpoint of continuity of EDG standby power generation during plant emergency conditions.
Discussion The inspector opened this item in connection with discussions with licensee personnel about EDG lube oil strainer clogging problems that occurred elsewhere.
The inspector emphasized the potential safety j
significance of a clogged simplex strainer under emergency conditions.
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However, there is no explicit regulatory requirement for use of duplex lube oil strainers on the EDGs.
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Findings l
l This item is considered closed.
It is concluded that the licensee's ap-proach to the resolution of this technical issue did not exhibit conser-l vatism.
(Closed) Unresolved Item 50-443/86-13-03, " Unsatisfactory Hot Restart of EDG-A" l
Scope:
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During the performance of test PT-33.1 on February 17, 1986, the "A"
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Emergency Diesel Generator (EDG) failed to complete its hot restart sequence.
References 1.
Memorandum STD 86-246, G. A. Kann (NHY) to V. W. Sanchez (YAEC),
" Unsatisfactory Hot Restart of EDG-A" dated April 18, 1986 2.
Test Procedure Field Change No. 16 for Test No. PT-33.1, revision 1,
" Emergency Diesel Generators", JTG approval date: March 20, 1986, Implementation date: March 18, 1986.
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Discussion Investigation showed that contactor K1 did not close and, consequently, the generator field was not excited.
The contactor problem was corrected (ref.1) and the pertinent test steps of PT-33.1 (ref. 2) were repeated with success,
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Findings
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This item is considered closed.
(Closed) Unresolved Item 50-443/86-13-04, " Incorrect Schedule Terminology l
for Preoperational Retests" Scope i
The paperwork of some of the retests for preoperational tests showed that
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this work would be done during " power ascension".
This term implies that the work will be done after Initial Criticality. The test schedule, however, indicated that these tests were scheduled for the Post Core Hot Functional period which is before Initial Criticality (the correct schedule). The licensee agreed to correct the paperwork.
References 1.
Memorandum STO 86-247, G. A. Kann (NHY) to V. W. Sanchez (YAEC),
" Schedule Terminology for Retest", dated April 18, 1986.
Discussion Supplemental information was added to PT-3.3 and PT-40.1 to delete the expression "during power ascension" and replace it with " prior to initial criticality". Other preoperational tests have been reviewed and corrected as identified above (ref. 1). The inspector has no further questions on this item.
Findings This item is hereby closed.
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l 3.0 Preoperational Test Program 3.1 Test Procedure Reviews and Vertftcation s
Scope The test procedures listed in Attachment A were reviewed for i
technical and administrative adequacy and to verify that test
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planning satisfies regulatory guidance and licensee commitments.
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Discussio_n The procedures were examined for the attributes listed in paragraph 3.1 of Inspection Report No. 50-443/86-19.
Findings No noncompliances were identified by the inspector within the scope of this inspection.
3.2 Test Witnessing l
Emergency Diesel Generator Set Reliability Testing of EDG "B" Set References References are documented in Inspection Report 50-443/86-13.
Scope l
The objectives of the EDG set reliability tests are as follows:
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(1) To demonstrate that the EDG differential lockout relay prevents the diesel from starting.
(2)
T.) demonstrate the capability of the air start system as to capacity, minimum pressure and shutdown capabilities.
(3) To demonstrate capability of the EDG set to accept load after operating at no load by loading the diesel to at least 6100 KW within 120 seconds after operating at no load for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(4) To demonstrate EDG set reliability by performing 35 consecutive valid tests with no failures on each EDG set.
Discussion Test witnessing of EDG "B" set reliability testing by the inspector included observations of the attributes listed in paragraph 3.1 of Inspection Report No. 50-443/86-17.
Findings Test results observed by the inspector indicated that acceptance criteria had been met for the Emergency Diesel Generator Set Reliability Testing of the EDG "B" set. All alarms, interlocks, controls, setpoints and test results were verified to be in accor-dance with test criteria.
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No items of noncompliance were identified and no discrepancies were noted during this inspection. The inspector had no further questions at this time.
3.3 Test Result Evaluation Scope The test procedures listed in Attachment B were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform criteria were being applied for evaluating completed preoperational tests in order to assure their technical and administrative adequacy.
Discussion The test results were reviewed for the attributes listed in paragraph 3.3 of Inspection Report No. 50-443/86-19.
Findings No discrepancies or unacceptable conditions were noted in the review of these procedures with the following licensee identified test exceptions:
Proc Title Test Exception No:
PT-3.3 Power Conversion & ECCS Dynamic Test 1, 2 PT-15.3 Service Water Cooling Tower Performance 1, 2 PT-4.2 PWR Conversion & ECCS Thermal Expansion 1,2,3,4,7 Test PT-39.1 Loss of Offsite Power
PT-22.1 Containment Enclosure Ventilation
PT-38 ESF Integrated Actuation 3, 4, 6, 10, 11, 12 PT-36 Containment SIT
PT-37.1 Containment Type A Tests
PT-39.2 Loss of Offsite Power Test w/ESF Actuation 3,4,5,6,7,
AT-19.1 Steam Generator Blowdown Flash Tank 3, 4 AT-61 Screen Wash
AT-58.5 SW/CW Intake / Discharge Structure
and Pump House, Sump Pumps and Heaters AT-58.4 Misc. Sump Pumps and Heaters
AT-22 Containment Purge
AT-31 Seismic Monitoring 1, 2
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AT-19.1 Steam Generator Blowdown Flash Tank 3, 4 AT-61 Screen Wash
AT-58.5 SW/CW Intake / Discharge Structure
and Pump house, Sump Pumps and Heaters
AT-22 Centainment Purge
AT-31 Seismic Monitoring 1, 2 These open exceptions against completed tests will be reviewed on subsequent inspections for their resolution and closing. These open
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exceptions collectively are designated unresolved item
50-443/86-37-01. The inspector reviewed the licensee's current status of closed safety significant test exceptions and the schedule for closing the remaining safety significant test exceptions and found it to be satisfactory.
4.
New Fuel Receipt Inspection and Storage
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References References are documented in Inspection Report 50-443/86-13.
Scope The objective of this inspection was to ascertain whether nuclear fuel received at the construction site is properly accepted and safeguarded, and whether it is stored in accordance with the NRC license requirements.
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documentation, and the witnessing of the last shipment of fuel, from its arrival on site, to its storage area, and its final placement in the spent
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J fuel pool.
Discussion The inspector reviewed documents in the following areas pertaining to the
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receipt, inspection and storage of new fuel; such as Nuclear Materials
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License, Qualifications and Training, Fire Protection, Health Physics and Radiation Protection, Physical Security and Preoperational Testing.
The inspector witnessed inspection and storage of the last 11 fuel assemblies from removal from the shipping casks to storage in the new
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fuel storage area. The activities included radiation surveys of the
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outer metal casks; opening of the casks; initial survey of the two fuel assemblies in each cask; the removal and inspection of each fuel
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assembly; and final storage of each fuel assembly in the new fuel storage
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areas.
The inspector observed the use of fuel handling cranes, new fuel handling tools, personnel involved, procedures being used, HP monitors, l
and QC participation.
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11 The inspector also reviewed documentation and made observations, on a samp-ling basis, during this evaluation, in the areas of Administration, Physi-cal Security, Health Physics and Radiation Control, Reactor Engineering, Quality Assurance and Quality Control.
The inspector verified that receipt, inspection and storage, including doc-umentation, was accomplished in accordance with NRC license requirements.
The inspector also verified that all license requirements had been imple-mented for new fuel receipt inspection and storage as follows: security controls were exercised; implementation of health physics and radiation protection controls; control of the environment of the fuel storage area; verification of documentation; inspection of shipping casks; and, qualifi-cation of personnel involved in management and implementation of receipt, inspection and storage of nuclear fuel. The inspector witnessed the evolu-tions and verified documentation and proper use of procedures for fuel movement within the fuel building and fuel storage locations.
Findings:
No items of noncompliance were identified and no discrepancies were noted during these inspections. This completes the observations and witnessing of new fuel receipt, inspection and storage from the arrival on site, to its storage in the spent fuel pool.
The inspector had no further questions at this time.
5.
Unresolved Items Unresolved items are matters about which more information is required in order to determine whether they are acceptable, an item of noncompliance or a deviation.
The status of all unresolved items, open prior to this inspection, are listed in Attachment C together with the available response information from the licensee.
For the items closed during this inspection period please refer to Section 2 of this report.
No new Unresolved Items, other than those opened in Section 2 to facilitate tracking of former items have been opened in this report period.
6.
Exit Interview At the conclusion of the site inspection, on June 13, 1986, an exit inter-view was conducted with the licensee's senior site representatives (denoted in Section 1).
The findings were identified and previous inspection items were discussed.
At no time during this inspection was written material provided to the 11-censee by the insepctor. Based on the NRC Region I review of this report
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and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction }
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ATTACHMENTi to 50-443/86-37 Test Procedure Review
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Item No.
Proc. No.
Title Rev. No.
Appr. Data
PT-37.2A Containment Type'B & C Leakage Rate Tests
5/8/86
PT-22.3 RHR Vault Stairway
5/8/86 Ventilation
PT-15.5 Service Water Flow Balancing
4/23/86
PT-29 Emergency Switchgear
4/18/86 Ventilation
PT-14.4 EFW Valves Logic Verification 0 4/16/86
PT-12.3 RWST and SAT Draw Down Test
3/26/86
AT-61 Screen Wash System
4/30/86
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AT-22 Containment Purge Systems
4/4/86
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AT-58.1 Plant Drainage & 011
4/2/86 Separation System 011 Separation Vault I g
AT-58.2 Plant Drainags & 011
4/2/86 Separation System 011
Senarator Vault 2
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AT-58.3 Plant Drainage & 011
4/2/86
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Separation Syst.em Oil
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Separator Vault 3
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AT-33.1 10 Mile Radius Radio
4/16/86 l
Communication
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AT-33.2 Emergency Diesel Generator-
4/30/86 Reliability Tests
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ATTACHMENT B to 50-443/86-37 Test Results Evaluation Review Item No.
Proc. No.
Title Rev. No.
Appr. Data
PT-3.3 Power Conversion & ECCS
10/23/85 System Dynamic Test Test results approved:
3/26/86
PT-4.1 RCS Thermal Expansion
10/2/85 Test results approved:
3/28/86
PT-15.2 Service Water Pumps & Tower
4/23/86 Actuation Test results approved:
4/30/86
PT-15.3 Service Water Cooling Tower
10/25/85 Thermal Performance Tests results approved:
3/31/86
PT-15.4 Service Water System Cooling
8/14/85 HVAC Tower Tests results approved:
2/21/86
PT-4.2 Power Conversion & ECCS
9/30/85 Thermal Expansion Tests results approved:
3/26/86
PT-39.1 Loss of Offsite Power Tests
2/21/86 j
Tests results approved:
4/16/86
PT-30.2 UAT to RAT Transfer Verifica- 0 2/19/86 tion Tests results approved:
3/26/86
PT-22.1 Containment Enclosure
10/9/85 Ventilation System l
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Item No.
Proc. Nc.
Title Rev. No.
Appr. Data
PT-15.10 Service Water Pump Tests &
3/7/86 Auto-Start Tests results approved:
3/12/86
PT-38 ESF Integrated Leak Rate Test 1 1/29/86 Tests results approved:
2/26/86
PT-36 Primary Containment
3/12/86 Structural Integrity Test Tests results approved:
3/28/86
PT-37.1 Reactor Containment Integrated Leak Rate Test
3/7/86 Tests results approved:
3/28/86
PT-15.1 Service Water Cooling
4/23/86 Tower Tests results approved:
4/30/86
AT-50 PAB & Fuel Storage Bldg.
I 1/22/86 Hot Water Heating Tests results approved:
5/8/86
AT-49 EDG & Control Bldg. Hot
1/22/86 Water Heating Tests results approved:
4/9/86
AT-48 EFW Pumphouse Heating
3/5/86 Tests results approved:
4/2/86
AT-47 Control Bldg. Computer Room
9/25/85 Air Conditioning Tests results approved:
3/31/86
AT-46.2 Demin. Water, Safety Showers
10/23/84
& Eyewash Stations
Tests results approved:
4/2/86
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Item No.
Proc. No.
Title Rev. N3.
Appr. Data
AT-33.2 Radio Communications During
3/20/86 A Shutdown Tests results approved:
3/26/86
AT-22 Containment Purge Systems
4/4/86 Tests results approved:
4/23/86
AT-19.1 Steam Generator Blowdown
11/1/85 Flash Tank Tests results approved:
11/20/85
AT-61 Screen Wash System
4/30/86 Tests results approved:
5/8/86
AT-58.5 SW/CW-I, D Structure &
6/17/85 Pumphouse Pumps & Heaters Tests results approved:
4/16/86
AT-58.4 Misc. Sump Pumps & Unit
4/11/86 Heaters Tests results approved:
4/23/86
AT-58.3 Plant Drainage & Oil
4/2/86 Separation Vault 3 Tests results approved:
4/16/86
AT-58.2 Plant Drainage & 011
4/2/86 Separation - Vault 2 Tests results approved:
4/30/86
AT-58.1 Plant Drainege & Gil
4/2/05 Separation - Vault 1 Tests results approved:
4/30/86
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AT-57 Non-Essential Switchgear
3/21/86 Room Ventilation Tests results approved:
3/26/86
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Item No.
Proc. No.
Title Rev. No.
Appr. Data
AT-31 Seismic Monitoring
5/17/85 Tests results approved:
5/14/86
PT-15.11 Service Water Cooling Tower
2/26/86 Makeup Pump Tests results approved:
5/14/86
PT-39.2 Loss of Offsite Power With
3/24/86 ESF Actuation Tests results approved:
4/16/86
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r ATTACHMENT C Preoperational Test Program Summary of Open NRC Items Seabrook 1 50-443/86-37 OIL No.
Description RF?**
Remarks / Disposition 84-05-01 D/G Air Start Problems Yes Closed, 86-37 Same as 86-00-01 85-26-02 Licensee to Evaluate SWS Yes Closed, 86-37 Assume Oper. Guidelines OK now. Verify 85-30-01 Waterhammer in EFWPT Yes Closed, see new numbers Steam line + others below, 86-37 85-30-11 Steam Dump Valves Open,NCR82/924 - NCR82/973A 85-30-12 MSIV Bypass Valves Yes Open, valves to be retested after installation of new gears Gear ration 43.6 -
109/1's NCR 82-0009578 85-30-13 Waterhammer EFWP Yes Open, modified system to be Turbine - Steam Supply retested during ST-53 RFI-99/10988 85-30-14 Air Operated Steam Yes Closed *, 86-37
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i Supply Valves (EFW/MS)
NCR 82/967A 85-30-15 EFW Recirc. lines Yes Open, Modified lines to be retested. NCf4 82/994
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85-30-16 EFW Pump Performance Yes Open, Modified system to be Problems retested. NRC 82/993A 86-00-01 D/G Air Start System Yes Closed, 86-37 86-01-01 Test Exceptions N/A Closed *, Determined Status see summary listing 86-13-01 Test Exceptions N/A Closed,* 86-37 Determined status (see summary status)
86-13-02 Duplex 011 Filters Yes Closed, 86-37 EDGs L
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ATTACHMENT C Preoperational Test Program Summary of Open NRC Items Seabrook 1 (Cont'd)
50-443/86-37 OIL No.
Description RF?
Remarks / Disposition 86-13-03 Generator Field Flashing Yes Open Problem EDG 86-13-04 Incorrect Schedule Yes Closed, 86-37 Terminology Retest 86-17-01 Test Exceptions N/A C]; sed *, See Attachment.
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7, 86-37 86-19-01 Test Exceptions N/A Closed *, See Attachment:
C 86-37
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86-19-02 Omission of Signoffs in NO Open Completed Tests
- Remaining open TEs tracked under new Unresolved Items 50-443/86-37-01
- RF? - Response File available?
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