IR 05000289/1981001
| ML20004F396 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/02/1981 |
| From: | Fasano A, Haverkamp D, Rekito W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20004F392 | List: |
| References | |
| 50-289-81-01, 50-289-81-1, NUDOCS 8106180289 | |
| Download: ML20004F396 (11) | |
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U.S. NUCLEAF. REGULATORY COMMISSION g
0FFICE OF IN3PECTION AND ENFORCEMENT Region I
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l Report No. 50-289/81-01 j
t Docket No.
50-289 l
Category c
License No. DPR-50 Priority
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Licensee:
Metropolitan Edison Company
P.O. Box 480
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Middletown, Pennsylvania 17057 l
Facility Name: Three Mile Island Nuclear Station, Unit 1
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Inspection at: Middletown, Pennsylvania l
t Inspection conducted: January 1 - February 27, 1981 Inspectors:
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SY2*/k/
w D. R. Ha erkamp, Senior esi ent Inspector date ' signed
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<1 51 l
W. A. Re ito, Rea6 tor Inspector dat'e signed l
t/s./r/
l Approved by: // /
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'A. N. fasano, Chief, Three Mile Island Resident dath signed
Section, Projects Branch #2
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Inspection Sumary:
I Inspection on January 1 - February 27, 1981 (Report No. 50-289/81-01)
i Areas Inspected: Routine. inspectiort by resident and region-based inspectors (143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br />) of licensee action on previous inspection findings; plant
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operations including facility tours and record reviews; review of periodic l
(monthly) reports; licensee action on IE Circulars, surveillance of pipe
support and restraint systems; local leak rate testing; potential degradation of steam generator auxiliary feedwater nozzle thermal sleeve / collar weld attachments; and, potential problems with emergency diesel generator cooling i
system operations.
Results: No items of noncompliance were identified.
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i Details j
1.
Persons Contacted
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Metropolitan Edison Company
- B. Ballard, Manager, TMI Quality Assurance Mcdifications/ Operations I
R. Barley, Lead Mechanical Engineer, TMI-1 l
- J. Colitz, Plant Engineering Director, TMI-l
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- J. Fornicola, Supervisor Operations Quality Assurance t
- L. Harding,. Supervisor of Licensing, TMI-1
C. Hartman, Lead Electrical Engineer, TMI-1
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- H. Hukill, Vice President and Director, TMI-l l
- D. Mitchell, Licensing Engineer, TMI-l
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J. Pearce, Engineer, TMI-l M. Ross, Manager of Operations, TMI-l j
R. Sumers, Engineer, TMI-1 l
- R. Toole, Operations and Maintenance Director, TMI-l
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The inspector also interviewed several other licensee employees
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during the inspection. They included control room operators, i
maintenance personnel, engineering staff personnel and general
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office personnel.
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- denotes those present at the exit interview on February 27, 1981.
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2.
Licensee Action on Previous Inspection Findings
(Closed) Unresolved Item 289/79-06-01.: Operating Temperature i
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Effect on Hydraulic Snubber Functional Testing. The licensee j
issued Revision 1 to Surveillance Procedure 1303-9.9, " Functional i
Testing of Hydraulic Snubbers," which changed the acceptance l
criteria for lock-up velocity to account for the difference in
temperature between operating and testing conditions. This pro-l cedure change completes the licensee actions required for this item.
(0 pen) Unresolved Item 289/78-CI-06, (Closed) Unresolved Item f
289/78-17-01: Licensee Review of IE Circular 78-06, " Potential l
Connon Mode Flooding of ECCS Rooms."
Inspection Report 50-289/79-08, j
described the licensee's plans to establish a periodic preventive
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maintenance (PM) inspection for the back flow check valves located in emergency safeguards, equipment vault drain lines.. This PM l
procedure was scheduled for implementation by May 15, 1979, however,
the licensee has not yet developed the procedure. The licensee's
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representative confirmed that the planned actions remain unchanged l
but was unable to provide a revised estimate for PM procedure
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implementation. This item remains unresolved pending implementation l
of satisfactory action by the licensee. The item number is changed from 289/78-17-01 to 289/78-CI-06 for administrative tracking l
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purposes.
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t 3.
Review of Plant Operations
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Inspection tours of selected plant areas were conducted during the
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day shift.with respect to housekeeping and cleanliness, fire l
protection, radiological controls, physical security and plant
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protection, operation and maintenance administrative controls and
Technical Specification compliance. The areas toured included the
Auxiliary Building, Intemediate Building,. Emergency Diesel Generator l
Building, and the Turbine Building. The inspector regularly
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visited the Control Roon during normal work hours to observe
operations in progress, review logs and records and to conduct discussions with control room personnel. During these tours the inspector observed plant operations in the cold shutdown mode.
i During the afternoon shift on two days the inspector monitored
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system operations and equipment tests related to a Reactor Coolant
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System partial heatup' evolution. Acceptance criteria for the
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above inspection tours included requirements of Technical Specifications, f
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applicable regulatory guides and standards and approved licensee
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plans and procedures.
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The inspector frequently attended the licensee's Plan-of-the-Day (P00) meetings, held by licensee mr.nagement and supervisory personnel l
at-9:00 a.m., each Monday, Wednesday and Friday, to assess licensee
evaluation of plant conditions, status and problems and to review the licensee's plans for conducting certain major plant operations
and maintenance activities which require special department coordination i
and management review. The insoector also attended Construction j
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Status Meetings and Engineering Status Meetings to assess licensee
progress and difficulties related to plant modi fications required
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for restart.
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fio items of noncompliance were idt.n.ified during the review and observation of plant operations.
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4.
In-Office Review of Periodic Reports The inspector reviewed the periodic reports listed below, which
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were submitted to the NRC Region I Office, to verify that the (
report included information required to be reported and that test
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results and/or supporting information discussed in the report were
consistent with design predictions and perfomance specifications,
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as applicable. The reports were also reviewed to ascertain whetner
planned corrective action was adequate for resolution of identified l
problems, where applicable, and to determine whether any infomation t
contained in the report should be classified as an Abnormal Occurrence.
The following TMI-l periodic reports were reviewed.
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August Operating Report, dated September 15, 1980 f
September Operating Report, dated October 15, 1980
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October Operating Report, dated November 15, 1980 l
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November Operating Report, dated December 15, 1980
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December Operating Report, dated January 15, 1981 l
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The above reports were closed based on satisfactory in-office l
review.
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5.
IE Circular Followup I
i The inspector reviewed the licensee's actions regarding the IE
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Circulars (IEC) listed beicw.
l IEC 78-06, " Potential Comon Mode Flooding of ECCS Equipment
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Rooms", dated May 31, 1978
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IEC 78-18, "UL Fire Test", dated November 6,1978 I
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IEC 79-02, " Failure of 120 '! alt Vital AC Power Supplies",
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dated January 16, 1979 l
IEC 79-04, " Loose Locking Nut on Limitorque Valve Operators",
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dated March 16, 1979 l
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IEC 79-05, " Moisture Leakage in Stranded Wire Conductors",
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dated March 20, 1979
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i IEC 79-08, " Attempted Extortion - Low Enriched Uranium", dated
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May 18,1979
IEC 79-09, " Occurrences of Split or Punctured Regulator
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Diaphragms in Certain Self-Contained Breathing Apparatus",
dated June 22, 1979 y
IEC 79-10, "Pipefittings Manufactured from Unacceptable
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i Material", dated June 26, 1979 i
IEC 79-12, " Potential Diesel Generator Turbocharger Problem",
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dated June 28, 1979 j
l IEC 79-13, " Replacement of Diesel Fire Pump Starting Contactors",
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dated July 16, 1979
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IEC 79-15. " Bursting of High Pressure Hose and Malfunction of
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Relief Valve "0" Ring in Certain Self-Contained Breathing
Apparatus", dated August 8, 1979
IEC 79-17, " Contact Problem in SB-12 Switches on General
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Electric Metalclad Circuit Breakers", dated August 14, 1979 l
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IEC 79-18, " Proper Installation of Target Rock Safety % lief
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Valves", dated September 10, 1979
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IEC 79-19, " Loose Locking Devices on Ingersoll Rand Pumps",
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datert September 13,1979
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IEC 79-20, " Failure of GTE Sylvania Relay", dated September 24, 1979
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IEC 79-21, " Prevention of Unplanned Releases of Radioactivity",
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dated October 19, 1979 IEC 79-22,. " Stroke Times for Power Operated Relief Valves",
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dated November 16, 1979 IEC 79-23, " Motor Starters and Contactors Failed to Operate",
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dated November 26, 1979
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IEC 79-24, " Proper Installation and Calibration of Core Spray
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i Pipe Break Detection Equipment", dated November 26, 1979 IEC 79-25, "inock Arrestor Strut Assembly Interference", dated
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December 23, 1979 l
IEC 80-C'., " Service Advice for General Electric Induction Disc l
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Relays", dated January 17, 1980 IEC 80-02, " Nuclear Power Plant Staff Work Hours", dated
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February 1,1980 IEC 80-03, " Protection from Toxic Gas Hazards", dated March 6,1980
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IEC 80-04, " Securing of Threaded Locking De 'ces on Safety-
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Related Equipment", dated March 14, 1980 IEC 80-05, " Emergency Diesel-Generator Lubricating Oil Addition
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and Onsite Supply", dated April 1,1980 t
IEC 80-07, " Problems with HPCI Turbine Oil System", dated
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April 3,1980 IEC 80-09, " Plant Internal Connunications Systems", dated
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April 28,1980 l
IEC 80-10. " Failure to Maintain Environmental Qualification of
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Equipment," dated April 29, 1980
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I IEC EO-11, " Emergency Diesel Generator Lube Oil Cooler Failures",
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date1 May 13, 1980 IEC 80-12,," Valve Shaft-to-Actuator Key May Fall Out of Place
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When Mounted Below Horizontal Axis", dated May 14, 1980
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l IEC 80-13. "C.'d Strap Damage in Westinghouse Fuel Assemblies",
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i dated May 28, 1980 l
IEC 80-14, " Radioactive Contamination of Plant Demineralized I
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Water System and Resultant Internal Contamination of Personnel",
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dated June 24, 1980 IEC 80-15, " Loss of Reactor Coclant Pump Cooling and Natural
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. Circulation Cooldawn," dated ' June 20,.1980 IEC 80-16 "Op'eratior-1 Deficiencies in Rosemount Model 510 00
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Trip Units and Modei lidd Pressure Transmitters", dated June 27,1980 IEC 80-17, " Fuel Pin Damage Due to Water det from Baffle Plate
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Corner", dated July 23, 1980.
IEC 80-18, "10 CFR 50.59 Safety Evaluations for Changes to
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Radioactive Waste Treatnent Systems", dated August 22, 1980 IEC 80-21, " Regulation of Refueling Crews", dated September 10, 1980
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IEC 80-22, " Confirmation of Employee Qualifications", dated
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October 2, 1980 IEC 80-23 " Potential Defects in Beloit Power Systems Emergency
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Generators", dated October 31,* 1980 The review included discussions with licensee personnel, review of selected facility records, and observations of selected facility equipment and components.
The inspector verified that the circulars were received by appropriate licensee management, a review for applicability was perfonned, and that action taken or planned is appropriate.
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and facility procedures.
Licensee. followup to the above circulars was acceptable, unless otherwise noted below.
IEC 78-06 was reviewed by the NRC during two previous inspections.
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The licensee's planned actions are not yet implemented.
For more details, refer to unresolrad item 289/78-CI-06 described in paragraph 2 of this report.
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The licensee's onsite review of IEC 79-19, 79-21, and 79-22
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was not completed at the time of this inspection, however, the
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Onsite Safety Review Conmittee was aware of this needed i
review, assigned responsibility to the Plant Engineering
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Department and is tracking completion of them.
The Plant Engineering Director stated that the reviews would be completed
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by May 1, 1981. Completion of licensee review of these circulars for applicability and determination of appropriate
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action will be reviewed by the NRC during a subsequent inspection
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(289/79-CI-19; 289/79-CI-21; and, 289/79-CI-22).
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IEC 80-03, Protection from Toxic Gas Hazards was initially
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reviewed for applicability by the Onsite Plant Engineering i
Department but responsibility for review was then transferred to GPU Nuclear Technical Functions Division. The licensee representative stated that this review was still in progress i
i and was being done in conjunction with relatc.f matters of the TMI-l Restart Program. Licensee management is uce.cking conrietion of this activity under Task Record (TR)-MC-0127.
i Completion of licensee review for applicability and determination
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of appropriate action will be reviewed by the NRC during a i
subsequent inspection (289/80-CI-03).
l 6.
Surveillance of Pipe Support and Restraint Systems
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Review of Program and Proceddres
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j The inspector reviewed the following documents to determine l
whether the licensee's procedures and programs are technically i
adequate and are in confnrmance with Technical Specifications
and applicable regulations.
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SP 1303-9.9, Revision'1, " Functional Testing of Hydraulic
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SP 1301-9.9, Revision 11, " Hydraulic Shock and Sway
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Suppressors Visual Inspection"
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1410-Y-34,. Revision 2, " Repair of Hydraulic Snubbers"
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No inadequacies were identified dui :a; this review.
l b.
Review of Records The inspector reviewed the records for hydraulic snubber vis~ual inspections and functional tests performed during 1980 to ascertain that required inspection intervals and procedural requirements were met.
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r For each of the documented snubber deficiencies the inspector
t reviewed additional records to verify that proper corrective actions were taken; PORC conducted evaluations for possible NRC reporting requirements; and the resulting revised inspection interval met applicable Technical Specification requirements.
No problems. or unacceptable conditions.were identified during this review.
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Independent Observations.
The inspector toured accessible portions of the Auxiliary and Intermediate Buildings to obsarve the general con.dition of i
safety-related pipe supports and restraints.
During this tour
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the inspector performed independent measurements to verify the l
acceptable settings of selected snubbers and spring hanger i
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l No. unacceptable conditions were identified during these j
inspections.
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Functional Testing of Snubbers
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On January 28, 1981 the inspector examined five snubbers selected for functional testing and witnessed the testing for j
lock-up rate and bleed rate of Emergency Feedwater Snubber EF-74. This test was also witnessed by a site quality control
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inspector and documented in Quality Control Inspection Report PIR No. ME-00009-81. The test was performed in accordance l
with approved procedures, and the test te'chnician appeared to
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be suitably qualified to operate the snubber test machine.
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During this test the inspector questioned the observed practice
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of exercising the snubber three times and recording the average j
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of tha values obtained. The test technician explained that
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this practice was part of the fonnal training he had received
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but was not included as guidance in the procedure. After
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consulting with the snubber manufacturer technical.repre-i sentative the licensee (1) instructed the test technicians to l
record the first values obtained for lock-up and bleed rate as
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the official data and (2) revised procedure 1303-9.9 to provide l
additional guidance which allowed the test technician the
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option of repeating the test to confirm the initial values obtained. Based on the licensee actions described above, the
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inspector's concern for proper test performance was satisfied.
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No other unacceptable conditions were identified.
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I The inspector had no further questions on snubber functional
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testing.
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~ Local Leak Rate Testing (LLRT)
a.
Review of Program and Procedures The inspector reviewed.the following documents to detennine whether the licensee's procedures and program are technically adequate and are in conformance with Technical Specifications, applicable regulatory requirements and industry standards.
SP 1303-11.18, Revision 16 " Reactor Building (RB) Local
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Leak Rate Testing" SP 1303-11.23, Revision 1, "RB Local Leakage - Fluid
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alock System" SP 13b3-ll.24, Revision 0, "RB Local Leakage - Penetration
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Pressurization" i
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Summary Listing of LLRT results arid test schedule l
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As part of this review the inspector discussed the current i
status of the LLRT program with the licensee representative.
He stated his plan to determine a new Total Combined Leakage i
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Value by conducting all J.LRT's in the program prior to the next unit startup. In addition the licensee plans to conduct the next Integrated Leak Rate Test during the suniner of 1981.
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No problems or inadequacies were identified during this review.
b.
Test Performance On February 23 and 24,1981 the inspector observed various
portions of the LLRT for valves WDL-V303 and WOL-V304. The
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tests were performed i'n accordance with SP 1303-11.18 and the l
results appeared to be satisfactory.
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On a sampling bas'is the inspector verified that (1) test
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equipment was properly calibrated, (2) procedural requirements including preparations and precautions were performed properly, t
(3) systems were adequacely vented and drained, and (4) valve lineups were correct for conduct of the test.
In addition, the inspector interviewed the test technicians to i
ascertain their knowledge of test procedure requirements,
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amount of special training received and qualification possessed for doing these tests.
No problems or unacceptable conditions were identified during l
inspection of this activity.
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OTSG Auxiliary Nozzle Sleeve / Collar Weld Attachments By NRC letter dated. June 16,1980, the licensee was requested to provide certain information regarding analyses for possible degra-dation of the Steam Generator Auxiliary Feedwater Nozzle Thermal Sleeve / Collar Weld Attachments. The reason for.the request was based on a reported failure of the subject weld at another facility and.the manufacturers' generic evaluation of the potential problem.
The licensee responded to this request by letter to the NRC dated October 17, 1980. The inspector discussed this subject with the licensee and reviewed the information provided which included previous examination results with no indication of crackisg and future plans for exaniination of the subject welds.
No problems or unacceptable conditions were identified during this review.
9.
Emergency Ciesel Generztor Coolant System The inspector identifieo to the licensee a potential problem with Emergency Diesel Generator (EDG) operations, which was reported by
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a licensee having a similar EDG coolant system. The problem related
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to the adequacy of the engine coolant system design and meeting the manufacturers' reconnendations to perform seasonal changes based on ambient temperature ranges.
A review of Colt Industries Service Manual No. 3514 revealed the following two seasonal chang'e recommendations.
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The coolant medium should be an ethylene glycol solution for
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cold weather freeze protection and changed to treated water for additional heat dissipation during wann weather operations.
The cooling fan blade pitch (angle setting) must be dacreased
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during cold weather when increased density of air could result in overloading the fan drive shaft coupling.
In sunnary the manufacturers' reconnendations are:
Ambient Fan Blade Radiator /
Temperature Angle Setting System Solution l
l-20*F to 70*F 8-1/ 2*
Ethylene Glycol 70*F to 105*F 10-1/2*
Treated Water
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l The inspector noted that Operating Procedure 1107-3, " Diesel Generator", required the engine coolant system medium to be main-tained as an ethylene glycol solution for year round operation and
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that Maintenance Procedure 1405-3.2, " Diesel Engine Maintenance" included the manufacturers' reconinendations stated above. Based on
the apparent conflicting procedural instructions; and lack of knowledge l
for the current fan blade angle setting the inspector identified a (
concern for the integrity and continued safe operation of the j
EDG(s).
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The licensee subsequently infonned che inspector that there was no l
proc? dural. conflict, because MP 1405-3.7. was a corrective mainte-
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nance procedure to be used as necessary, and the subject recom-l mendations were not requirements. The licensee measured the l
current fan blade angle setting and found them to be a nominal
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eight degrees which could not jeopardize the integrity of the fan
drive shaft coupling.. The licensee reviewed the operating history
of the engine coolant outlet temperature and found the maxinrm l
experienced to be 164*F whicht is well below the coolant maximum
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temperature specification of 180*F.
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The licensee's actions and information provided. above along with l
the initiation of an engineering evaluation for applicability of,
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the subject manufacturers' reco::;nendations satisfied the inspectors j
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concern for assurance of safe operation of the EDG(s).
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No items of noncompliance or unacceptable conditions were identified.
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10. Exit Interv'ew_
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Meetings were held with senior facility management ' periodically
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during the course of the inspection to discuss the inspection scope
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and findings. The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on
February 27, 1981.
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