IR 05000289/1979001
| ML19224A589 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/27/1979 |
| From: | Haverkamp D, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A588 | List: |
| References | |
| 50-289-79-01, 50-289-79-1, NUDOCS 7903150450 | |
| Download: ML19224A589 (13) | |
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U.S. NUC1. EAR REGULATORY CCMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
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Region I 50-289/79-01 Report No. 50-320/79-01 50-289 Docket No. 50-320 DPR-50 C
License No. DPR-73 Priority Category C
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Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19640 Facility Name:
Three Mile Island Nuclear Station, Units 1 and 2 Inspection at:
Middletown; oennsylvania and Reading, Pennsylvania Inspection conduuced:
. January 8-11, 1979 Inspectors:
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D. R. Haverkamp, Reactc[/ Inspector date signed date signed date sigred Approved b :
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. R. KeimIg, Chief, Reactor Projects Section
'ca te 'si gn'ed No.1, R0 & NS Branch Inspection Summary:
Inspection on January 8-11, 1979 (Combined Report Nos. 50-289/79-01' 50-320/79-01)
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Areas Insoected:
Routine, unannounced inspection by a reciorial based ini~pector of plant operations including aift logs and records and facility tour during normal hours (Unit 2); plan? operations during backshifu (Unit 2): selected licensee events and periodic reports ' Unit 2); and, licensee followup to IE Circular 78-08 and previous inspection findings (Units 1 and 2).
The inspection involved 4 inspector-hours onsite for UnitT,,16 inspectrr-hours onsite for Unit 2, and 8 inspector-hours at the corporate office by one NRC' regional based inspector.
Resul ts : No items of noncompliance were identified.
'O C.B Region I Form 12 7903150q50 (Rev. April 7'/)
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DETAILS 1.
Persons Contacted Metropolitan Edison Company - Three Mile Island Mr. R. Barley, Unit 1 Lead Mecharical Engineer
- Mr. M. Bezilla, Unit 2 PORC Secretary Mr. C. Hartman, Unit 1 Lead Electrical Engineer Mr. K. Hoyt, Unit 2 Shift Foreman
- Mr. G. Kunder, Unit 2 Superintendent - Technical Support Mr. J. Logan, Unit 2 Superintendent Mr. F. Scheimann, Jr., Unit 2 Shift Foreman Mr. M. Shatto, Unit 1 PORC Secretary Mr. B. Smith, Shift Supervisor Mr. W. Zewe, Shift Supervisor Metropolitan Edison Company - Corporate Office
- Mr. R. Harding, Unit 2 Lead Licensing Engineer
- Mr. G. Treffer, Manager - Generation Quality Assurance The inspector also interviewed several other licensee employees during the inspection.
Thev included control room operators, licensing and engineering staff personnel, and general office personnel.
- denotes those present at the exit interview onsite on January 10, 1978.
- denotes those present at the exit' interview at the corporate office on January 11,19i.
2.
Licensee Action on Previous Inspection Findinos (Units 1 and n (Closea) Inspector Followup lten 209/78-13-01-
.ER 78-08/lT Corrective Action.
The plant continues to operate with a low water level in the OTSGs when at low power levels.
Various options which would a? low flooded OTSG nozzel startup operations are being considered by the licensee.
However, such operation will not be perfomed without NRC/NRR approval.
The inspector had no further questions concerning this item.
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(Closed) Unresolved Item 28b/78-19-02:
LER 78-24/lT Corrective Action.
Temporary Change Notices78-261 through 78-267 have been issued to incorporate revised heatup/cooldown limits in applicable operating procedures.
TSCR #88, dated January 4, 1979, has been submitted to NRC/NRR to revise applicable Tech-nical Specifications.
The inspector had no further questions concerning this 1 tem.
(Closed) Unresolved Item 289/78-19-03:
LER 78-25/lT Corrective Actions.
TCN 78-269 was issued to SAP 1002 to ensure proper selection and testing of backup E.S. equipment, when taking emergency safeguards components out-of-service.
Permanent revision of SAP 1002 is in progress.
The inspector had no fur-ther c;uestions concerning this item.
(Closed) Unresolved Item 289/78-19-05:
Licensee Review of IE Circular 78-16.
IEC 78-16 has been reviewed by PORC and Gener-at; n Engineering - Electrical Section.
The plant has some Limitorque valves of the type described, however, manual operation is infrequent.
Present procedural guidance for valve operation and maintenance is considered adequate.
Vendor comments concern-ing proper valve operation were sent to the training department for discussion in the operator requalification program.
The inspector had no further questions concerning this item.
(Closed) Unresolved Item 320/78-29-06:
Licensee Review of IE Circular 78-08.
Licensee review of environmental qualification of safety-related electrical equipment has been completed, as described in paragraph 3 of this report.
The inspectcr had no further questions concerning this item.
(Closed) Noncompliance 320/78-32-04 and Unresolved Item 320/78-32-05: Administrative Controls for Jumpers and Lifted I eads.
A licensee audit of jumpers and lifted leads has been completed.
No further examples of improper administrative control of these items were noted by the inspector.
SAP 1013 does not require revision to require more stringent controls or to include specific controls for gagging devices at this time.
The inspector had no further questions concerning these items.
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(Closed) Unresolved Item 320/78-36-08:
Environmertal Qualification Testing of NAMCO - Type SMLSs.
NAMC0-type stem mounted limit switches, used for position indication of R.B. purge supply and exhaust valves, were tested for environmental qualification, as described in paragraph 3 of this report.
The inspector had no further questions concerning this item.
3.
IE Circular 78-08 Followup (Units 1 and 2)
The inspector reviewed the licensee's followup actions regarding IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Equipment at Nuclear ?. ier Plants," c ated May 31, 1978.
The review included discussions with licensee personnel and review of the following selected records at the corporate office.
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Generation Division Service Requests 780260, 780261, 780292, and 780302 (used to assign responsibility for review of IE Circular 78-08 and referenced material)
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Electrical Connector /Panetration Concern Summary (Licensee drafted)
Union of Concerned Scientists Summary (Licensee drafted)
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Summary of IE Circular 78-08 Review (Licensee drafted)
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Metropolitan Edison Company (MEC) memorandum serial GEM v258, dated November 13,1978 (list of electrical compo-nents located iriside containment which are required to function following a LOCA/ steam line break at Tf1I-1)
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Burns and Roe, Inc. letter to MEC serial 4301-GP, dated November 9,1978 (TMI-2 electrical equipment environmental qualification)
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MEC memorandum serial GQM 5162, dated November 8,1978 (verification of no failures of electrical components lccated inside containment at TMI-l and TMI-2 as a result of adverse environmental conditio..s)
MEC memorandum serial GEM 5147, dated November 7, 1978
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(description of engineering review and verification that installed safety-related electrical equipment at IMI-l is environmentally a.alified)
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GPU/ Burns and Roe documentation sent to MEC (Review of TMI-2
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safaty-related electrical equipment in relation to IE Circular 78-03 concerns)
Speci fication 2555-100, Containment Purge Isolation Butter-
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fly Valves me MEC memorandum serial GQM 5619, dated December 5,1978 (Field
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verification of electrical components installed at TMI-1)
Selected documentation of TMI-2 component changes / modifications
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to provide environmentally qualified electrical equipment Selected environmental qualification test report data for
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electrical components installed at TMI-1 and TMI-2 The inspection. purpose, scooe and acceptance criteria renardina licensee followup to IEC 78-08 were as described in OIE Inspection Report No. 50-320/78-29, paragraph 8.
Findings were acceptable, except as described below.
Field verification of electrical components installed at
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TMI-l has not yet been completed. MEC memorandum GQM 5619 states that such verification is to be performed by MEC QC personnel during the 1979 refueling outage commencing in mi d-Fe brua ry.
The QC surveillance report is scheduled to be published by April 1, 1979.
This item is unresolved, pending NRC review of the TMI-l field verification (289/
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79-01-01).
4.
Review of Plant Operations (Unit 2)
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Shift Logs and Operating Records The inspector reviewed the following logs i records.
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Shift Foremen Log, Control Room Log Bock, Control Room Operator's Log Sheets, Primary Auxiliary Operator's Log-Tour Readings, Primary Auxiliary Operator's Log-Liquid Waste Disposal Panels, Secondary Auxiliary Operator'r Log Sheets, and Auxiliary Operator Log Sheets-Out-Building Tour, dated October 16 - December 31, 1978.
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Shift and Daily Checks, dated October 16 - December 31, 1978.
Jumper, Lifted Lead, and Mechanical Modifications Logs
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(active and cleared); entries made during October 16 -
December 31, 1978, and selected active entries.
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Fire System Removal from Service Notification Log; entries made during October 16 - December 31, 1978.
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Applications for Apparatus to be Taken Out of Service; those active on January 10, 1979 and those cleared, dated December 28, 1978 - January 9,1979.
Do Not Operate and Caution Tag Logs; entries made during
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October 16 - December 31, 1978.
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Transient Cycle Log Book; entries made during October 16 - December 31, 1978.
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Unit 2 Operations Department Memos 2-78-17 through ?-78-25.
The logs and records were reviewed to verify the following i ter.s.
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Logkeeping practices and log book reviews are conducted in accordance with established administrative controls.
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Log entries involving abnornal conditions are sufficiently detailed.
Operating orders do not conflict with Technical Specifi-
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cations (TSs).
Jumper Log and tagging log entries do not conflict with
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TSs.
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Jumper / lifted lead / mechanical modification and tagging operations are conducted in conformance with established administrative controls.
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Problem identification reports confirm compliance with TS reporting and LC0 requirements.
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Acceptance criteria for the above review included inspector judgment and requirements of applicable Technical Specifications and the following procedures.
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Station Administrative Procedure (SAP) 1002, " Rules for the Protection of Employees Working on Electrical and Mechanical Apparatus," Revision 13.
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SAP 1010, " Technical Specification Surveillance Program,"
Revision 12, TCN 2-78-736.
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SAP 1011, " Controlled Key Locker Control," Revision 16.
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SAP 1012, " Shift Relief and Log Entries," Revision 8.
SAP 1013, " Bypass of Safety Functions and Jumper Control,"
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Revision 7.
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SAP 1016, " Operations Surveillance Program," Revision 12.
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SAP 1033, " Operating Memos and Standing Orders," Original.
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SAP 1037, " Control of Caution and DN0 Tags," Revision 1.
No items of noncompliance were identified.
b.
Plant Tour Upon arrival at the site at 6:45 a.m. on January 8,1979, the inspector proceeded directly to the Unit 2 Control Room to observe plant operations during off-normal hcurs.
Control Room manning and control board monitoring instrumentation and equipment were observed for conformance with applicable Technical Specification requirements.
The inspector then conducted a tour of the Unit 2 Auxiliary Building to check for general cleanliness and housekeeping conditions, potential fire hazards and adequacy of radiation controls.
The tour was completed at 8:45 a.m.
Findings were acceptable.
At various times on January 9-10, 1979, the inspector conducted tours of the following accessible plant areas.
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Auxiliary Building
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Turbine Building-3 353
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Control and Service Building
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Control Room
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Switchgear Rooms
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Inverter and Battery Rooms Makeup Pump Rooms
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The following observations / discussions / determinations were made.
Control Room and local monitoring instrumentation for
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various components and parameters was observed.
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Radiation controls established by the licensee, including the posting of radiation and high radiation areas, the condition of s'tep-off pads, and the disposal of protective clothing, were observed.
Radiation Work Permits used for entry to radiation and controlled areas were reviewed.
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Plant housekeeping, including general cleanliness conditions and storage of materials and components to prevent safety and fire hazards, were observed.
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Systems and equipment in all areas toured were observed for the existence of fl Jid le.aks and abnormal piping vibrations.
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Selected piping snubbers / restraints were observed for proper fluid level and condition / proper hanger settings.
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The indicated positions of electrical power supply breakers and selected control board equipment start switches and remote-operated valves and the actual positions of selected manual-operated valves were observed.
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Selected equipment lockout tags, caution tags, and
' -Not-0perate tags were observed for proper posting
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L.id the tagged equipment was observed for proper positioning, where applicable.
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Selected jumper and lifted lead markers were observed for proper identification and the effected wiring changes were observed for proper completion.
The Control Board was observed for annunciators that nor-
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mally should not be lighted during the existing plant conditions.
The reasons for the annunciators were discussed with control room operators.
The licensee's policy and practice regarding plant tours
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were reviewed.
Control Room manning wa: observed on several occasions
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during the inspection.
Acceptance criteria for the above items included inspector judgment and requirements of 10 CFR 50.54(k), Regulatory Guide 1.114, applicable Technical Specifications, and the following procedures.
SAP 1002, " Rules for the Protection of Employees Working
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on Electrical and Mechanical Apparatus," Revision 13.
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SAP 1003, " Radiation Protection Manual," Revision 12.
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SAP 1008, " Good Housekeeping." Revision 4.
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SAP 1009, " Stat lon Organization and Chain of Command,"
Revision 3.
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SAP 1028, " Operator at the Controls," Original.
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SAP 1037, " Control of Caution and DN0 Tags," Revision 1.
SAP 1034, " Control of Combur.tible Materials," Original.
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No items of noncompliance were identified.
5.
In-Office Review of Licensee Event Reports (LERs) (Unit 2)
The LERs listed below were reviewed in the Region I office promptly following receipt to verify that details of the event were clearly rerorted including the accuracy of the description of cause and the adequacy of corrective action.
The LERs were also reviewed to deter-mine whether further information was required from the licensee, whether generic implications were involved, whether the event should be classified as an Abnormal Occurrence, whether the information involved with the event should be submitted to Licensing Boards, and whether the event warranted onsite followup.
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The following LERs were reviewed.
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LER 78-60/3L, dated October 13,1978 (R.B. pressure switch BS-PS-3987 was.01 psig greater than the allowable setpoint of 3.60 psig, due to setpoint drift)
LER 78-61/3L, dated November 1,1978 (while performing pseudo
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dropped rod test, the nuclear overpower trip setpoint was not verified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to using special test exception of Technical Specifications)
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LER 78-62/lT, dated October 19,1978 (Technical Specification limit fnr RCS unidentified leakage was exceeded without shut-down of unit due to misinterpretation of Technical Specification requirements)
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LER 78-63/3L, dated November 28,1978 (ratchet trip of Group
.ntrol rods during normal shutdown due to incorrectly installed vendor-supplied field change in three gate drive modules)
LER 78-64/3L, dated December 4,1978 (during a calibration check
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of the BWST level switches, the switches exceeded the setpoint allowed by Technical Specifications)
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LER 78-66/3L, dated November 15, 1978 (while in Mode 3 the C.R.D. trip breakers were closed on three occasions with only one source range detector operable)
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LER 78-67/3L, dated December 11,1978 (during load service testir:g, fuses blew in battery chargers 2-2A and 2-28 due to defective gating and filter modules, which resulted in loss of the chargers for Battery Bank B)
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LER 78-68/3L, dated De. ember 13,1978 (twelve diesel generator load sequence setpoints were cutside the Technical Specification tolerance due to setonint drift)
LER 78-70/3L, dated December 23. '978 (intermediate range
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neutron flux and rat, functional surveillance was not performed during heatup prior to cloHng C.R.D. breakers, due to procedtral inadequacy)
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- denotes those LERs selected for onsite followup
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LER 78-71/li, dated December 21, 1978 (make-up pump control logic allowed starting of two pumps from a single diesel generator, due to design deficiency)
LER 78-72/3L, dated January 2,1979 (four R.B. icolation
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valves failed to close during surveillance testing, due to an inoperable logic relay)
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NPDES Permit 0009920 Noncompliance Notifications 78-22, 78-23, and 78-25 (IWFS aischarge of pH limits exceeded)
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NPDES Permit 0009920 IWTS Bypass Notification, dated November 3, 1978 The above LERs were closed based on satisfactory review in the Region I office, except those LERs selected for onsite followup.
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Onsite Licensee Event Followup (Unit 2)
For those '.ERs selected for onsite followup (denoted in paragraph 5), the inapector verified that the reporting requirements of Technical 1pecifications and GP 4703 (Original) had been met, that appropriate corrective action has been taken, that the event was reviewed by the licensee as required by Technical Specifications, and that coi tinued operation of the facility was conducted in conformance vith Technical pecification limits.
The inspecto s firidings regarding these licensee events were acceptable, unless otherwise noted below.
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LER 78-67/3L described the inoperability of Battery Chargers 2-2A and 2-28, due to blown fuses which occurred during load service testing surveillance.
Two defective gating and filter modules were identified and replaced.
The licensee will evaluate the need for additional corrective action, pending review of the vendor's examination results of the defective modules.
This item is unresolved, pending NRC review of additional licensee corrective actions (320/79-01-01).
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LER 78-68/3L described the out-of-specification condition of 12 diesel generator load sequence timers, attributed to possible setpoint drift.
Future corrective action to prevent recurrence is still being investigated by the licensee, as tracked by PAI 2-78-057.
This item is unresolved, pending NRC review of additional licensee corrective action (320/79-01-02).
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- denotes those LERs selected for onsite follcwup
- denoted those environmental reports subject to generic and selective onsite followup durirg a subsequent environmental inspection
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7.
In-0ffice Review of Periodic Reports The periodic reports listed below were reviewed in the Region I cffice to verify that the report included information required to be reported and that test results and/or supporting information discussed in the report were consistent with design predictions and performance specifications, as applicable.
The reports were also reviewed to ascertain whether planned corrective action was adequate for resolution of identified problems, where applicable, and to determine whether any information contained in the report should be classified as an Abnormal Occurrence.
The following TMI-2 periodic reports were reviewed.
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October Operating Report, dated November 15, 1978
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November Operating Report, dated December 15, 1978 The above reports were closed base.d on satisfactory review at the Region I office.
8.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items disclosed durino this inspection are discussed in Paragraphs 3 and 6.
9.
Exit Interviews The inspector met with the licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on January 10 and 11,
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The inspector summarized the purpose and scope of the inspec-tion and the findings.
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