IR 05000289/1979008
| ML19289F830 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/19/1979 |
| From: | Haverkamp D, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19289F829 | List: |
| References | |
| 50-289-79-08, 50-289-79-8, 50-320-79-07, 50-320-79-7, NUDOCS 7906200339 | |
| Preceding documents: |
|
| Download: ML19289F830 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF IflSPECTION AND ENFORCEMENT Region I 50-289/79-08 Report No.
50-320/79-07 50-289 Docket No.
50-320 DPR-50 C
Category _
C License No. DPR-73 Priority
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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:
fliddletown, Pennsylvania Inspection conducted: Mar h 19-23 and 26, 1979
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/7[79 Inspectors:
D.R.Haverkamp,ReacforInspector date signed date signed fj date signed
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Approved by:
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/h [79 R.vR. KeimignChief, ReacBor Projects Section No.
~'date digned
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1, RO&NT Branch fj Inspection Summary:
Inspection on March 19-23 and 26, 1979 (Combined Report Nos. 50-289/79-08 and 50-320/79-07)
Areas Insoected:
Routine, unannounced inspection of previous inspection findings (Unit 1); selected licensee events (Units 1 and 2); facility tour (Unit 1); and licensee followup to a prompt reportable occurrence identified during the inspec-tion (Unit 1).
The inspection involved 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> onsite for Unit 1 and 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> onsite for Unit 2 by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
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236 22 79o82oo nof Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Metropolitan Edison Comoany Mr. T. Acker, Unit 1 Shift Foreman Mr. R. Barley, Unit 1 Lead Mechanical Engineer Mr. M. Benson, Station Nuclear Engineer Mr. R. Bensel, Unit 2 Lead Electrical Engineer Mr. M. Bezilla, Unit 2 PORC Secretary Mr. J. Chwastyk.. Snift Supervisor Mr. R. Dubiel, fupervisor of Radiation Protection and Chemistry Mr. C. Hartman, Unit 1 Lead Electrical Engineer Mr. T. Hawkir.s, Unit 1 Maintenance Supervisor
- Mr. J. Logan, Unit 2 Superintendent Mr. T. Mackey, Supervisor of Quality Control fir. L. Noll, Unit 1 Shift Foreman Mr. V. Orlandi, Unit 1 Lead Instrumentation and Controls Engineer Mr. D. Pilsitz, Unit 1 Shift Foreman Mr. W. Potts, Unit 1 Superintendent - Technical Support Mr. M. Ross, Unit 1 Supervisor of Operations
- Mr. J. Seelinger, Unit 1 Superintendent Mr. M. Shatto, Unit 1 PORC Secretary
- Mr. R. Warren, Unit 2 Lead Mechanical Engineer Other Personnel Mr. T. Szymanski, Instructor, Career Management Branch, NRC Headquarters The inspector also interviewed several other licensee employees during the inspection.
They included control room operators, main-tenance personnel, engineering staff personnel and general office personnel.
- denotes those present at the exit interview on March 23, 1979.
- present at the exit interviews on March 23 and 26,1979.
2.
Licensee Action on Previous Inspec sn Findings (Unit 1)
(0 pen)
Unresolved Item 289/77-09-02: Adequacy of Snubber Visual Inspection Surveillance Procedure.
Licensee review and approval of the proposed PCR to SP 1301-9.9 is scheduled for completion by May 1, 1979.
A special tool has been manufactured to measure snubber piston positions for sufficient stroke to allow for ther-mal growth without hitting the mechanical stops.
This item re-mains unresolved pending revision of SP 1301-9.9.
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(0 pen) Unresolved Item 289/78-17-01:
Licensec 'eview of IE Circular 78-06 and IEC 78-07.
Licensee review or these circulars for applicability a 'd determination of appropriate action has been completed.
With respect to IEC 78-07, " Damaged Components on a Bergen-Patterson Series 25000 Hydraulic Test Stand," applicable test stand inspection requirements have been incorporated in SP 1303-9.9.
With respect to IEC 78-06, " Potential Conmon Mode Flooding of ECCS Rooms," a periodic preventive maintenance (PM)
inspection is planned for back flow check valves located in safe-guards equipment vaults drain lines. This item remains unresolved pending preparation and approval of the PM procedure, scheduled for completion by May 15, 1979.
(Closed)
Unresolved Item 289/78-14-01: Adequacy of Alarm Circuits to Monitor Operability of the Reictor Building Access Hatch Inter-locks.
New limit switches were installed during the current re-fueling outage, as documented by Work Request #24246 completed March 14, 1979.
The limit switches were located to provide proper monitoring of Reactor Building personnel and equipment hatch door interlocks.
The inspector had no further questions concerning this item.
(Closed)
Noncompliance 289/78-19-01: Administrative Controls for Operating and Surveillance Procedures.
The licensee's specific corrective actions were completed as described in MEC letter to NRC: Region I Serial GQL 2071, dated December 29, 1978.
The general corrective action included a complete audit by the Operations Engi-neer of the Control Room file of operating procedures.
Additional discrepancies were identified during that audit concerning noncon-formance with administrative procedural controls and were corrected by initiating about 35 procedure change requests.
Selected opera-ting procedures were reviewed by the inspector and were determined to contain appropriate revisions.
The inspector had no further questions concerning this item.
(Closed) Unresolved Item 289/78-19-04:
LER 78-27 Corrective Actions.
Change / Modification 1165 was approved to replace the core flood tank level transmitters with those of a different design.
Work associated with C/M 1165 was performed under Work Request #25057 during the current refueling outage.
C/M 1165 has been fully completed with the exception of final drawinga revisions.
The inspector had no further questions concerning this item.
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(Closed)
Unresolved Item 269/78-20-01:
SP 1302-5.13 Discrepan-cies.
SP 1302-5.13 has been superseded in its entirety by TCfl's
<E, 79-40 and 79-46.
The previous comments concerning SP 1302-5.13
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were no longer applicable.
The inspector had no further questions
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concerning this item.
(0 pen) Unresolved Item 239/78-20-03:
SP 1302-6 Discrepancies.
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Surveillance Procedure 1303-5.5, Revision 7, dated January 30, 1979, correctly identified six D/P instruments, used to perform surveillance of the Control Room Emergency Filters.
SP 1302-6,
" Calibration of tion Tech Spec Instruments Used for Tech Spec Compliance," Revision 1, included calibration requirements for four of the D/P instruments (DPI-698, -699, -700 and -701), but did not list calibration requirements for DPI-695 and DPI-696, due to an apparent oversight.
The referenced calibration procedure for the four listed filter D/P instruments, IC-76, provided for a multi-point check of the D/P indicators.
(The inspector detemined that all six D/P instruments had in fact recently been calibrated per IC-76).
SP 1302-6, Revision 1, also listed calibration require-ments for fire protection instrumentation used to comply with Tech Spec requirements.
The Unit 1 Lead Instrumentation and Centrols Engineer stated that SP 1302-6 would be further revised to include calibration require-ments for DPI-695 and DPI-696.
In addition, the method of sched-uling (by computer printout) and documenting completion of SP 1302-6 calibration requirements would be reviewed.
This item remains unresolved pending completion of these additional actions.
(Closed) Unresolved Item ?89/78-20-04:
Gage Calibration Scheduling.
Decay Heat Pump Flow Instruments DH-1-FI-l and DH-1-FI-2, Diesel Generators l A and IB Megawatt and Volt Meters and Control Room Emergency Ventilation Filter D/P Indicators were satisfactorily calibrated in January, 1979.
The inspector had no further ques-tions concerning this item.
(Closed) Unresolved Iten 289/78-20-05:
Thermocouple Calibrations.
SP 1302-14.1, Revision 5, dated March 1, 1979 incorporated changes which resolved the referenced concerns.
The inspector had no further questions concerning this item.
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3.
In-Office Review of Licensee Event Reports (LERs) (Units 1 and 2)
The LERs listed below were reviewed in the Region I office promotly following receipt to verify that details of the event were clearly reported including the accuracy of the description of cause and the adequacy of corrective action. The LERs were also reviewed to
'atennine whether further information was required from the licen-see, whether generic implications were involved, whether the event should be classified as an Abnormal Occurrence, whether the infor-mation involved with the event should be submitted to Licensing Boards, and whether the event warranted onsite followup.
The following Unit 1 LERs were reviewed.
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LER 79-03/3L, dated March 9, 1979 (High Pressure Injection Pump MU-P-lC tripped on overload during surveillance testing, due to a failed lead that connects sections of the motor in-ternal windings).
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LER 79-04/3L, dated March 14,1979 (Emergency Diesel EG-Y-1B tripped on overspeed during surveillance testing adjustedlinkagefollowinggovernorreolacement),duetomis-
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flonroutine 10 Day Environmental Report, dated February 26, 1979 (Measured level of tritiun in river water at stations 9A2 and 981 exceeded ten times the control station value, due to location and sampling methods).
The following Unit 2 LERs were reviewed.
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flPDES Noncompliance Notification 78-26, dated January 3,1979 (IWFS discharge pH of 9.1 exceeded perait limitations which allows a pH range of 6.0-9.0).
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LER 78-73/3L, dated January 15, 1979 (Containment atmosphere particulate radioactivity monitor air pump for HP-R-227 was seized, due to iccumulation of water in the sample lines).
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LER 78-74/3L, dated January 23, 1979 (Diesel Generator DF-X-1B did not start during surveillance testing, apparently due to petially clogged fuel oil filter).
- denotes those LERs selected for onsite followuo.
- denotes those environmental reports subject to generic and selective onsite followup during a subsequent environmental inspection.
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LER 79-01/3L, dated February 1,1979 (RB Pressure Hi-Hi Channel A monthly functional test was not performed when scheduled, due to technician error).
LER 79-02/3L, dated January 23, 1979 (Adequr.te documenta-
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tion was not retained to verify T.S. 3.^,. I turveillance per-fomance, due to personnel error).
LER 79-03/3L, dated February 2,1979 (Quadrant power tilt
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steady state and transient limits were exceeded when Control Rod #6-12 dropped irto the core, due to a blown fuse in the B phase).
LER 79-04/3L, dated February 2,1979 (Valve BS-V-iB position
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indication was inoperable due to a bent valve stem).
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LER 79-05/3L, dated February 2,1979 (Small crack in decay heat piping weld due to vibration).
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LER 79-06/3L, dated January 31, 1979 (Borated water source -
BWST - baron concentration surveillance was not performed when schewled, due to personnel error).
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LER 79-07/3L, dated February 26,19/9 (Travelling Water Screens were inoperable in Mode 5, due to significant build-up of debris causing a high differential level across the idle screen system).
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LER 79-08/3L, dated February 9,1979 (Setpoints of two feed-water line rupture detection pressure switches were outside allowable limits due to instrument drift or steam leakage).
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LER 79-09/3L, dated February 26,1979 (Boration system flow path verification surveillance was not performed in Mode 5 after the makeup pumps were tagged out, due to inadequate procedure).
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LER 79-10/lT, dated February 26, 1979 (Boron concentration for boric acid mix tank was in excess of the T.S. limit, and dppropriate Corrective action was not taken due to personnel error).
" denotes those LERs selected for onsite followup.
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The above LERs were closed based on satisfactory review in the Region I office, except those selected for onsite followup.
4.
Onsite Licensee Event Followuo (Units 1 and 23 For those LERs selected for onsite followup idenoted in Paragraph 3), the inspector verified that the reperting requirements of Technical Specifications 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 continued operation of the facility was conducted in conformance with Technical Specification limits.
The inspector's findings regarding these licensee events were acceptable, unless otherwise noted below.
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Unit 2 LER 78-74/3L described the failure of Diesel Generator DF-X-1B to start during surveillance testing.
The event cause was attriouted to be a partially clogged fuel oil filter, although the cause could not be positively determined. The corrective actions included changing the fuel oil filters, changing the air intake filter, and draining and refilling the fuel oil day tank. The LER did not fully describe the corrective actions taken. This LER will remain open pending additional review of corrective and preventive actions.
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Unit 2 LER 79-04/3L described the inoperability of Valve BS-V-IB due to a bent valve stem. The valve was temporarily repaired and returned to service by installing a spacer between the valve and the operator.
Perranent repair is scheduled under Work Request C-0647 and Change / Modification 2-0400, as tracked by PORC Action Item 2 79-010.
The permanent repair will include removal of the temporary spacer and replacement of the stem with a stem of improved material.
The inspector determined that BS-V-1B was an eight-inch Aloyco manufactured valve, and there are about 18 Aloyco valves of different sizes used in safety-related applications at the facility.
Licensee representatives stated that the need to reslace the stems of other Aloyco valves with improved stems, as a precautionary measure, would be evaluated. This iten is unresolved pending permanent repair of BS-V-1B, licensee evaluation of the need for additional generic corrective action, and submiss; :.1 of an Update LER.
(320/79-07-01)
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Unit 2 LER 79-05/3L described a small crack that had developed in a piping weld upstream of the B Decay Heat Pump discharge relief valve.
The crack was in the heat affected zone of the weld and was attributed to vibration.
The AE is evaluating if additional pipe hangers are required to reduce vibration, as tracked by PAI 2-79-011.
This item is unresolved pending completion of the AE's vibration evaluation, final PORC dis-position of long term corrective action and submission of an Update LER.
(320/79-07-02)
Unit 2 LER 79-10/1 T described the out-of-specification condi-
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tion of the boric acid mix tank and subsequent facility oper-ation in violation of Technical Specification 3.1.2.9 require-ments.
The inspector determined that appropriate immediate and long term corrective actions were taken, but not ade-quately described in the LER.
The report failed to identify the cause of high boron concentration and corrective action to restore the concentration to within specification.
Addi tien-ally, the basis for the conclusion that the event did not adversely affect health and safety was insufficiently described.
This item is unresolved pending submission of an Update LER that fully describes the event, cause and corrective actions.
(320/79-07-03)
5.
BWST Dome Damaae (Unit 1)
On March 19, 1979, the Unit 1 Borated Water Storage Tank (BWST)
dome was observed to be partially collapsed.
The center section of the dome had collapsed about 2-3 feet.
The olant was in cold shutdown for a scheduled refueling outage at the time of discovery of the BWST damage.
This event was determined to be prompt report-able by plant management on March 22, 1979, and the inspector was informed of the event description, apparent cause and planned cor-rective action.
Details of the event will be reported to Region I in the 14-day LER.
The inspector reviewed C/M 1309 (Work Request 0784) dated March 24, 1979, which requested acdification or replacement of the 24-inch manway cover on top of the BWST with a venting device.
The modif-ication was considered necessary to ensure that no significant vacuum is created when drawing down water from the tank.
The in-spector also reviewed MEC letter GEM 1607 dated March 23, 1979,
" Structural and Functional Adequacy of BWST," MEC letter GEM 1615 236 268
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dated March 23,1979, "BWST Atmospheric Vent," and other corres-pondence and documentation related to C/M 1309.
Additionally, the inspector observed work in progress on March 26, 1979, to modify the manway cover for continuous venting.
The inspector noted that the licensee's corrective actions concerning the BWST dome damage appeared acceptable and had nc further questions concerning this matter at this time.
6.
In-Office Review of Special Reports (Unit 2)
The special reports listed below were reviewed in the Region I office to verify i. hat the report included information required to be reported and that test results and/or supporting infomation 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 Abnorinal Occurrence.
The following TMI-2 special reports ware reviewed.
LER 78-65/99X dated January 30, !979 (ECCS actuation which
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occurred on November 7, 1978).
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LER 78-69/99X dated February 28, 1979 (ECCS actuation which occurred on December 2,1978).
The above reports were closed based on satisfactory review at the Region I office and previous review of the events during p ior inspections.
7.
Plant Tour (Unit 1)
At various times during the inspection, the inspector conducted tours of the Unit 1 auxiliary building, turbine building, and reactor building.
The tours were conducted to observe general hocsekeeping and cleanliness conditions and the readiness of systems / equipment for plant startup.
Findings were acceptable.
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8.
Unresolved Items (Unit 2)
Unresolved it;., are matters about which more information is required in order to a',cc.'tain whether they are acceptable items, items of nor. compliance, or deviations.
Unresolved items disclosed during this inspection are discussed in Parcgraph 4.
9.
Exit Interviews The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on March 23 and 26, 1979.
The inspector summarized the purpose and scope of che inspection and the findings.
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