IR 05000320/1977017
| ML19220C281 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/27/1977 |
| From: | Caphton D, Markowski R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220C278 | List: |
| References | |
| 50-320-77-17, NUDOCS 7904300134 | |
| Download: ML19220C281 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No.
77-17 Docket No.
50-320 License No.
CPPR-66 Priority Category B
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Licensee:
Metropolitan Edison Company Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island 2 Inspection at:
Middletown, Pa.
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Mav 1213 Inspection conducted:
Inspectors:
R 5. M kcwsk, React'or Inspector date signed
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T. A. Retfelowski, Reagtor Inspector date' signed hh
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. Fasano ea y6p Inspectgf date si ned Approved by:
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U.'L. Capnton, Chief, Nuclear Support Section No. I cate sigried RO&NS Branch Insoection Sumary:
Inspecticn May 12-13,1977 (Recort No. 50-320/77-17)
Areas Inspected: Routine, unannouriced inspection of licensee action on previous inspection items; plant maintenance program implementation; witness of flushing operations; follow-up on IE Bulletins; preoperational procedure issuance completion; site tour. The inspection involved 64 inspector hours on site by four NRC inspectors.
Resul ts: Of the six areas inspected, no items of noncompliance were identified.
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Region I Fonn 12
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(Rev. April 77)
904300l'59
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DETAILS 1.
Persons Contocted The below supervisory and technical personnel were contacted:
- R. J. Toole, Test Superintendent, GPUSC
- J. E. Wright, Site QA Manager, GPUSC
- M. A. Nelson Technical Engineer, GPUSC
- R. Fenti, Lead QA Auditor, GPUSC T. Faulkner, Senior Technical Analyst, GPUSC D. Ryne. Maintenance Senior Engineer, UE&C R. Carlson, Electrical Instrumentation and Control Senior Engineer. UE&C H. Schiefer Electrical Senior Engineer, UE&C
- S. Levin, Project Engineer, GPUSC During the course of the inspection other engineering personnel were contacted.
Other Accomoanyina NRC Personnel D. L. Caphton, Chief, Nuclear Support Section No.1. Reactor Operations and Nuclear Support Branch (
- denotes attendees at exit interview.
2.
Licensee Action on Previous Inspection Items (Closed) Inspection Followup Item (320/77-10-05): Class B cleaning of Makeup System.
Review of VSP 147.9.1, Reactor Coolant System Cleaning Sequence, Rev. O, indicated that valve nozzle welds for 152A through D were checked for cleanliness.
(Closed) Inspector Followup Item (320/77-14-01): TP 200/4 (MTX 147.S)
Reactor Coolant System Hydrostatic Test was reviewed.
The inspector's concerns have been incorporated into the procedure.
(Closed) Inspector Followup Item (320/77-12-03): Stainless steel mirrors with extensions are to be used to examine weld areas to sfford detection of minor leaks by condensation fogging of the mirrored surface.
(Closed) Inspector Followup Item (320/77-10-03): The specified tests and inspections have been completed and documented in SP51.19 Enclosure I.
A four hour load test and final inspection will be conducted during TP401/l, Diesel Generator Functional Test.
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3.
Plant Maintenance Procram Imolementation a.
References (1)
a.
Field Change 100; completed 3/10/77 b.
Field Change Request 157 c.
Field Questioneer 1762 (2) Work Authorization No. 38 Control Rod Drive - Cable Connectors, May 7,1977 (3)
GPU letter to Ingersoll Rand, August 27, 1976 (TMI-2/2684)
b.
Review and Findinos Reference (1) involved the installation and calibration of an Intermediate Coolant System level control switch (IC-3-LS-1);
Reference (2) correction of the control cable connectors in the controlled drive system; Reference (3) circulating water pump impeller modification. Review of the above referenced documentation and questioning of the Maintenance, Electrical Instrumentation and Electrical Senior Engineers verified that:
(1) the maintenance activities were completed in accordance with established administrative controls; (2) supervisory (
personnel were familiar with the administrative controls covering the conduct of corrective and preventive maintenance during preoperational testing. The inspector had no further questions on this item at this time.
4.
Flush of Reactor Coolant Bleed Holdup Tank Piping a.
References (1)
Phase 1 Turnover Agreement (2)
Piping Exception List (3) QC-11-2, Rev. 2 Cleaning and Cleanliness Control (4)
QC-21-2, Rev. 2 Flushing of Piping Systens and Components (5)
TP 250/4 b.
Pre-Flush Review The above referenced documents were reviewed prior to witnessing the flush. No inadequacies were identified.
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Flush Witnessing a gravity flush of a run of piping from the On May 12,1977, The Reactor Coolant Bleed Holdup Tank Al to B1 was observed.
valve lineup was verified; members of the Quality Control staff were witnessing the conduct of flush; two flush bags were
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examined for evidence of particulate (nons was evident); a sample was drawn for analysis; applicable field data was entered on the data sheets.
No inadequacies were noted during the conduct of the flushing operation.
Pneumatic Time Delay Setpoint Drift (IE Bulletin 77-01)
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The Startup Group has received IE Bulletin 77-01.
An engineering evaluation and inspection has been instituted to determine the number This is an open item of relays installed in the diesel generators.
and will be reviewed at a subsequent inspection.
(320/77-17-01)
6.
Verification of Preoperational Procedure Issuance The following procedures remain to be issued to comply with the i
requirements of Regulatory Guide 1.68: TP 600/3, 600/10, 600/4, 600/20, 600/21, 600/13, 600/30 and 330/5. This item is open and will be reviewed at a subsequent inspection.
(320/77-17-02)
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Plant Tour The inspectors performed three general tours of the reactor..iding, auxiliary building, turbine building, diesel generator building and external areas. No problems were identified.
8.
Procedure Review a.
References TP 301/3A - Source Range Pre-Operational Calibration (1)
TP 301/3B - Intermediate Range Pre-Operational Calibration (2)
TP 301/3C - Power Range Pre-Operation Calibration (3)
TP 301/3D - Determination & Settings of Detector Voltages (4)
- Nuclear Instrumentation Detector Cabling and (5) TP 301/2 Response Checks TP 305/l A - Reactor Protection System Initial Power Operation (6)
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b.
Findings The above referenced procedures were reviewed for the following items: (1) management approval, (2) format, (3) prerequisites specified, (4) acceptance criteria, (5) provision for noting and correcting deficiencies, and (6) step-by-step instructions assuring that test objectives are met.
The inspector has no further questions on these items at this time.
9.
Diesel Piston Machinino Error Inspection (DRO Bulletin #74-16)
a.
Referer.ces (1)
DRO Bulletin No. 74-16, December 1974 (2)
Letter, Metropolitan Edison /JPO, January 3,1975 (3) SP 59.19, Diesel Generator Initial Operational Test, Enclosure 1.
b.
Findings The testing of piston inserts for machining errors was completed on May 11,1977. After pressurization of cylinders, dial indi-cator readings were less than.005".
This bulletin is closed.
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Exit Interview At the conclusion of the inspection the inspectors held a meeting (see Paragraph I for attendees) to discuss the inspection scope and findings. The unresolved items were identified.
The licensee stated his intent to use stainless steel mirrors to aid in identifying any leaks during the forthcoming reactor and piping hydro test.
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