IR 05000320/1978014
| ML19220A792 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/17/1978 |
| From: | Caphton D, Hurd R, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220A785 | List: |
| References | |
| 50-320-78-14, NUDOCS 7904240620 | |
| Download: ML19220A792 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION -
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OFFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No.
50-320/78-14 Docket No.
50-320
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License No.
DPR-73 Priority Category B2
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Licensee:
Metrocolitan Edison Comoany
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P. O. Box 542 Readino, Pennsylvania 19603 Facility Name: Three Mile Island Nuclear Station, Unit 2 Inspect % n at: Middletown, Pennsylvania Inspection conducted: March 27-28, 1978 i
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/7[J7 Inspectors:
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u'r ifeactor Inspector date signed
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61,fao%fTL s/ obr T. Stetkk,'/ Reactor Ihspector
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Approved by:
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D. L. CaThton, Chief, Nuclear Support
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cate signed Section No.1, RO&NS Branch Insoection Sumary:
Inscection on March 27-28, 1978 (Recort No. 50-320/78-14)
Area Insoected:
Routine, announced inspection to witners initial criticality.
The inspection involved 32 inspector-hours on site by tuo NRC inspectors.
Results:
Of the one area inspected, no items of noncompliance were identified.
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Region I Fom 12 7b (Rev. April 77)
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DETAILS
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1.
Persons Contacted M. Beers, Shift Supervisor T. Davis, Radiation Chemistry Technician A. Dominguez, Shift Test Director J. Flint, Physics Test Coordinator, Babcock and Wilcox J. Floyd, Operations Supervisor D. Good, Surveillance Test Coordinator C. Guthrie, Shift Foreman T. Hawkins, Shift Test Director P. Lydon, Shift Foreman
- J. Seelinger, Unit Superintendent, Technical Support T. Toole, Test Superintendent W. Zeive, Shift Supervisor
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The inspector also talked with and interviLwed several other licensee employees during the inspection.
These included engineering personnel, reactor operators, and technical support personnel.
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- denotes those present at the exit interview.
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Insoector's Witness of Initial Criticality
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Certain activities, system / component operating status, procedures, and documents of the licensee were reviewed by the inspector to
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verify completeness of requirements for initial criticality.
~Conformance to License Recuirements Prior to Initial Criticality a.
TS 2.1.1, RCS Pressure and Tenperature Limitations.
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TS 3.1.1.1, Shutdown Margin Requirements.
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TS 3.1.1.2, Reactor Coolant Flow Requirements.
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TS 3.1.1.4, Temperature Requiren.ents for Criticality.
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TS 3.1.2.2, Baron Injection Flow Paths Operable.
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TS 3.1.2.4, Makeup Pumps Operable.
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TS 3.1.2.7, Boric Acid Pump Operable.
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TS 3.1.2.9, Borated Water Sources.
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TS 3.1.3.1, Control Rods Operable.
TS 3.1.3.2, Axial Power Shaping Rods Operable.
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TS 3.1.3.3, Rod Position Indication.
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TS 3.1.3.5, Rod Drop Times.
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TS 3.1.3.6, All Safety Rods Fully Withdrawn.
TS 3.1.3.7, Regulating Rods Atuve Insertion Limits.
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F TS 3.1.3.8, Control Rod Program.
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TS Table 3.3-1, Selected RFS Instrumentation.
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TS Table 3.3-6, Radiation Monitoring Instrument.
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TS Table 3.3-9, Remote Shutdown Instrumentation.
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TS Table 3.3-10, Post Accident Monitoring Instrumentation.
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TS 3.4.1, Reactor Coolant Lcops.
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TS 3.4.4, Pressurizer Operable.
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TS 3.4.5, Steam Generator Levels.
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TS 3.4.6.1, RCS Leakage Detection System Operable.
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TS 3.4.6.2, RCS Leakage Li its.
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TS 3.5.1, RCS Core Flood Tanks Operable.
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TS 3.6.1.5, Containment Internal Pressure Limi's.
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TS 3.6.2.1, Containment Spray Systems Operable.
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lS 3.6.2.2, Spray Additive System Operable.
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TS 3.6.4.1, Gas Chromatograph Operable.
TS 3.6.4.2, Hydrogen Recombiner Operable.
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TS 3.6.4.3, Containment Hydrogen Purge Cleanup System
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TS 3.7.1.2, Emergency Feedwater Pumps and Flcupath Operable.
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TS 3.7.3.1, NSCCW Pumps Operable.
TS 3.7.3.2, Decay Heat CCW Pumps Operable.
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TS.3.7.4.1, NSRW Pumps Operable.
Source and Intermediate range nuclear instruments cali-
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brated and operable.
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Operating and test crew at or above minimum requirements.
Prerequisites of Test Procedure (TP 710/'s) and Unit
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Startup Procedure (OP 2102-1.3) satisfied.
The inspector's review included direct observations of control room instrumentation, review of completed surveillance pro-cedures, review of comp'leted preoperational test procedurns, review of control room logs, and direct observation of control room acti~ities during the test evolution.
During this review the inspetor noted the following items.
(1)
Recctor Coolant Pump 2B was not operating due to a failure of the anti-reverse rotation device.
The li-censee had therefore used the Special Test Exception of TS 3.10.3 which limits reactor power to 5% of Rated Therral Power and set the Nuclear Overpower trip settings to less than 25% of Rated Thermal Power.
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(2) The control rod reed switch position indicator channel
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for rod number 5 of rod group 8 indicated 85% withdrawn vice 100% withdrawn indicated by the pulse stepping-position indicator.
As required by TS 3.1.3.3.a.2.a, the licensee verified this rod to be fully withdrawn using the zone reference position indication system.
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Following the initial criticality and transfer from oper-ational mode 3 to 2 the reed switch position indicator channel was repaired and indicated that the rod was 100%
withdrawn.
In reviewing this incident the licensee identified the above as contrary to TS 3.0.4 in that entry into mode 2 was made with reliance on the provisions of the action statements of TS 3.1.3.3.
This was reported to the NRC per the requirements of TS 6.9.1.8.b as Reportable Occur-rence No. 78-19/IP.
b.
Review of "As-Run" Procedure and Evaluation The inspectors reviewed the "as-run" procedure (including changes and exceptions) of TP 710/1, Zero Power Physics Test, and observed the following test evolution on March 28, 1978.
0018 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> Rod Group 6/7 at 75% WD, all other rods
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at 100% WD.
0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> RCS dilution commenced with RCS baron
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concentration at 1833 ppm.
0311 hours0.0036 days <br />0.0864 hours <br />5.142196e-4 weeks <br />1.183355e-4 months <br /> Entry into operational mode 2, keff > 0.99.
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0416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br /> Dilution halted.
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0437 hours0.00506 days <br />0.121 hours <br />7.225529e-4 weeks <br />1.662785e-4 months <br /> Reactor Critical, RCS boron concentration
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1534 ppm.
0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> Intermediate range nucicar instrumentation
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channel responded.
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Duri. g the above evolution, the inspector observed the proper
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maintenance of the inverse count rate plots, control panel indications of rod position, a RCS boron sample and analysis, and independently predicted critical boron concentration using the data of OP 2103-1.9, Reactivity Balance.
The measured boron concentration at time of criticality was 1534 ppm.
The prediction of TP 710/1 was 1551 ppm and the inspector's predic-tion was 1510 ppm.
This data was well within the acceptance criteria of 1% ak/k.
No inadequacies were found in the above review and evaluations.
3.
Exit Interview The inspector met with a licensee representative (denoted in Para-graph 1) at the conclusion of the inspection on March 28, 1978.
The inspector summarized the scope and findings of the inspection as they are detailed in this report.
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