IR 05000320/1978033
| ML19224A383 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/29/1978 |
| From: | Bettenhausen L, Haverkamp D, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A382 | List: |
| References | |
| 50-320-78-33, NUDOCS 7901100030 | |
| Download: ML19224A383 (7) | |
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U.S. NUCLEAR P,EGULATORY COMMISSI0t1 CFFICE OF IfiSPECTI0tt AND Ef;FORCEMENT Region I Report flo. 50-190/78-11 Docket No. 50-320 B2 License No. Lik-73 Priority
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Catepary Licensee:
Metrooolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
H1ddletown, Pennsylvania Iaspection conducted:
November 7-9 and 16-17,1978
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Inspectors:
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v D.R.Haveramp,Rea(torInspector date signed 0W UhTf7V
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L. H. Bettenhausen, Reactor Inspector
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date signed
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Approved by-
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//,/9 - 78 R. R. Keim'iyI Chief, R/ actor Projects date signed Section Je. I, RO& C/ Branch Inscection Summary:
Inspection on November 7-9 and 16-17,1978 (Report No. 50-320/78-33)
Areas Inspected:
Routine, unannounced inspection by two regional based inspectors of startup test results; power level plateau data; and emergency safeguards actuation on November 7,1978.
The inspection involved 16 inspector-hours onsite by one ?!RC regional based i,nspector and one inspector-trainee, and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by one regional based NRC supervisor.
Resul ts:
No items of noncompliance were identified.
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Region I Form 12 77) 790110ccgg (Rev. April
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DETAILS 1.
Persons Contacted Metropolitan Edison Company M. J. Floyd, Unit 2 Supervisor of Operations Mr. J. Hilbish, Station Lead Nuclear Engineer General Public Utilities Service Corporation Mr. C. Gatto, Lead Mechanical Test Engineer Mr. S. Poje, Test Engineer
- Mr. R. Toole, Test Superintendent Mr. J. Ullrich, Test Engineer Babcock anu Wilcox Mr. J. Flint, Startup Test Engineer USNRC
- Mr. D. L. Caphton, Chief, Nuclear Suppert Section No.1
- denotes those present at the exit interview cn November 17, 1978.
2.
Startuo Test Results Evaluation The inspector conducted an evaluation of startup test TP 800/11 (MTX 147.21), Core Power Distribution (75% power level plateau testing completed on October 24,1978)
The test records were evaluated to verify the following items.
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Test changes had been approved in accordance with administrative procedures, properly entered into the procedure, accomplished if actions were necessary, and did not change the basic objective of the test.
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Test deficiencies had been resolved, accepted by appropriate management, retest conducted if required, and any system or process changes necessitated have been properly documented and
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reviewed.
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Test sumnories and evaluations had been performed by the
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cognizant engineers, and test results had been compared with established acceptance criteria.
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"As-run" copies of the test procedures contain completed data sheets (sample), data are reccrded where required and are within acceptance tolerances (sample), test deficiencies noted receive appropriate review and evaluation, and individual test steps and data sheets have been properly initialed and dated.
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Quality Assurance inspection records have been completed to document the adequacy of the test package contents, to indi-cate independent review of test records and data package contents, and an independent audit was performed during test performance, as required by administrative procedures.
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Approval of the test results by those personnel charged with responsibility for review and acceptance has been documented, and if the off site review committee has audited the test package, that their comments are included and corrective action has been taken if required.
The inspector used one or more of the following acceptance criteria for the above items.
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Final Safety Analysis Repo t
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Technical Specifications
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Test Instruction ), GPU Startup Problem Report
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Test Instruction 9, Conduct of Test
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Test Instruction 13, Test Interface Instructions
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Test Instruction 18, Test Procedure Documents
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Regulatory Guides
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Inspector Judgment
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Quality Assurance Program Findings were acceptable and no items of noncompliance were identified.
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3.
Power Level Plateau Data Review a.
Verification of Licensee Evaluation of Test Results The irspector conducted a review of the following startup tests.
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TP 800/5 (MTX 147.19), Reactivity Coefficients at Power (75% power level plateau testing completed on October 25, 1978)
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TP 800/35 (MTX 147.36), Effluent and Effluent Monitoring
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System. Test (75% power level plateau testing completed on October 23,1978)
TP 800/18 (MTX 147.27), Power Imbalance Detector Cor-
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relation Test (75% power level plateau testing completed on October 27, 1978)
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TP 800/2 (MTX 108.7), fluclear Instrument Calibration at Power (75% pcwer level plateau testing completed on October 27,1978)
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TP 800/12 (MTX 147.22), Unit Load Steady State Test (75%
power level plateau testing completed on October 23,1978)
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TP 800/22 (MTX 147.30), f4SS Heat Balance (75% power level plateau testing completed on October 23, 1978)
The test records were reviewed to verify the followinc items.
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Test summaries and evaluations had been performed by the congizant engineers, and test results had been compared with established acceptance criteria.
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Approval of the test results by those personnel charged with responsibility for review and acceptance has been documented, and if the off site committee has audited the test package, that their comments are included and corrective action has been taken if required.
T 28b
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The inspector used one or more of the following acceptance criteria for the above items.
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Final Safety Analysis Report
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Technical Specifications
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Test Instruction 18, Test Procedure Documents
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Regulatory Guides
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Inspector Judgment
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Quality Assurance Progrt.n Findings were acceptable and no items of noncompliance were identified.
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Authorization to Raise Power The inspector reviewed the licensee's evaluation of the 75%
plateau test results and the authorization for proceeding to the next test plateau.
This review included discussions with licensee and startup group representatives and review of the following items.
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Startup tests listed in Paragraphs 3 and 4.a
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SP 800/21 (MTX 147.29), !! nit Startup and Power Escalation Test (TWG approval received to escalate power to 100% on October 27,1978)
The review was conducted to assure or confirm the following i tems.
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All applicable testing has been completed.
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All testing anomalies have been evaluated and resolved by the licensee.
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The licensee has reviewed Technical Specification recuire-ments applicable to the next higher power level and has fully implemented them.
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T 28b
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The licensee performed core and plant surveys to assure safe operation during the increase of power level and arrival at the next plateau; including examination of flux distribution, core performance, reactor heat balance, unexpected radioactivity and radiation leakage, pressure boundary leakage, and reactor coolant chemistry.
The licensee has extrapolated the results of tests to
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applicable plateaus in the power ascension program, h&s compared the extrapolation with predicted plant performance, and has determined that it is reasonable and prudent to continue the testing program to the next planned power level plateau.
The inspector used one or more of the following acceptance criteria for the above items.
Final Safety Analysis Report
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Technical Specifications
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Test Instruction 9, Conduct of Test
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Regulatory Guides
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Inspector Judgment Findings were acceptable.
No items of noncompliance were identified.
4.
Emergency Safeguards Actuation The inspector reviewed the licensee's corrective measures concerning an emergency safeguards (ES) actuation which occurred on November 7, 1978.
While operating at 92% rated thermal power (RTP), startup testing per TP 800/5, Reactivity Coefficients at Power, was in progress.
All operating parameters were normal except RC Tave, which had been elevated to 588 F (6 F above nomal) for temperature coefficient measurement. A heater drain tank low level alarm wa.
received, which automatically tripped the operating heater drain pumps.
The subsequent feedwater flow transient resulted in trioping a condensate booster pump on low suction pressure, which automatically tripped the 1B feedwater pump.
The Integrated Control System began
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a power runback to 55% RTP, based on the loss of one feedwater pump.
However, due to the elevated RCS temperature, the reactor tripped at 64% RTP, when all four RPS channels received a variable temperature / pressure trip signal.
RCS pressure continued to decrease and safety injection Was automatically initidted at 1600 psig, which limited the pressure decrease to 1550 psig.
The decreased RCS volume due to the cooldown caused the pressurizer volume to decrease below zero indicated level for approximately 30 seconds.
Subsequent to the occurrence, an in-depth investigation was initiated by the licensee to evaluate the 5ctual event and appropriate corrective action.
The inspector reviewed the site report of the incident, which included sections that described the event, the sequence of events, conclusions and recommended action items, as well as various pertinent appendices.
No Technical Specification limits were exceeded and the pressurizer was not emptied during the transient.
The licensee will submit a 30-day LER of the pressurizer low level condition and a special report of the ES actuation and injection pursuant to T.S. requirements.
The inspector had no further questions concerning this incident.
The licensee's final disposition of recommended corrective actions and the above licensee reports will be reviewed during a subsequent routine inspection.
5.
Exit Interview The inspector met with a licensee representative (denoted in Para-graph 1) at the conclusion of the inspection on November 17, 1978.
The inspector summarized the purpose and scope of the inspection and the findings.
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