IR 05000289/1974026
| ML19256D449 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/28/1974 |
| From: | Mccabe E, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D445 | List: |
| References | |
| 50-289-74-26, NUDOCS 7910180786 | |
| Download: ML19256D449 (6) | |
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g3 U S. AT031IC ENERGY C01CIISSION
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DIRECTORATE OF REGUL\\ TORY OPERATIONS
REGION I
RO Inspection Report No:
50-289/74-26 Docket No:
50-289 Licensee:
Metropolitan Edison Cocoany License No:
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Three Mile Island - Unit 1 Priority:
Category:
B-2
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Location:
Middletown, Pennsylvania
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Type of Licensee:
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Type of Inspection:
Routine, Announced Dates of Inspection:
June 24-25, 1974 9(~DatesofPreviousInspection:
June 3-6, 1974
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Reporting Inspector-
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D. M. Sternberg, Reactor Inspector Date Accompanying Inspectors:
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Date Date Date Date
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Other Ac.:ompanying Personnel:
O G l2?I7'l L.
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McCabe, Senior Reactor Inspector Date Reviewed By:
C@k A
4['27/74
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r.. L. McLace, denior steactor inspector, nuclear Support Date Section, Reactor Operations Branch-9,._
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B.
Follow-up Action - A0 74-11 and Apparent Violation - Containnent Integrity Degradation.
(Detail 3)
C.
Inspectors Witnessing of Loss of Off-site Power Test.
(Detail 4)
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DETAILS
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Persons Contacted Metropolitan Edison Comcany (Met Ed)
Mr. M. L. Beers, Shift Foreman
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Mr. E. E. Bulcer, Mechanical Engineer Mr. J. J. Colitiz, Station Engineer Fk. J. R. Floyd, Supervisor of Operations - Unit 1
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Mr. C. E. Hart =an, Electrical Engineer Mr. J. G. Herbein, St,a, tion Superintendent Mr. B. J. Rittle, Electrical Maintenance Foreman Mr. M. J. Ross, Shift Supervisor Mr. B. G. Smith, Shift Foreman
Mr. G. C. Wallace, Shift Supervisor General Public Utilities Service Corporation (GPUSC)
Mr. W. H. Behrle, Shift Test Director Mr. G. P. Miller, Test Superintendent 9~
Mr. ' S. G. Poje, Shif t Test Engineer
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Babcock and Wilcox Nuclear Services-
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Mr. W. E. Schaid, Shift Data Analyst 2.
Follow-up Action - AO 74-8 d -
g On June 6, 1974 during a spot check of the Reactdr Protection System settings, it was found that one of the settings (Channel B linear amplifier) was set at a value which, in accordance with the con-
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servative assumptions, corresponded to 20% nuclear over-power trip'.
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This is a violation of Technical Specificatien paragraph 3.1.9.1.b which provides for low power ohysics testing "above 1800 psig nuclear overpower trip shall be set at less than 5.0. percent....
The licensee stated in his letter dated June 17, 1974 that appropriate warnings and/or cautions would be added to the surveillance procedure as corrective action for this incident.
During this inspection the inspector reviewed the revised procedure.
A Test Change Notice added appropriate warnings for using this procedure during the low power physics testing program. The inspector had no further questions on this matter.
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Follow-up Action - AO 74-11 On June 13, 1974 uith the Reactor Coolant System at a temperature of 520 F and a pressure of 2155 psig both doors of the Reactor Building Personnel Hatch were simultaneously opened.
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This is a violation of Technical Specification paragraph 3.6.1 which states:
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" Containment integrity, as defined in'Section 1.7 shall be maintained whenever all three of the following conditicns exist:
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Reactor coolant pressure is 300 psig or greater b.
Reactor coolant temperature is 200 F or greater c.
Nuclear fuel is in the core."
The licensee stated in his letter dated' June 21, 1974 that new 9('
operating instruct ons and precautions would be posted at each i
access and that the maintenance worker involved would be counseled on the procedure for use of the doors.
During this inspection, the inspector observed the new operating instruction and precaution sign at the Personnel Hatch and was infor=ed by the Unit 1 Mecha.nical Engineer that the maintenance worker involved was counseled by him. The inspe.ctor had no further questions on this item.
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4.
Inspectors Witnessing of Loss of Off-site Power Test During this inspection the inspector witnessed the preparation for and conduct of the Loss of Off-site Power Test.
The following ite=s represent areas observed and specific comments concerning them.
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Correct procedure and revision in use: The OfficiIal Field Copy in use had all revisions included.
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b.
Minimum crew requirements: The normal shift complement performed the test, additionally a second crew was present to perform unique test functions and assist if required.
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Test prerequisites met: The inspector observed the electrical plant realign =ent for this test, th'e alignre,nt and availability of the diesel generators, and the checklist signoffs for the Test G
Procedure.
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SUMMARY OF FINDINGS Enforcement Actiot:
A.
Contrary to Technical Specification requirements, the licensee
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improperly set the gain of the B channel nuclear overpower trip
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which resulted in a trip etpoint in excess of the reqaired value
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during the initial criticality on June 5, 1974.
(Detail 2)
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B.
Contrary to Technical Specification requirements, both doors of the Reactor Building Personnel Hatch were opened simultaneously on June 13, 1974 resulting in a degradation of the containment integrity.
(Detail 3)
Licensee Action on Previousiv Identified Enfe cement Items Not inspected Unusual Occurrences A.
B Channel Nuclear Overpower trip setpoint was improperly set.
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(A0 74-8, Met Ed letter dated June 17, 1974 to Director, DL).
(Detail 2)
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Both doors of th. Reactor Building Personnel Hatch were opened simultaneously.
(A0 74-11, Met M letter dated June 21, 1974, to Director, DL).
(Detail 3)
Other Significant Findings A.
Loss of Off-site Power Test The inspector witnessed the Loss of Off-site Power Test.
(Detail 4)
Management Inttrview
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The exit interview was held on-site on June 25, 1974, at the conclusion of the inspection teith Mr. J. G. Herbein of the Metropolitan Edison Company, the Station Superintendent.
The following su==arizes items discussed.
A.
Follow-up Action - A0 74-8 and Appareht.Iiolation - Improper Nuclear Overpower Trip Setpoint.
(Detail 2)
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Proper plant systems in service: No special systems were required.
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Special tjest equipment : The inspector observed the reactimeter e.
and analog recorders used for this test as well as the Heise Gauge used to measure RCS pressure. No deficiencies were noted.
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Transient test data equipment calibration to a common time base:
All recor.ders were noted to be started by a common switch and
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common event markers were available for time correlation.
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Testper$ormedasrequiredbyprocedure: The test was observed g.
to be performed i~n accordance with the test procedure which
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included portions of the emergency procedure for loss of off-cite power modified for this test.
No exceptions were noted.
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Crew response: No deficiencies noted.
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Quick suc=ary analysis made to assure proper plant response to the test: The reactor tripped and both diesel generators started. The tecperature and pressure of the plant were con-trolled within limits.
The off-site power was then restored and the plant was placed in the hot shutdown mode at about
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4:45 a.m.
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Data collected for final analysis by the proper personnel:
Required data sheet: were completed and recorders appeared to function. satisfactorily, d
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Test results indicate acceptance criteria has' been met: Plant pressure was observed to stay below the limit of 2750 psig.
Both diesels started satisfactorily and, reportedly, no fission
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product activity increase was observed in the reactor coolant following the test.
Automatic components appeared co function as required.
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