IR 05000219/1974010
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U.S. ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS
REGION I
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RO Inspection Report No:
50-219/74-10 Docket No: ' 50-219 Licensee: Jersey Central Power and Light Company License No:
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Madison Avenue and Punch Bowl Road Priority:
C Morristown, New Jersey 07960 Category:
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Location: Oyster Creek, Forked River, New Jersey
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4i Type of Licensee:
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Announced Type of Inspection:
Dates of Inspection:
May 30-31, 1974 Dates of Previous Inspection:
May 8--9, 1974 p
Reporting Incpector:
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T. Rebelo ki, Reactor Inspector-Date/
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Accompanying Inspectors:
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Fl]h Date
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Date Date
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Other Accompanying Personnel:
Date 6.I l'4.l7 i Reviewed By:
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W Date E. C. McCabe, Senior Reactor Inspector, Nuclear
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Support Section, Reactor Operations Branch
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l 9604180229 960213
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DEKOK95-258 PDR J
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a SUMMARY OF FINDINGS
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' Enforcement Action id.
. None
' Licensee Action on Previously Identified Enforcement Items Not inspected Unusual Occurrenens
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Thelicenseeidentifiedreactor.coolantleakageexistingintheaieaof
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In Core Flux Housing, core position 28-05.
(Details, Paragraph 4)
Other Significant Findings A.
Current The licensee postponed the Containment Integrated Leak Rate test due to. the identification of in-core. flux monitor housing leak.
(De tails,
' Paragraph 4)
46sl B.
Status of Previously Reported Unresolved Items The licensee has revised the Integrated Primary Containment Leak Rate Test to resolve inspector concerns.
(Details, Paragraph 3)
Management Interview A management interview was conducted by telephone conference call on June 3, 1974, with.the following persons.
Jersey Central Power and Light Mr. J. T. Carroll, Station Superintendent Mr. K. O. Fickerssen, Jr., Technical Supervisor Mr. E. J. Growney,' Technical Engineer The following summarizes the item discussed.
A.
Containment Integrated Leak Rate Test The licensee stated that he has revised the CILRT procedure in areas of concern documented in report 50-219/74-09. Areas reviewed by inspector were
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Reassignment of Instrument Volume Fractions.
(De tails,
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Paragraph 3.a);
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Calculated Containment Free Volume.
(Details, Paragraph 3.b);
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3.
Temperature Stabilization Criteria.
(Details, Paragraph 3.c);
4.
10 CFR 50, Appendix J requirements.
(Details, Paragraph 3.d);
5.
Containment Test Format. - (Details, Paragraph 3.e).
B.
In Core Flux Monitor Housing (A0 50-219/74-34)
The licensee stated that a program to determine the cause and~ institute repair of the In-Core flux monitor housing leakage has not been developed.
The licensee stated that, prior to resumption of power operation, report will be submitted to the Directorate of Licensing.
(De tails,
Paragraph 4)
C.
Control Rod Drive Stub Tube Examination The inspector stated that he had witnessed removal of the CRD imbd mechanism, core position 18-47, and of the thermal. sleeve, in preparation for ultrasonic testing of the weld joint.
0 Details, Paragraph 5)
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DETAILS 1.
Persons Contacted Mr. R. M. Bright, Associate Engineer Mr. J. T. Carroll, Station Superintendent Mr. R. Dube, Quality Assurance Supervisor Mr. K. O. Frickeissen, Jr., Technical Supervisor Mr. E. J. Growney, Technical Engineer Mr. D. L. Reeves, Jr., Chief Engineer Mr. E. Rosenfeld, Associate Engineer Mr. D. A. Ross, Manager, Nuclear Generating Station
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Mr. J. L. Sullivan, Jr., Operations Engineer 2.
General The inspector was notified by the licensee of the pending Containment Integrated Leak Rate Test (CILRT), and proceeded to the site on May 30, 1974.
The licensee reported the Abnormal Occurrence 50-219/
74-34 and postponed indefinitely the CILRT.
3.
Containment System Leak Rate Test The licensee notified the inspector that the local leak rates have
,ygkg not been completed. The inspector reviewed the revision of CILRT procedure and closed out the following areas of concern:
a.
Reassignment of Instrument Volume Fractions The licensee's Containment Integrated Leak Rate Test presently attributes equal volume fractions to the temperature and dewpoint test instruments. Upon loss of an instrument the reassigned values of volume fraction will be equally shared by the renain-ing operable instruments. The licensee has also established a criterion on the minimum number of operable instruments. This concern, documented in Report 50-219/74-09, Details, Paragraph 2.b, is resolved, b.
Calculated Containment Free Volume The licensee presented to the inspector the calculations of containment f ree air volume and torus water level as a function of air volume. This concern, documented in Report 50-219/74-09, Details, Paragraph 2.c, is resolved.
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c.
Temperature Stabilization Criteria
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The licensee has established, in the CILRT procedure, a stabilization
'y criteria of 1*F/hr rate of change of average temperature over a two hour period. This area of concern, documented in Report 50-219/74-09, Details, Paragraph 2.d remains unresolved pending resolution of the 0.1*F/hr criterion referred to RO:HQ.
d.
Appendix J of 10 CFR 50. Additional' Requirements The licensee has revised the CILRT procedure to reflect the requirements of 10 CFR 50, Appendix J in the area of testing.
This concern, documented in Report 50-219/74-09, Details,
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Paragraph 2.g. is resolved.
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c.
Integrated Primary Containment Leak Rate Test - Format The licensee has revised the CILRT to include the following.
1.
Signature and date block entry requirements for the prerequisites and performance of the test.
2.
System diagram reference numbers have been added to the procedure.
"M 3.
Elimination of non-defnitive statements and referenced operational procedures where necessary.
This concern, documented in Report 50-219/74-09, Details, Paragraph 2.h, is resolved.
4.
In Core Flux Monitor Housing Abnormality-The licensee Abnormal Occurrence report 50-219/74-34 dated May 30, 1974, identifies coolant leakage in the area of the In Core Flux monitor reactor vessel housing at core coordinate 28-05.
Leakage was found during scheduled reactor vessel hydrostatic test inspec-tion of pressure boundaries following a routine refueling mainte-nance activity.
The licensee has contacted the nuclear steam supplier and reactor vessel manufacturer.
Onsite discussions to determine the course of action were in progress during the inspection.
The licensee stated that the evaluation of the problem is not complete at present time, and that RO:HQ and RO:I will be informed of the progress of discussions.
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-5-The licensee also s tated ' that, prior to returning to power operations, he would submit a report for. review and approval by the Directorate
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of Licensing.
5.
Control Rod Drive'- Position 18-47 The licensee, upon identification of the In-Core Flux Tube leakage, initiated reinspection of all bottom head reactor penetrations. Dur-ing this inspection, discoloration was noted on the Control Rod Drive Mechanism housing at core position 18-47.
The. inspector witnessed portions of the CRD mechanism removal from the reactor. vessel, and thermal sleeve removal. The licensee was preparing to-perform an ultrasonic test inspection of the wel3~ area between the stub tube and CRD sleeve.
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The licensee reported to the inspector by telephone that no abnormalities were determined. This item will'be subsequently reviewed.
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