IR 05000219/1979013
| ML19256G332 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/02/1979 |
| From: | Neely D, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256G330 | List: |
| References | |
| 50-219-79-13, NUDOCS 7912310065 | |
| Download: ML19256G332 (3) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-219/79-13 Docket No.
50-219 License No.
DPR-16 Priority Category C
--
Licensee:
Jersey Central Power and Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey Facility Name:
Oyster Creek Nuclear Generating Station Inspection At:
Forked River, New Jersey Inspection Conducted:
May 3-4, 1979 Inspectors: A /2/ys r e,, -
///q/r7e D. R. Neelf, Radiation Specialist
'date date Approved by:
/[
N
/./J. Stotir, Chief, Radiation Support date
.Section, FF&MSB Inspection Summary:
Inspection on May 3-4, 1979 (Report No. 50-219/79-13)
Special inspection of the radiological conditions associated with the low-low-low water level incident which occurred after the reactor trip on May 2, 1979.
Specific areas inspected included:
review of raciation and contamination surveys, air sample analysis, primary and secondary water chemistry analysis; independent measurements and tours of the plant controlled areas.
The inspection involved 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on-site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
1660 315 Region I Form 167 7 912310 Ob.
(August 1979)
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DETAILS 1.
Persons Contacted
- I. R. Finfrock, Jr., Vice-President, Generation
- 0. A. Ross, Manager, Nuclear Generating Stations
- J. T. Carroll, Jr., Station Superintendent J. L. Sullivan, Chief Engineer E. Growney, Operations Engineer E. Scalsky, Radiation Protection Supervisor L. Smailek, Health Physicist J. Cook, Group Radiation Protection Supervisor D. Pellrine, Chemical Supervisor During the course of the inspection the inspector also interviewed other licensee members of the health physics staff, reactor operators and main-tenance personnel.
- Denotes those persons present at the exit interview on May 4, 1979.
2.
Surveys Review of the licensee's contamination, radiation, and airborne survey records indicated that no significant change in radiological conditions existed at the Oyster Creek Station as a result of the low-low-low water level condition which occurred after the reactor trip on May 2, 1979.
Specific records reviewed were for the surveys performed in the Turbine Building and Reactor Building prior to and following the reactor trip.
Survey records for areas in the immediate vicinity of the Isolation Con-densers (located in the Reactor Buiiding) were specifically reviewed.
In addition, to reviewing survey records, the inspector performed independent radiation and contamination surveys at various areas inside and outside the plant.
No radiological conditions in excess of station or NRC limits appeared to exist as a result of the reactor trip.
3.
Water Chemistry The inspector reviewed the results of isotopic analysis performed on licensee samples collected from the shell side of the A and B Isolation Condensors, Condenstate Storage Tank, and primary reactor coolant water.
Spec..ic reactor water sample analysis reviewed by the inspector are listed below:
Sample Time Date 8:20 a.m. (A Loop)
May 2, 1979 3:20 p.m. (B Loop)
May 2, 1979 4:40 p.m. (B Loop)
May 2, 1979 10:05 p.m. (B Loop)
May 2, 1979 1h 05 p.m. (A Loop)
May 2, 1979 1660 316 6:41 a.m. (A Loop)
May 3, 1979
a
The inspector noted that the reactor trip occurred at approximately 1:51 p.m.
on May 2, 1979.
Based on reviews of the isotopic analysis performed on the primary reactor coolant water samples collected by the licensee prior to and after the reactor trip and subsequent low-low-low reactor water level, the inspector determined that no significant degradation of fuel cladding had occurred.
In addition, based on reviewed of analytical results of samples collected from the Condensate Water Storage Tank and shell side of the A and B Iso-lation Condensors prior to and during operation of the Isolation Condensors, the inspector determined that no recognizable primary to secondary leakage had occurred.
4.
Radiological release information is contained in IE Inspection Report No. 50-219/79-10 5.
Exit Interview An exit interview was conducted at the conclusion of the inspection on May 4, 1979 with senior management representatives denoted in Detail 1.
The inspector summarized the purpose and scope of the inspection and findings.
1660 317
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