IR 05000317/1979021
| ML19294B988 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/04/1980 |
| From: | Architzel R, Dante Johnson, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19294B983 | List: |
| References | |
| 50-317-79-21, 50-318-79-20, NUDOCS 8003060504 | |
| Download: ML19294B988 (3) | |
Text
.
b M
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-317/79-21 Report No. 50-318/79-20 50-317 Docket No. 50-318 DPR-53 C
License No. DPR-69 Priority Category C
--
Licensee:
Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name:
Calvert Cliffs Nuclear Power Plant Units 1 and 2 Inspection at:
Lusby, Maryland Inspection conducted:
November 27-30, 1979 Inspectors:
W
/ '/ N 0. F de on eactor Inspector date signed WW
/
/6 R. E. Wrchitzel, Reactor Inspector date signed date signed Approvedby:/
Z
/
O
. R. Keim1g M nlet, Reactor Projects
/ da2'e signed Section No. 1, RO&NS Branch Inspection Summary:
Inspection on November 27-30, 1979 (Report Nos. 50-317/79-21 and 50-318/79-20)
Areas Inspected:
Routine, announced inspection for the purpose of turnina over project inspector assignment for the facility.
The inspection involved 22 inspector-hours on site by two regional based inspectors.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
8003060 50 9
.
.
DETAILS 1.
Persons Contacted J. Carroll, Supervisor - Technical Support
- R. Denton, Nuclear Plant Engineer - Operations C. Dunkerly, Shift Supervisor W. Gibson, Nuclear Plant Engineer - Performance J. Hill, Shift Supervisor L. Hinkle, Foreman - Instrument Maintenance A. Kaupa, Radiation Safety and Chemistry Engineer
- L. Russell, Chief Engineer D. Thomas, Training Specialist R. Wenderlich, Training Coordinator J. Yoe, Training Specialist The inspectors also interviewed several members of the licensee's operations, technical, and administrative staffs.
- denotes those present at the exit interview.
2.
Plant Tour a.
The inspectors performed a tour of the following accessible areas:
Auxiliary Building
--
Containment Building (Unit 2)
--
Control Room
--
Turbine Building
--
Outside Peripheral Areas
--
Spent Fuel Pool Area
--
Newly Constructed Administration Building (Resident Inspector's
--
Office Space)
Security Buildings
--
Health Physics Control Points
--
.
.
b.
The following observations, and determinations were made:
Radiation controls established by the licensee, including
--
posting of radiation areas, conditions of step-off pads and disposal of protective clothing were observed.
Independent radiation surveys were conducted to verify
--
levels of radiation were consistent with posted areas and levels specified on selected radiation work permits (RWP's)
and special work permits (SWP's).
Control room manning was observed on several occasions
--
during the inspection.
Systems and equipment in all areas toured were observed for
--
the existence of fluid leaks and abnormal piping vibrations.
--
Seismic restraints and hydraulic snubbers were examined on a sampling basis to verify adequate installation and fluid levels.
Plant housekeeping conditions, including general cleanliness
--
conditions and storage of materials and components to preclude safety and fire hazards, were observed.
Control room and local monitoring instrumentation for various
--
components and parameters were observed, including reactor power level, CEA positions and safety related valve position indication.
No items of noncompliancc were identified.
3.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on November 30, 1979 to discuss the inspection findings.
On November 29, representatives from the NRC's Office of the Executive Legal Director were on site for a tour of the facility.