IR 05000317/1978032
| ML19263A981 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/22/1978 |
| From: | Dante Johnson, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19263A971 | List: |
| References | |
| 50-317-78-32, 50-318-78-29, NUDOCS 7901040022 | |
| Download: ML19263A981 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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Region I 50-317/78-32 Report No.
50-318/78-29 50-317 Docket No.
50-318 DPR-53 C
License No. DPR-69 Priority Category C
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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:
Nov ber 6-9, 1978 Inspectors:
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D. F. Johnson, Keactor inspector date s#1gned date signed date signed
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Approved by:
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//-/E-18 R: RTK ig, ef, Reactor Projects date signed Secti No.
RO&NS Branch Inspection Summary:
Inspection on November 6-9,1978 (Report Nos. 50-317/78-32 and 50-318/78-29)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of reactor operations conducted during the previous year for conformance with safety limits; limiting safety system settings and limiting conditions for operation; licensee followup actions concerning IE Bulletins; and facility tours conducted during normal and off normal hours.
The inspection involved 16 in-spector-hours onsite for Unit 1 and 13 inspector-hours onsite for Unit 2 by one NRC regional based inspector.
Results: No items of noncompliance were identified.
79010 4 0 0R Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Baltimore Gas and Electric Company
. Mr..J. Carroll, Perfornance Engineer - Operations
- Mr. R. Denton, Nuclea. Plant Engineer - Operations Mr. J. Hill, Shift Supervisor
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- Mr. A. Kaupa, Radiation Safety and Chemistry Engineer Mr. J. Lemons, Nuclear Plant Engineer - Maintenance Mr. J. Miernick, Performance Engineer - Maintenance Mr. M. Roberson, Assistant General Foreman - Maintenance
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- Mr. L. Russell, Chief Engineer The inspector also interviewed several other licensee employees during this inspection. They included reactor operators, plant operators, health physics and chemistry technicians, and technical engineerf.1g staff personnel.
- denotes those present at the exit interview.
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Review of Safety Limits, Limiting Safety System Settings and Limiting Conditions for Operation The inspector observed process instrumentation monitoring a.
current operations on November 6-9, 1978 and reviewed records of previous reactor operations for Unit 1 and 2 during July 1978 through November 1978.
The following logs and records were reviewed on a sampling basis:
Control Room Log Sheets.
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Control Room Logs
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Control Room Semi-Weekly Log, Electrical Power Supplies
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Shift Supervisors' Log
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Check Lists for Nonroutine Technical Reports Requiring
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Timely Reporting
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Auxiliary Building Log Sheets
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Reactor Coolant Chemistry Log
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Steam Generator Chemistry Log
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Refueling and Spent Fuel Pool Chemistry Log
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Safety Injection Chemistry Log
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Boric Acid Batching and Storage Tank Chemistry Log
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Condensate, Feedwater and Main Steam Chemistry Log
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b.
The following Surveillance Test Procedures (STP's) Operating Procedures check lists and completed test data were reviewed:
Completed check lists for OP-1, OP-2, OP-4, OP-5 and
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OP-6.
STP-0-1, Main Steam Isolation Valve Full Stroke Test,
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Revision 1, Ocotber 27, 1976. Test completed October 17, 1978.
STP-0-6, Reactor Protection System Startup Test, lievision
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4, July 12, 1978. Test completed October 23, 1978.
STP-0-7, Engineered Safety Features Actuation System
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Logic Test, Revision 5, July 5,1978. Test completed August 31, 1978.
STP-0-8, Diesel Generator Weekly Test, Revision 5,
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September 20, 1978. Test completed November 7,1978.
STP-0-33, Radiation Monitoring System Functional Test,
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Original July 27, 1976.
Test completed November 7,1978.
STP-0-55, Containment Integrity Verification, Test
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completed October 22, 1978.
STP-M-220, Engineered Safety Features Actuation System
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Functional Test, Revision 3, June 30, 1977.
Test com-pleted October 19, 1978.
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The observations and record review were conducted to verify that startup, power and/or shutdown operations were in con-formance with Technical Specification safety limits, limiting safety system settings and limiting conditions for operation.
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Acceptance criteria for the above items included selected requirements of the following Technical Specifications and facility operating procedures:
Reactivity Control Systems Technical Specification (TS)
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TS 3.1.1.1, Shutdown Margin TS 3.1.2.8, Barated Water Sources - Operating TS 3.1.2.6, Boric Acid Pumps - Operating TS 3.1.2.4, Charging Pumps - Operating TS 3.1.3.3, Position Indicating Channels TS 3.1.3.1, Full Length CEA Position Instrumentation Technical Specification
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TS 3.3.2.1, Engineered Safety Features Actuation System Instrumentation TS 3.3.3.1, Radiation Monitoring Instrumentation
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Reactor Coolant System Technical Specifications TS 3.4.6.1, Reactor Coolant System Leakage TS 3.4.7, Chemistry TS 3.4.9.2, Pressure / Temperature Limits TS 3.4.9.1, Pressurizer l
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Containment Systems Technical Specifications
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TS 3.6.1.1, Primary Containment TS 3.6.1.3, Containment Air Locks
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Plant System Technical Specifications TS 3.7.1.5, Main Steam Isolation Valves TS 3.7.3.1, Component Cooling Water System TS 3.7.4.1, Service Water System TS 3.7.5.1, Salt Water System TS 3.7.1.6, Secondary Water Chemistry
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Electrical Power System Technical Specifications TS 3.8.1.1, A. C. Sources TS 3.8.2.1, Onsite Power Distribution Systems TS 3.8.2.3, D. C. listribution, Operating Emergency Cooling System Technical Specifications
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TS 3.5.1, Safety Injection Tanks TS 3.5.2, ECCS Subsystems Tavg >,300 F
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Power Distribution Limit Technical Specification TS 3.2.4, Azimuthal Power Tilt
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Operating Procedure OP-1, Plant Startup from Cold Shut-down to Ho't Standby, Revision 10, September 13, 1978.
OP-2, Plant Startup from Hot Standby to Power Operation,
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Revision 5, February 24, 1977.
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OP-3, Normal Power Operation, Revision 9, November 30,
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1977.
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OP-4, Plant Shutdown from Power Operation to. Hot Standby,
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Revision 3, March 18,1977.
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OP-5, Plant Shutdown from Hot Standby to Cold Shutdown,
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Revision 10, September 13, 1978.
OP-6, Pre-startup Checkoff, Revision 8, March 31, 1978.
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No items of noncompliance were identified.
3.
IE Bulletin Followup The inspector reviewed the licensee's followup actions regarding the IE Bulletins listed below:
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IEB 78-05, " Malfunctioning of Circuit Breaker Auxiliary Con-tact Mechanism - General Electric Model CR105X." April 14, 1978
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IEB 78-06, " Defective Cutler-Hammer Type M Relays with D. C.
Coils." May 31,1978 IEB 78-10, "Bergen-Paterson Hydraulic Shock Suppressor Accumu-
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lator Spring Coils." June 27,1978 The review included discu2sions with licensee personnel, revww of selected facility records, and observation of selected facility equipment and components.
With respect to the above Bulletins, the inspector verified that licensee management forwarded copies of the bulletin response to appropriate onsite management representatives that information and corrective action discussed in the reply was accurate and effective as described, and that the reply was submitted within the time period described in the bulletins.
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and facility procedures.
No items of noncompliance were identified concerning licensee follow-up on the above Bulletin.
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4.
Plant Tour Upon arrival at the site on November 6,1978, the inspector pro-ceeded directly to the Control Room to observe plant operations during off normal hours.
Control Room manning and Control Board monitoring instrumentation and equipment controls were observed for conformance with applicable Technical Specification require-ments. The inspector then conducted a tour of the turbine building to check for general cleanliness, housekeeping conditions and potential fire hazards.
At various times during November 6-9, 1978, the inspector con-ducted tours of the following accessible plant areas.
Auxiliary Building
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Turbine Building
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Spent Fuel Pool Area Control Room
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Safeguards Room
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Outside Peripheral Areas The following observations / discussions / determinations were made.
Control Room and local monitoring instrumentation for various
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components and parameters were observed, including reactor power level, CEA positions, radiation monitoring levels, and refueling activities.
Radiation controls established by the licensee, including
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posting of radiation areas, the condition of step-off pads and the disposal of protective clothing were observed.
Radia-tion Work Pennit R-78-6 used for entry to radiation areas was reviewed.
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Plant housekeeping conditions, including general cleanliness conditions and storage of material and components to prevent safety and fire hazards, were observed.
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Systems and equipment in all areas toured were observed
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for the existence of fluid leaks and abnormal piping vibra-tions.
The indicated positions of electrical power supply breakers,
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control board equipment start switches, and control board remote-operated valves and the actual positions of selected manual-operated valves were observed.
The Control Board was observed for annunciators that normally
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should not be lighted during the existing plant conditions.
The reasons for the lighted annunciators were described by a Control Room Operator.
The licensee's policy and practice regarding plant tours
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were reviewed. There were no changes in this area since the previous inspection.
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Control Room manning was observed on several occasions during the inspection.
Acceptance criteria for the above items included inspector judge-ment and requirements of 10 CFR 50.54(k), Regulatory Guide 1.114, applicable Technical Specifications and the following procedures.
CCI-107D, " Area and System Cleanliness," Original, July
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1977.
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CCI-il2A, " Safety and Safety Tagging," Change 3, October 14, 1976.
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CCI-300B, "Calvert Cliffs Operating Manual, " Change 4,
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February 13, 1976.
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CCI-400A, " Radiation Safety Manual," Change 2, July 15, 1977.
The inspector's findings regarding the plant tour were acceptabl.
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5.
Exit Interview The inspector met with., licensee representatives (denoted in Detail
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1) on site at the conclusion of the inspection on November 9,1978.
The purpose, scope, and findings of the inspection as documented in this report were discussed.
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