IR 05000317/1978034
| ML19269C032 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/29/1978 |
| From: | Baunack W, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19269C009 | List: |
| References | |
| 50-317-78-34, 50-318-78-31, NUDOCS 7901190224 | |
| Download: ML19269C032 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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78-34 Report No. 78-31 50-317 Docket No. 50-318 DPR-53 C
License No.
DDD-69 Priority Category C
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Licensee:
Baltimore Gas and Electriq. Comoany P. O. Box 1475 Baltimore, Maryland 21203 Facility Name:
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection at:
Lusby, Maryland Inspection cond ted:
November 1,4-17, 1978 Inspectors:
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W. H. Baunack, Reactor Inspector date signed date signed date signed
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Approved by:
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H. B. Kister, Chief, Nuclear Support Section
/date' signed No. 2, R0 & NS Branch Inspection Summary:
Inspection on November 14-17,1978 (Recort No. 50-317/78-34; 50-318/78-31)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of admi;:i-strative controls for surveillance precedures; surveillance testing; witnessing of surveillance test; technician qualification; and facility tour.
This inspection involved 24 inspector-hours on site by one NRC regional based inspector.
Rasul ts: Of the five areas inspected, no items of noncompliance were found in four areas; one apparent item of noncompliance was f.und in one area (Deficiency - failure to docu-ment performance of a surveillance requirement - Paragraph 3.c).
7 9 01 19 0D4 Reg; n i Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted D. Butler, Instrument and Control Technician
- J. Carroll, Performance Engineer-0perations
- R. Denton, Nuclear Plant Sqineer-0perations M. Miernicki, Performance Engineer-Maintenance
- L. Russell, Chief Engineer T. Taylor, Instrument and Control Technician The inspector also interviewed other licensee employees, including members of the technical staff, and reactor operators.
- denotes those present at the exit interview.
2.
Administrative Controls for Surveillance Procedures The inspector performed an audit of the licensee's administrat've controls by conducting a sampling review of the below listed admini-strative procedures with respect to the requirements of the Technical Specifications, Section 6, " Administrative Controls," ANSI N18.7
" Administrative Controls for Nuclear Power Plants" and Regulatory Guide 1.33 " Quality Assurance Program Requirements."
Calvert Cliff Instruction (CCI) 1010, Review and Approval
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Procedures for Proposed Calvert Cliffs Procedures, Decem-ber 12,1973.
CCI 104B, Surveillance Test Program, November 30, 1977.
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QAP 16, Surveillance Testing, October 17, 1978.
No items of noncompliance were identified.
However, the inspector noted a Quality Assurance (QA) Manual Procedure QAP 16, appears to be the principle document describing the surveillance test program including the preparation, format, and content of surveillance procedures. This procedure, which is being used as part of the facility administrative controls, is a portion of the QA Manual and is not Plant Operations and Safety Review Committee reviewed and approved as are all other administrative controls.
The licensee stated this matter, also identified during a corporate QA audit, would be reviewed and if necessary applicable portions of QAP 16 would be incorporated into CCI 104B. This item will be reviewed during a future inspection (317/78-34-02; 318/78-31-02).
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3.
Surveillance Testing a.
The inspector reviewed surveillance tests on a sampling basis to verify the following.
Test required by Technical Specifications are available
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and covered by properly approved procedures.
Test format and technical content are adequate and provide
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satisfactory testing of related systems or components.
Test results of selected tests are in conformance with
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Technical Specifications and procedure requirements have been reviewed by someone other than the tester or individual directing the test.
b.
The following surveillance tests were reviewed to verify the items identified above:
Unit 1 STP-0-86-1, Boration Flow Path Temperature Determination,
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Revision 0, July 26,1978.
Data were reviewed for five surveillances performed October 6, 1978 through November 2 1978.
STP-0-62-1, Monthly Valve Position Verification, Revision
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1, November 23, 1977.
Data were reviewed for four verifications performed July 21, 1978 through October 21, 1978.
STP-0-73-1, Engineered Safety Feature Equipment Performance
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Test, Revision 4, September 30, 1977.
Data were reviewed for four tests performed July 26, 1978 throug.1 November 1, 1978.
STP-0-29-1, CEA partial Movement, Revision 0, January 28,
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1977.
Data were reviewed for five tests performed July 4, 1978 through November 5, 1978.
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STP-0-27-1, RCS Leakage Evaluation, Revision 2, February 27, 1975.
Data were reviewed for daily evaluations performed August 1,1978 through October 31, 1978.
STP-0-55-1, Containment Integrity Verification, Revision
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5, April 27,1977.
Data were reviewed for six verifications performed June 29, 1978 through November 6, 1978.
STP-0-8-0, Diesel Generator Weekly Test, Revision 5,
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September 20, 1978.
Data were reviewed for fourteen tests performed October 9,1978 through November 13, 197.
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Unit 2 STP-0-29(A-D)-2, CEA Partial Movement, Revision 0, January
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18, 1978.
Data were reviewed for twelve surveillances performed July 2,1978 through November 12, 1978.
STP-M-572A-2, Pressurizer Safety Valve Test, Revision 0,
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September 11, 1978.
Data were reviewed for test performed September 16, 1978.
STP-M-211-2. Secondary CEA 00S Alarm Verification, Revision
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2, November 10, 1975.
Data were reviewed for four verifi-cations performed July 8,1978 through October 19, 1978.
STP-0-70-2, Staggered Test of "A" Train Components,
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Revision 0. December 8,1978.
Data were reviewed for four tests perfonned August 7,1978 through November 7, 1978.
STP-0-71-2, Staggered Test of "B" Train Components,
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Revision 1, May 26, 1977.
Data were reviewed for four tests performed June 23, 1978 through October 14, 1978.
c.
As a result of the above review, the fol~owing items were identified:
(1)
Documentation associated with STP-0-29, CEA Partial Movement surveillances completed July 2,1978 through November 12, 1978 for Units 1 a;;d 2 did not indicate that the motion inhibit circuit (preventing any CEA from being misaligned from all other CEA's in its group by more than 7.5 inches) has been demonstrated operable.
This is contrary to Technical Specification 4.1.3.1.3 which requires this verification be performed at least once per 31 days and is considered to be an item of noncompliance at the deficiency level (317/78-34-01; 318/78-31-01).
Discussions with ?icensee personnel indicate that the required motion inhibit had in fact been verified.
However, due te a lack of detail and no clear acceptance criteria in the orocedure no adequate documentation resulted showing that the required surveillance had been performed.
(2) Technical Specifications require that the minimum volume of fuel in the diesel generator day fuel tanks be verified at least once each 31 days.
The day fuel tanks are not provided with level indicating devices consequently the licensee is verifying a level in excess of the minimum
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required by actuation of fuel oil transfer pumps which start on a level in the tanks in excess of the minimum required level. This verification is performed weekly in conjunction with the diesel weekly load test.
The licensee is considering installing a more positive means of performing the required level verification.
This matter will be reviewed further during a future inspection (317/78-34-03; 318/78-31-03).
4.
Inspector's Witnessing of Surveillance Test a.
The inspector witnessed the performance of surveillance testing of selected components to verify the following:
Surveillance test procedure was available and in use.
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Special test equipment required by procedure was calibrated
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and in use.
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Test prerequisites were met.
The procedure was adequately detailed to assure performance
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of a satisfactory surveillance.
b.
The inspector witnessed the performance of STP-M-171-2, Personnel Air Lock Seal Test, Revision 2. September 13, 1978.
No items of noncompliance were identifiec.
5.
Technician Qualifications The inspector discussed the qualification records of 2 personnel having responsibility for surveillance testing of safety-related components and equipment to verify that the individual's experience level and training were in accordance with the guidelines of ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel.
No unacceptable items were identified.
6.
Facility Tour On several occasions during the inspection, tours of the facility were conducted of portions of the Auxiliary Building, Containment Entrance Area, Control Room, and the Diesel Gencrator Rcoms.
During the tours, the inspector discussed plant operations and observed housekeeping, radiation control measures, monitoring instrumentation, and controls for Technical Specification Compliance.
In addition, the inspector observed control room operations for control room manning and facility operation in accordance with administrative and Technical Specification requirements.
No items of noncompliance were identifie.
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7.
Exit Interview The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on November 17, 1978.
The purpose, scope and findings of the inspection were summarized.