IR 05000317/1978028

IE Insp Repts 50-317/78-28 & 50-318/78-25 on 781010-13. Noncompliance Noted:Failure to Document,Review & Approve Temporary Changes & Failure to Control & Review Procedures for Adequacy

ML19322A117
Person / Time
Site:	Calvert Cliffs
Issue date:	11/09/1978
From:	Conte R, Dante Johnson, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19322A107	List: IR 05000317/1978028 ML19322A103 ML19322A108 ML19322A112 ML19322A115
References
50-317-78-28, 50-318-78-25, NUDOCS 7901020456
Download: ML19322A117 (17)

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U.S. NUCLEAR REGULATORY COMMISSION

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v 0FFICE OF INSPECTION AND ENFORCEMENT Region I 50-317/78-28 Raport No. 50-318/78-25 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: October 10-13, 1978

// 9 /g Inspectors:

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R.J.ConteMeactor/ Inspector

/!atr/ signed N

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R.P.Zimmerman,ReacqrInspector

'date signed h?

/Y k'

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q D. F J hnso, Rd ctor 'Inspectgf date signed

//!f/M Approved by:

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'H. B. Kister7 Chief, Nuclear Support

• dafe signed Section No. 2, RO&NS Branch Inspection Summary:

Inspection on October 10-13,1978 (Combined Report Nos. 50-317/78-18; 50-318/78-25)

Areas inspected:

Routine, unannounced inspection by regional based inspectors of administrative controls of facility procedures; format and technical content of facility procedures; procedure revisions resulting from Technical Specification Amendments; procedure revisions made in accordance with 10 CFR 50.59(a) and (b);

standing orders; special orders, and temporary procedures; design of safety in-jection system reset feature; review of plant operations including a facility tour; review of monthly operation status reports for August and September,1978; and, licensee action on previous inspection findings.

The inspection involved 40 inspector-hours on site for Unit 1 and 43 inspector-hours on site for Unit 2 by three NRC regional based inspectors.

Rasults: Of the 9 areas inspected, no items of noncompliance were found in 7 areas; 2 apparent items of noncompliance were found in 2 areas (Deficiencies - failure to document, review,and approve temporary changes, Paragraph 5.c; and failure to control and review for adequacy facility procedures, Paragraph 5 d).

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DETAILS

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1.

Persons Contacted A. Barth, Engineering Technician J. Carroll, Performance Engineer

• D. Crinigan, Performance Engineer

• R. Denton, Performance Supervisor

• R. Douglass, Chief Engineer C. Dunkerly, Shif t Supervisor R. Eherts, Performance Engineer J. Hill, Shift Supervisor B. Lathan, Performance Engineer J. Rivera, Shift Supervisor P. Rizzo, Assistant General Foreman, Instrument and Electrical Maintenance

• L. Russell, Nuclear Plant Engineer - Operations K. Sebra, Principal Engineer C. Zapp, Shift Supervisor The inspector interviewed other licensee employees, including members of the performance, maintenance and operation staffs.

denotes those present at the exit interview.

• 2.

Licensee Action on previous Inspection Findings (Closed) Inspector Follow Item.(a17-78-ER-01)i Technical Specifications (TS) on Secondary Water Chemistry, to be revised to reduce the number of reportable occurrences for normal plant transients. Amendment No. 34 to DPR-53, dated August 7,1978, revised TS in this area. This changed the format of the specification such that only abnormal conditions (e.

g.,

condenser leak) will be reported.

(Closed) Unresolved Item (317/78-11-01 and 318/78-06-01): The licensee conducted a review of acceptance criteria as specified on log sheets.

The review was performed to revise applicable parameters that were ori-ginally too conservative and did not allow enough flexibility for nor-

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mal plant operations.

Based upon the inspector's review of complsted log sheets for the past quarter, the newly established acceptance cri-

-teria appears adequate to preclude the frequent logging of unacceptable results and is within Technical Specification limits.

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(Closed) Inspector Follow Item (317/78-14-01):

The inspector re-l viewed Operating Procedures OP-1, " Plant Startup from Cold Shutdown to Hot Standby," Revision 10, September 13, 1978, and OP-5, " Plant Shutdown from Hot Shutdown to Cold Shutdown," Revision 10, September 13, 1978, and verified that the respective checklists for the abosa pro-cedures'have been revised to include the recording and calculation of heat up and cooldown rates of the reactor coolant system every thirty minutes.

(Closed) Unresolved Item (317/78-15-01): The inspector reviewed Opera-ting Procedure OP-6, " Pre-Startup Checkoff," Revision 9, May 10,1978, and verified that the above checklist has been revised to reflect the correct reference to the applicable Surveillance Test Procedures.

(Closed) Unresolved Item (317/78-15-02): The inspector reviewed Sur-veillance Test Procedures STP 0-7-1, "Eng *neered Safety Features Logic and Performance Test," Revision 4, July 5,1978, and STP 0-7-2,

" Engineered Safety Features Logic and Performance Test," Revision 5, July 5,1978, and verified that the indices to the above procedures have been revised to accurately correspond with the contents of the p rocedures.

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3.

Administrative Ccntrols for Facility Procedures

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Administrative controls were reviewed to determine the licensee's system for implementing requirements associated with the control of facility procedures as specified in Technical Specification, Section 6; Regula-tory Guide 1.33, Quality Assurance Program Requirements; and, ANSI N18.7,

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" Administrative Controls for Nuclear Power Plants." Areas of emphasis were in the established controls for format, content, review (including periodic review), and approval of facility procedures.

The following documents were reviewed:

Calvert Cliffs Instruction (CCI) 100 C, Change 4, April 28,1978,

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Plant Instructions and Notices;

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CCI 101 E, February 18, 1977, Review and Approval Procedures for Proposed CC Procedures; CCI 103 C, Change 4, April 4,1978, Organization and Operation of

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the Plant Operations and Safety Review Committee (POSRC);

CCI 104 B, Change 1, June 19,1978, Surveillance Test Program;

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-CCI 106, April 24, 1972, Special Orders by the Chief Engineer;

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CCI 108 D, Change 12, September 5,1978, Change to Effective

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Calvert Cliffs Instructions and Notices; CCI 119, August 7,1974, Shop / Lab Memos;

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CCI 125, August 4,1975, Control of FSAR and Technical Speci-

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fication Manuals; CCI 201 A, Change 5, August 2, 1978, CC Nuclear Power Plant

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Maintenance Procedcres; CCI 204 A, Change 1, May 31, 1977, Functional' Test Procedures;

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CCI 300 B January 9,1976, (Change 6, August 16, 1978), Calvert

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Cliffs Operating Manual, CCOM; CCI 302 B, June 14, 1976, Calvert Cliffs Alarm Manual;

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CCI 404 A, March 3, 1976, (Change 3, January 24, 1978), Calvert

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Cliffs Radiation Safety and Chemistry Procedures Format;

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CCI 406, March 3,1976, (Change 7, June 7,1978), Index of Rad-Chem Procedures; CCI 500 C, April 7,1978, Requirements for Preparation of Fuel

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Handling Procedures;

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CCI 501 A, Change 1, April 4,1978, Requirements for Preparation and Use of Nuclear Fuel Group Procedures; and, CCI 502, July 26, 1977, Requirements for Preparation of Post

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Startup Test Procedures.

No items of noncompliance were identified.

4.

Technical Content of Facility Prccedures Facility procedures were reviewed on a sampling basis using FSAR Sys-tem Descriptions, Piping and Instrument Diagrams and Technical Speci-fications, where necessary to verify that procedures were sufficiently detailed to control the operation or evolution described within Technical Specification Requirements.

The procedures reviewed with respect to this area are marked by asterisk (*) in the next paragraph (Paragraph 5, l

Review of Facility Procedures).

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During the review of the selected Alarm Manual Procedures, it was noted that many procedures describe what provides the alarm, however, they do not specify corrective actions to be taken by the operator.

The licensee representative stated that the majority of the procedures in question involve alanns due to switch positions and are really status indicators for the operator, and therefore, corrective action would not be appropriate.

The inspector singled out the following alarm procedures in which it appeared appropriate corrective actions were warranted, yet no corrective actions were specified:

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1C08/2C08, G-02, Nos.11 A,11 B,21 A, and 21 B SI Check Valve Pressure High; 1C03, C-40, No.11 Main Steam Isolation Valve Test Valve

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Close; and,

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1C08, C-40, No. 21 Main Steam Isolation Valve Test Valve Close.

The licensee representative agreed that appropriate operator action was warrented for the procedures noted above and stated that apparently this was overlooked during the periodic review conducted within the last year.

It was stated that these procedures would be revised.

It appeared to the inspector that this mr.y be generic to other procedures in the Alann Manual.

The licensee representative stated that another review of the Alann Manual would be conducted by the end of January,1979, to determine if similiar problems exist with other procedures in the manual.

This is unresolved pending completion of actions by the licensee at stated above and subsequent review by NRC:I (317/78-28-01 and 318/78-25-01).

5.

Review of Facility Procedures a.

Facility procedures were reviewed on a sampling basis to verify the following:

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Procedures, plus any changes, were reviewed, approved and retained in accordance with the requirements of the Technical Specifications and the licensee's administrative

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controls;

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The overall procedure format and content were in conformance

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with the requirements of the Technical Specifications and ANSI N18.7, " Administrative Ccatrols for Nuclear Power Plants;"

Checklists, where applicable, were compatible with the

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step-wise instructions in the procedures; Appropriate Technical Specification limitations had been

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included in the procedures; and,

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Temporary changes were made in conformance with Technical Specification requirements and the licensee's administrative

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controls. (This temporary change review included procedures in addition to those listed below.)

b.

The following procedures were reviewed:

Administrative Procedures (Verification of proper review and approval only)

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CCI 104 B, Change 1, June 19, 1978, Schedule for Surveillance Tests and Calibration; CCI 133, Change 1, August,1978, Calvert Cliffs Fire Pro-

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tection Plan; and,

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CCI 120 A, April 13, 1977, Calibration Program for Measuring and Test Equipment.

General Plant Operating Procedures Abnormal Operating Procedure - 14, Revision 5, August 9,

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1978, Reactor Trip Recovery;

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Operating Procedure - 4, Revision 3, March 18,1977, Plant Shutdown from Power Operation to Hot Standby; Operating Procedure - 6, Revision 9, May 10,1978, Start-

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Up Checkoff List; and, Operating Procedure - 3, Revision 9, November 30, 1977,

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Normal Power Operations, t

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Emergency Procedures Emergency Operating Procedures (EOP) - 3, Revision 2,

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November 30, 1977, Loss of Main Feedwater; E0P - 13, Revision 2, November 30, 1977, Emergency Boration;

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E0P - 12, Revision 0, Loss of Reactor Coolant Flow; and, Abnormal Operating Procedure - 6, Revision 4, December

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22, 1977, Loss of Containment Integrity.

System Operating Procedures Operating Instruction (0I) - 3, Revision 14, August 17,

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1978, Safety Injection, Shutdown Cooling and Containment Spray;

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OI - SA, Revision 2, February 24, 1977, Containment Cooling;

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OI - 8C, Revision 6, May 25, 1977, Main Steam Vents and Drains and Moisture Separator Reheater Vents and Drains;

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OI - 8E, Revision 6, November 3, 1977, MSIV Hydraulics; OI - 2A, Revision 12, June 21, 1978, Chemical and Volume

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Control System Volume Control;

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OI - 27C, Revision 3, March 2, 1977, 4.16 KV System; and,

.0I - 30, Revision 4, June 21, 1978, Nuclear Instrumentation.

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• Alarm Manual Procedures (Revision 11, June 21,1978)

1C03, C-40, No, ll, Main Steam Isolation Valve Test

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Valve Close; 1C03, C-41, No.11, Main Steam Isolation Valve Hydraulics

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System;

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1C07, F-41, No.11, Charging Pump SIAS Blocked Auto Start; 1C07, F-45, Charging Header Flow Low, Pressure Low;

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1C08, G-09, No. 11, HPSI Pump Discharge Pressure Hi;

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IC08, G-29, MOV 655 SIAS Blocked;

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2C09, H-36, No. 21, Containment Cooling Fan Auto Start;

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2C10, J-09, No. 23, Containment Filter Differential

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Pressure Hi; 2005, D-15, Power Ratio;

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2C05, D-39, Nuclear Instrument Channel Inoperative;

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1C19, R-09, Diesel Out of Service;

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1C19, R-12, No. 24, Bus Diesel Lineup Improper; 1C08/2C08, G-02, No. 11 A, B, 21 A, B SI Check

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Valve Pressure Hi;

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2008, C-40, No. 21, Main Steam Isolation Valve Test Valve Close; and, 1C08/2C08, G-07, Steam Generator Isolation Signal A

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Blocked.

Maintenance Procedures

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CVCS-10, Revision 0, January 13, 1978, Charging Pump Inspection; HE-21, Revision 1, September 6, 1978, Containment Personnel

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Lock Interlock Bypass;

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I-5, Revision 1, January 1,1978, Wide Range Proportional Counter Plateau Check; MSIV-5, Revision 0, March 16, 1977, Repair of MSIV Pres-

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sure Seal; I-10, Revision 1, September 24, 1975, Containment Pres-

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sure Transmitter Isolation Valve Maintenance / Repair; and, BAT-2, Revision 0, October 11, 1973, Cell Peplacement.

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c.

During the review of the control of temporary changes the below listed items were observed.

Change Report (temporary change) 78-56 was issued on June

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28, 1978 to 0I 20, Revision 2, May 10, 1978, Fire Protection System.

This change updated the procedure to reflect numbered valves already installed in the system.

However, the change had not been forwarded to POSRC for review as of Octobe'r 13,.1978,. exceeding the 14 day TS limit for POSRC review of such a change.

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The required Nitrogen Surge Accumulator Pressure for

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Nos.11 and 12 Main Steam Isolation Valve (MSIV) L. P.

Hydraulic Pump was changed from 600 psig + 30 to 300-psig + 30, on Table 1 to 01 8E, Revision 6, November 3, 1977, MSIV Hydraulics. This was to accurately reflect

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a modification to this system.

However no Change Report was generated and,:as a result, proper rsview and approval by Shift Supervisor and POSRC was not documented.

This failure to properly document, review and approve temporary changes represents an apparent noncompliance with TS 6.8.3 (317/78-28-02 and 318/78-25-02).

d.

The below listed observations were made in the area of control of procedures and review of procedures for adequacy.

Table 1 to 0I 8E, MSIV Hydraulics was missing from the

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Unit 1 and Unit 2 Operators' copy of the procedure.

This table specifies the required Surge Accumulator Nitrogen Pressure for L. P. Hydraulic Pumps on system startup.

It appeared these Tables were removed for local reference.

A third copy of this procedure, also filed in the control room did contain the subject table.

Several procedures do not reflect appropriate TS limits.

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OP-6, Start-Up Checkoff List, and OP-3, Unit 1 Normal Power Operation, indicates nonconservative limits for the following:

Safety Injection Tank (SIT), Nitrogen Pressure 200-250 psig, (listed in the OP-6 as > 200 psig);

Refueling Water Tanks Minimum Temperature > 40 F (listed in OP-6 as > 35 F); and Unit 1 Departure from Nucleate Boiling (DNB) Limit for Tc (Cold Leg Temperature) 1 547 F)

(listed in one section of OP-3 as 1 548 F).

The SIT Nitrogen Pressure Limit has existed since the is-

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suance of the original TS.

The other two limits were revised in subsequent TS amendments.

In the case of OP-6, the pages which reflected these nonconservative limits were revised on dates subsequent to issuance of TS/ Amend-ments.

In the case of OP-3, another section of the pro-cedure was revised to reflect the amended limit.

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' The inspector attempted to verify the performance of

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periodic review of these procedures and several other

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0Is to determine why these procedures were not updated to reflect appropriate TS limits. However, this docu-mentation (required by CCOM 300B to be documented on the original of the procedure in the procedure history file) was not available. The maintenance of the history file is addressed in paragraph 7.b.

Further, the docu-mentation for 0I 8E, 3, and 2A was also not available.

The licensee representative stated that the ops and E0Ps are reviewed annually as a part of the Training Program.

This represents noncompliance (deficiency) with 10 CFR 50, Appendix B, Criterion VI (317/78-28-03 and 50-318/78-25-03).

The inspector also verified compliance with present TS limits addressed above by review of other documents such as operating logs or completed surveillance procedures, which were adequately reviewed and updated.

6.

Standing Orders, Special Orders and Temporary Procedures

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The inspector reviewed licensee Orders / Procedures which are cate-gorized as Standing Orders, Special Orders, or Temporary Procedures as defined in ANSI N18.7, " Administrative Controls for Nuclear Power Plant," to determine that:

The content of the Order / Procedure was compatible with ANSI

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N18.7 definitions; and, Provisions exist for approval, periodic review, updating and

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cancellation of these Orders / Procedures.

The inspector identified that the following types of licensee docu-ments were issued in this area:

Shop / Lab Memo, Operations Department Standing Orders / Night Orders, Technical Support Procedures. Those procedures issued within the last year were reviewed on a sampling basis.

No items of noncompliance were identified.

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7.

Changes to Procedures as Described in the Safety Analysis Report Pursuant to 10 CFR 50.59(a) and (b)

a.

The inspector reviewed licensee records to identify changes to procedures which are described in the Final Safety Analysis Report (FSAR) and to verify that these changes, if any, were reviewed and maintained by the licensee in accordance with 10 CFR 50.59(a) and (b).

Records reviewed were associated with the procedures noted in the previous paragraph (Paragraph 5, Review of Facility Procedures) and included the licensee's Pro-cedure History File and Onsite Safety Committee Meeting Minutes File.

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Of the procedures / changes to procedures sampled, the inspector did not identify any change to procedures as described in the FSAR.

It was noted that the licensee has established administrative con-trols for such changes and that these controls do not conflict with 10 CFR 50.59 requirements.

b.

However, during the review of the Procedure History File, the below listed items were noted.

Not all revisions / changes issued within the last year to

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certain procedures (0P-3 and 6 in particular) were filed.

These revisions were located in routing folders throughout the facility.

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These routing folders took up to several months to be re-turned by the procedure coordinator for filing. The licensee representative acknowledged the plausibility of these folders being lost since they were not controlled documents.

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There appeared to be an inconsistency of filing which raised questions as to what exactly was revised in a particular

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procedure history.

Some packages had new revision cover forms with replaced pages and others had new revision forms with new revision pages.

• Documentation of periodic review.(as required by CCOM) was

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missing for several 0Ps and 0Is (see paragraph 5.d).

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The licensee representative acknowledged the above findings and stated that this area would be reviewed and that a system was started for a copy of the revision to be inserted in the history file inmediately upon issuance.

This is unresolved pending NRC:I review within three months to assure the effective implenentation of maintaining these records as Quality Assurance documents, that is, the maintenance-of the procedure history file and the required duplication of these records for duplicate storage (317/78-28-04 and 318/78-25-04).

8.

Procedure Changes Resulting from License Amendments License Amendments 24 through 34 for Unit 1, and 8 through 16 for Unit 2, which included Technical Specification (TS) changes, were reviewed on a sampling basis to verify that applicable procedures were revised as necessary to reflect these changes.

During this review, is was determined that Amendments 33 and 21 for Unit 1 and Amendment 9 for Unit 2, were not fully incorporated into applicable procedures (OP-6 and OP-3).

It appeared to the inspector this was due to an improper revies during the implementation of the system for ircorporation of license amendments to the facility (con-trolled by the Facility Change Requests (FCR Forms).

This apparent noncompliance is addressed in paragraph 5.d.

No other items of noncompliance were identified.

9.

Survey of Operating PWRs with a Safety Injection System (SIS) Reset Feature (IE TI 2515/14)

a.

Objective The purpose of this review was to assure that Calvert Cliffs Units 1 and 2 (with an SIS Reset Feature) have written pro-

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cedures which describe all necessary operation actions to sus-tain operation of the energency diesel generator and related engineered safety features after a loss of offsite power fol-lowing a Loss of Coolant Accident (LOCA), and subsequent to an SIS reset.

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b.

Review

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In addition to discussions with the licensee, the following documents were reviewed:

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Applicable _ Sections, logic diagrams, piping and instru-

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ment diagrams of Chapters 6 and 7 of the Final Safety Analysis Report (FSAR) on Emergency Core Cooling Systems and Safety Injection Actuation System;

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Drawing IE-76, 61-076-B, Sheet 2, Revision 6, February 16, 1977, Low Pressure Safety Injection Pump No.12; Drawing IE-76, 61-076-B, Sheet 22, Revision 6, February 16,

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1977, Reactor Safeguards Motor Operated Valves 615, 625, 635, 617, 627, 637 and 647; E0P-4, Revision 1, November 30, 1977, Steam Line Rupture;

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E0P-5, Revision 3, November 30, 1977, Loss of Reactor

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Coolant; E0P-6, Revision 2, November 30, 1977, Steam Generator

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Tube Rupture; AOP-5, Revision 1, November ~30, 1977, ECCS Long Term

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Cooling; 01-3, Revision 14, August 9,.1978, Safety Injection Shutdown

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Cooling and Containment Spray (Unit 2); and, OI-34, Revision 3, March 2, 1977, Engineered Safety Feature

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Actuation System, c.

Findings

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A procedure addressing " Inadvertent Safety Injection / Reset" dces not exist per se.

It is the licensee's policy to utilize the emergency procedure for LOCA or. Major Steam Leaks to verify pro-per equipment function on any Safety Injection Signal (inadvertent or real).

Once the determination is made that an SI is inadver-tent and equipment is functioning properly, the SI is reset and components are manually realigned for normal plant operation /re-covery per checklists in the subject procedures.

If a true SI subsequently occurs during the realignment, equipment will auto-matically function as required as long as control switches are not in " pull-to-lock off/ shut" positions for pumps and valves and are not held in the "off" position (spring to normal) for pumps.

No procedures require the use of these ' abnormal postions during the realignment.

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The licensee does not feel a separate. procedure is warranted for the subject scenario. The inspector had no further questions in this area.

10.

Review of Plant Operations a.

Shift Logs and Operating Records The inspector reviewed the following logs and records.

Shift Supervisor's Log for the period September 3,1978

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through October 12, 1978.

Apparatus Service Tag Logs; entries made during August 1,

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1978 through October 10, 1978.

Control Room Log Sheets for the month of September,1978

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The logs and records were reviewed to verify the following items.

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Log keeping practices and log book reviews are conducted

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in accordance with established administrative controls.

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Log entries involving abnormal conditions are sufficiently

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detailed.

Log book reviews are being conducted by the staff.

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Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifi-cations and the following administrative control procedures.

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CCI-106, "Special Orders by the Chief Engineer," Original

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dated April 24, 1972.

CCI-ll2, " Safety and Safety Tagging," Change 3, October 14,

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1976.

CCI-ll4, " Plant Logs," Change 8 January 9,1978.

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CCI-116, "BG&E Hold for QC Clearance Tags," Original dated

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June 5,1974.

No items of noncompliance were identifie.

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b.

Plant Tour Upon arrival at the site at 3:30 p.m. on October 10, 1978, the inspector proceeded 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 requirements. The in-spector then conducted a tour of the Unit 2 containment to directly observe fuel handling activities and radiation con-trols established at the entry and exit points to contain-ment.

The inspector then conducted a tour of the turbine building to check for general cleanliness and housekeeping conditions and potential fire hazards.

The tour was com-pleted at 8:00 p.m.

At various times during October 10-12, 1978, the inspector conducted tours of the following accessible plant areas.

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Auxiliary Building

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Turbine Building Spent Fuel Pool Area

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Control Room

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Safeguards Room Outside Peripheral Areas

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The following observations / discussions / determinations were made.

Control Room and local monitoring instrumentation for

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var ious components and parameters was 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.

Radiation Work Permit R-78-6 and SWP-1201, used for entry to radiation areas were reviewed.

. Plant housekeeping conditions, including general cleanliness

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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 vibrations.

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 was observed.

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Selected apparatus service tags were observed for proper posting and the tagged equipment was observed for proper positioning. The items observed included tags and equip-ment associated with clearance 78 656 and MR-0-77-711.

In addition, the inspector audited the status of Apparatus Service Tags by compariag tag log entries with Watch En-gineer File Cards.

The Control Board was observed for annunciators that nor--

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mally should not be lighted during the existing plant con-ditions. 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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was reviewed. There were no changes in this area since the previous inspection.

Control Room manning was observed on several occasions

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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,

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applicable Technical Specifications and the following procedures.

CCI-107D, " Area and System Cleanliness," Original, July,1977.

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CCI-112A, " Safety and Safety Tagging," Change 3, October 14,

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1976.

CCI-3008, "Calvert Cliffs Operating Manual," Change 4,

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February 13, 1976.

CCI-400A, " Radiation Safety Manual," Change 2, July 15,1977.

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The inspector's findings regarding the plant tour were acceptable, except as noted below.

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During the plant tour the inspector noticed a rather large amount of oil on the floor in the #21 diesel engine room.

The inspector could not ascertain whether the oil was from a spill or a leak.

He informed the licensee that this pre-sents a possible fire hazard and requested that an investi-gation be performed to determine the source of the oil.

This item (318/78-25-05) is unresalved and will be examined on a subsequent inspection.

11.

In-Office Review of Periodic Report The inspector reviewed the Calvert Cliffs Nuclear Power Plant Monthly Operation Status Reports for August,1978 and September, 1978, in the Region I office.

The inspector verified that the reports included the information required to be reported by Technical Specifications, and that test results and supporting information was consistent with performance specifications.

The inspector ascertained that applicable cor-rective actions taken or planned were adequate for resolution of identified problems and determined whether any information contained in the report should be classified as an abnormal occurrence.

The monthly status reports were closed out based upon a satisfactory re-view in the Region I office.

No items of noncompliance were identified.

12.

Unresolved Items Unresolved items are findings about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations.

Unresolved items disclosed during the inspection are discussed in paragraphs 4, 7.b, and 10.b.

13.

Exit Interview

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The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on October 13, 1978.

The inspector sumarized the purpose, scope and findings of the inspection.

The findings were also reviewed in a subsequent telephone discussion between Mr. R. Conte, NRC:I and Mr. L. Russell on November 1, 1978.

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