IR 05000338/1986011

Insp Repts 50-338/86-11 & 50-339/86-11 on 860407-11.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification,Monthly Maint,Primary Sys Leakage & Diesel Generator Walkdown

ML20210U412
Person / Time
Site:	North Anna
Issue date:	05/12/1986
From:	Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20210U409	List: IR 05000338/1986011 ML20210U402
References
50-338-86-11, 50-339-86-11, NUDOCS 8606020320
Download: ML20210U412 (4)

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pauco UNITED STATES f jo NUCLEAR REGULATORY COMMISslON y\ n REGION ll y j 101 MARIETTA STREET. * ATLANTA, GEORGI A 30323

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Report Nos.: 50-338/86-11 and 50-339/86-11 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.: 50-338 and 50-339 License Nos.: NPF-4 and NPF-7 Facility Name: North Anna 1 and 2 Inspection Conducted: April 7-11, 1986 Inspector: . . Na%b S!/2. !B(,

Date Signed

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J. L. mathis Approved by: #MYN F. Jape, Section Chief f Date Signed

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Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection at the site was in the areas of operational safety verification, monthly maintenance, diesel generator walkdown, and primary system leakag Results: No violations or deviations were identifie {DR ADOCK 05000338 l

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REPORT DETAILS Persons Contacted Licensee Employees

• E. W. Harrell, Station Manager

• E. Kane, Assistant, Station Manager

• E. R. Smith, Assistant, Station Manager

• R. O. Enfinger, Superintendent, Operation

• J. R. Haper, Superintendent, Technical Services '

• J. H. Leberstein, Licensing Coordinator

• D. E. Thomas, Mechanical Maintenance Supervisor Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personne NRC Resident Inspector

• L. King

• Attended exit interview Exit Interview The inspection scope and findings were summarized on April 11, 1986, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio l Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Followup on Inspector Identified items (0 pen) 85-24-15, Direct reading of RWST level not available outside the control room. The inspector reviewed the above item for close-out; however, the licensee requested NRR to review for exemption. This item will remain open until NRR gives a disposition on the licensee request.

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(Closed) 84-37-02, Review current practice of maintaining split records of certain test The licensee maintains split records of certain tests. The methods of analysis and analysis work sheet are part of station record This item is close Within the areas examined, no violations or deviations were identifie . Operational Safety Verification (71707)

By observations during the inspection period, the inspector verified that the control room manning requirements were being met. In addition, the inspector observed shift turnover to verify that continuity of system status was maintained. The inspector periodically questioned shif t personnel relative to their awareness of plant condition Through log review and plant tours, the inspector verified compliance with selected requirements of Technical Specification and Limiting Conditions for Operation During the course of the inspection, observations relative to protected and vital area security were made, including access controls, boundary integrity, search, escort and badgin On a regular basis, radiation work permits (RWP) were reviewed and the specific work activity was monitored to assure that activities were being conducted per the RWPs. Selected radiation protection instruments were periodically checked and equipment operability and calibration frequency was verifie The inspector was kept informed, on a daily basis, of the overall status of both units and of any significant safety matter related to plant operation Discussions were held with plant management and various members of the operations staff on a regular basis. Selected portions of operating logs and data sheets were reviewed dail The inspector conducted various plant tours and made frequent visits to the control room. Observations included: witnessing work activities in progress; verifying the status of operating and standby safety systems and equipment; confirming valve positions, instrument and recorder readings, annuciator alarms, and housekeepin No violations or deviations were identifie . Monthly Maintenance (62703)

Station maintenance activities af fecting safety-related systems and components were observed and reviewed to ascertain that the activities were conducted in accordance with approved procedures, regulatory guides and industry codes or standards, and in conformance with Technical Specifi-cation .

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3 Diesel Generator Walkdown The following selected diesel generator systems were verified operable by performing a walkdown of the accessible and essential portions of the system Unit 1 Valve Check Off - Diesel Air (1-0P-6.7A)

Valve Check Off - IJ Diesel Engine Lube Oil System (1-0P-6.4A)

Valve Check Off - 1J Diesel Engine Cooling Water (1-0P-6.2A)

Valve Check Off - 1H Diesel Engine Lube Oil System (1-0P-6.3A)

Valve Check Off - 1H Diesel Engine Cooling Water (1-0P-6.1A)

Unit 2 Valve Check Off - Diesel Air (2-0P-46.4A)

Valve Check Off - 2J Diesel Engine Lube Oil System (2-0P-6.4A)

Valve Check Off - 2J Diesel Engine Cooling Water (2-0P-6.2A)

Valve Check Off - 2H Diesel Engine Lube Oil System (2-0P-6.3A)

Valve Check Off - 2H Diesel Engine Cooling Water (2-0P-6.3A)

No violations or deviations were identified in these area . Reactor Coolant System Leak Rate Monitoring (61710)

Procedures 1-PT-52.2 and 2-PT-52.2, both titled " Reactor Coolant System Leak Rate," applying to Units 1 and 2 respectively, were reviewed. _ Completed copies of 1-PT-52.2 and 2-PT-52.2 were reviewed for the period March 30, 1986 for Unit 1 and April 1, 1986 for Unit The reviewer confirmed that the limiting conditions of TS 3.4.6.2, as well as the frequency of surveil-lance required by TS 4.4.6.2d, were satisfied. The procedure reviewed by the inspector had been performed in 60 minutes for RCS leakage for Unit 1 and 61 minutes for RCS leakage for Unit 2. The calculated unidentified leakage for Unit I was 0.16 gpm and 0.89 gpm for Unit 2. TS requires that the total leakage (unidentified) does not exceed 1 gp In the areas inspected, no violations or deviations were identifie !

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