IR 05000313/1982010

IE Insp Repts 50-313/82-10 & 50-368/82-08 on 820501-31.No Noncompliance Noted.Major Areas Inspected:Operational Safety Verification,Surveillance,Followup on Previously Identified Items & Emergency Preparedness Exercise

ML20055B955
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/21/1982
From:	Callan L, Randy Hall, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20055B951	List: IR 05000313/1982010 ML20055B950
References
50-313-82-10, 50-368-82-08, 50-368-82-8, NUDOCS 8207230651
Download: ML20055B955 (9)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

Report: 50-313/82-10 Licenses: DPR-51 50-368/82-08 NPF-6 Dockets: 50-313

50-368 Licensee

Arkansas Power and Light Company Facility Name: Arkansas Nuclear One (AN0), Units 1 and 2 Inspection At: AN0 Site, Russellville, Arkansas Inspection Conducted: May 1-31,1982 Inspectors: / /O ~ 6/9/.92 W. D. Johnson, Senior Resident Reactor Inspector Date (Pa "ra s , ,4,5)

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L.'d.fallan,ResidentReactorInspector /Dafe (Par / graphs 1,2,3,4,5,6,7)

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Approved: ' 6 - 6 / 34 i

R. E' Hall, Chibf, Reactor Project Section C

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! Inspection Summary

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Inspection conducted during period of May 1-31, 1982 (Report 50-313/82-10)

Areas Inspected: Routine, announced inspection including operational safety verification, surveillance, followup on previously identified items, and

emergency preparedness exercis The inspection involved 55 inspector-hours by two NRC inspectors.

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Results: Within the four areas inspected, no violations or deviations were identifie PDR ADOCK 05000313 G _ _ _ . _ _ _ . . _ . __

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-2-Inspection conducted during period of May 1-31, 1982 (Report 50-368/82-08)

Areas Inspected: Routine, announced inspection including operational safety verification, surveillance, maintenance, followup on previously identified items, review of Licensee Event Reports, and emergency preparedness exercise.

The inspection involved 60 inspector-hours by two NRC inspectors.

Results: Within the six areas inspected, no violations or deviations were identifie . _ . . _ _ - _ - _ _ - _- . _ -

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DETAILS SECTION

1. Persons Contacted J. Levine, All0 General Manager B. A. Baker, Operations flanager T. N. Cogburn, Plant Analysis Superintendent E. C. Ewing, Plant Engineering Superintendent L. Sanders,ibintenance Manager J. !1cWilliams, Unit 1 Operations Superintendent

! M. J. Bolanis, Health Physics Superintendent R. Tucker, Electrical Maintenance Superintendent R. Wewers, Unit 2 Operations Superintendent

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L. Dugger, Special Projects Manager

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L. Humphrey, Administrative Manager J. Lamb, Safety and Fire Prevention Coordinator S. Lueders , Radwaste Coordinator The inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Followup On Previously Identified Items (Units 1 and 2)

(Closed) Severity Level V Violation 368/8129-04: Category E valve not locke Following the identification of this item, the licensee reeerified the status of all Unit 2 Category E valves in I accordance with Procedure 2102.01, Attachment E, and took steps to assure that operators were aware of their respon-sibilities relative to administrative controls over locked valve (Closed) Severity Level IV Violation 368/8128-04: Seismic Class 1 pipe support missin The licensee has installed the missing pipe support, which

had been removed without adequate administrative control to facilitate a design change during the construction phas

Present administrative controls are expected to prevent recurrenc (Closed) Severity Level IV Violation 368/8129-05: Seismic Class 1 pipe support deficiency.

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The identified deficiency has been corrected and training has been conducted to stress the individual responsibilities for complete job closeou (Closed) Severity Level IV Violation 313/8130-04: Station battery rack discrepancie The identified discrepancies have been corrected and training has been conducted to stress the individual responsibilities for complete job closeou (Closed) Severity Level V Violation 313/8201-01; 368/8201-01:

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Posting of radiation area The radiation areas identified by the NRC inspectors were

promptly posted when identified. Posting requirements have t

been reviewed at Health Physics Department meeting The NRC

. inspectors have not identified posting discrepancies during subsequent tours.

4 (Closed) Severity Level V Violation 313/8204-02: Manual valves locked in wrong positio The two valves were repositioned and the licensee took steps to assure that operators were aware of their responsibilities relative to controls over Category E manual valve (Closed) Open Item 368/8135-01: Containment electrical penetrations.

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The licensee has issued and implemented Revision 7 of Appendix A,

" Weekly Electrical Penetration N2 Pressure Check," of Procedure

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l 2107.01, " Electrical System Operations." This procedure now I

includes a weekly check of the N2 isolation valve to each pene-tration and a weekly verification that each penetration is pressurize (Closed) Open Item 368/8022-02: Temperature readings during High Pres-sure Safety Injection (HPSI) pump annual surveillanc On-the-job training is now conducted by the licensee to ensure that Unit 2 Waste Control Operators obtain the HPSI pump bearing temperature data from the same location as the vibration dat Similarly, temperature data taken during annual surveillance testing of the Low Pressure Safety Injection Pumps, Containment Spray Pumps, and Charging Pumps are now obtained from specific, identified locations that will provide trendable, consistent data from one year to the nex . - _ _ _ _ - _ _ _ ___ _ _ . . _ _ - _ _ . _ . _ - .

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-5-(Closed) Severity Level V Violation 313/8128-01; 368/8127-01: Emergency _

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battery power not available on security inverte The identified deficiency has been corrected. Additionally, the NRC inspector reviewed the licensee's new maintenance procedure for testing and inspecting the security inverter and noted procedural steps that should help prevent a recur-rence of this deficiency.

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l (Closed) Unresolved Item 368/8128-05: " Fan Trouble" alarm for vital instrument inverters disable The NRC inspector determined by review of Unit 2 Startup Test-ing records that the " Fan Trouble" alarms were disabled after appropriate safety reviews for technical reasons that appeared adequate. Following identification of this item, the licensee

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placed administrative controls on this temporary modification by I

placing it in the Jumper and Lifted Lead Log (serial 1837). The inspector has no further questions regarding this ite (Closed) Severity Level V Violation 313/8129-02; 368/8128-02: Failure to adequately label radioactive container Following identification of this item, the licensee took prompt corrective action. Additionally, Plant Procedure 1622.008,

"flarking and Handling of Radioactive Materials and Equipment,"

has been revised to provide instructions for proper labeling and use of 55-gallon drums as storage containers.

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(Closed) Severity Level V Violation 313/8130-02; 368/8129-02: Failure to delete superseded safety-related procedure The licensee deleted the identified superseded procedures and i reviewed the remaining procedures for further examples of a i breakdown in administrative controls over safety-related proce-

dures. A followup review of safety-related procedures by the NRC inspector did not identify any further discrepancies of this nature; however, the NRC inspector noted an instance where a portion of an existing procedure has been replaced by a new procedure without deleting the affected portion of the old proce-dure. The procedures involved were 1602.020, " Radiation Exposure Control," and 1612.001, " Exposure Limits and Monitoring Techniques."

Procedure 1612.001 significantly modifies that portion of Procedure 1602.020 that discusses exposure control and author-ization requirements for increasing weekly exposure administrative limits, yet both procedures are in effect in their entiret The NRC inspector discussed this matter with licensee representatives who indi-cated that both 1612.001 and 1602.020 would soon be superseded by new

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-6-Procedures 1622.01 and 1622.012, at which time the old proce-dures would be deleted. The inspector noted to licensee representatives the confusing nature of the multiple series of Health Physics procedures still in effect, as evidenced by the above example, and emphasized the importance of sorting out the various procedures into an orderly system. This item will remain open pending further inspector revie (313/8210-01; 368/8208-02)

(Closed) Open Item 313/8135-05; 368/8135-03: Leaking ccatainers in the Radwaste Buildin The two leaking containers have been removed by the license The remaining fiberglass storage casks used for storage of radioactive resin slurry have had their drain connections bagged with plastic to collect any leakage that may occu (Closed) Severity Level V Violation 313/8201-02; 368/8201-02: Failure to perform surveillance on radioactive sealed source The NRC inspector verified that the surveillance requirements for radioactive sealed sources are now included in Revision 3 to Plant Procedure 1001.09, " Master Test Control List." Placing radioactive sealed source surveillance in the formal scheduling system is expected to prevent recurrenc No violations or deviations were identified.

3. Licensee Event Reports Followup (Unit 2)

Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specifications:

8110 8125 81 36 8138 8210 The following subparagraphs provide inspector comments on certain of the above LER's:

Unit 2 Diesel Generator Exhaust Header Fire LER 81-25 reported the ignition of oil-soaked insulation on a diesel generator exhaust header during routine monthly surveillance. The oil

-7-had leaked through gaskets in the exhaust system into the insulatio The licensee has implemented Revision 4 to Operating Procedure 2104.36,

" Emergency Diesel Generator Operations," to help preclude future occur-rences. This revision incorporates the manufacturer's recommendation to run the diesel generators for at least an hour after each start to ensure that any oil in the exhaust system is removed prior to securing the diese Failures of the Steam Driven Emergency Feed Pump (2P7A)

LER 81-38 reported trips of the Steam Driven Emergency Feed Pump (2P7A)

on October 9,10, and 11,1981. These trips were reported as being caused by inadequate administrative controls following restoration after maintenance. The NRC inspector has verified that the licensee's cor-rective action appears to be adequate and that 2P7A has had no further failures. Additionally, the inspector has verified that there appears to be no similarity between the failures reported in LER 81-38 and the previous failures of 2P7A reported in LER's 80-22, 80-30, 80-36, and 80-50 that were corrected by design changes (Inspection Report 50-368/82-01, paragraph 3, discusses the earlier failures and the licensee's corrective action).

Failure of Differential Pressure Transmitters Inside Containment LER 82-10 reported the failure of two reactor coolant pump differential pressure transmitters inside the Containment Building due to moisture from a nearby valve bonnet leak shorting the electrical terminations in the transmitter casings. The water had entered the casings through an open conduit box and associated conduit The licensee reported com-pleting all corrective actions, consisting of closing and sealing the open conduit box and cleaning the shorted electrical terminations. The NRC inspector noted, however, that the licensee's corrective actions appeared to be inadequate since approximately one month later an additional reactor coolant pump differential pressure transmitter failed due to an apparently similar cause, when it was exposed to moisture from a leaking main feed-water check valve inside containment. The NRC inspector discussed this matter with licensee representatives who indicated an inspection of the Unit 2 Containment Building would be performed to identify any other leakage paths for moisture into electrical components. This item will remain open pending the NRC inspector's review of the licensee's inspection results (50-368/8208-01).

No violations or deviations were identified.

4. Operational Safety Verification (Units 1 and 2)

The NRC inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators. The inspec-tors verified the operability of selected emergency systems, reviewed tagout records, and verified proper return-to-service of affected compo-nents. Tours of accessible areas of the units were conducted to observe

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-8-plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspectors, by obser-vation and direct interview, verified that the physical security plan was being implemented in accordance with the station security pla The NRC inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. The NRC inspec-

tors walked down the accessible portions of the Uqit 2 emergency feedwater i supply to "B" steam generator from the turbine-driven (2P7A) and motor-

! driven (2P78) Emergency Feedwater Pumps to verify operability. The inspec-

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tor also witnessed portions of the radioactive waste system controls

! associated with radwaste shipments and barreling.

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l These reviews and observations were conducted to verify that facility

! operations were in conformance with the requirements established under

! Technical Specifications,10 CFR, and administrativa procedure . Monthly Surveillance Observation (Units 1 and 2)

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j The NRC inspector observed the Technical Specification required surveil-

, lance testing on the Unit 1 High Range Auxiliary Building Stack Radiation

! Monitor (Procedure 1304.87) and verified that testing was performed in accordance with adequate procedures, that test instrumentation was cali-brated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with Technical Specifications and procedure requirements, that test results were reviewed by personnel other than the individual directing

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i I the test, and that any deficiencies identified during the testing were

! properly reviewed and resolved by appropriate management personnel.

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The inspector also witnessed portions of the flow test of Unit 1 Reactor Building Cooling Units, VCC-2A and 2B, including the chlorination of the l

service water system (Procedure 1104.33 Supplement VI) and the semi-t annual calibation of the Peak Shock Recorder (Procedure 2304.58).

No violations or deviations were identifie . Monthly Maintenance Observation (Unit 2)

Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, Regulatory Guides, and industry codes or standards; and in conformance with Technical Specification The following items were considered during this review: the limiting con-l ditions for operations were met while components or systems were removed

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from service; approvals were obtained prior to initiating the work; i

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-9-activities were accomplished using approved procedures and were inspected l as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records i were maintained; activities were accomplished by qualified personnel; parts

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and materials used were properly certified; radiological controls were 1 implemented; and fire prevention controls were implemente Work requests were reviewed to determine status of outstanding jobs and  !

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to assure that priority is assigned to safety-related equipment mainte-l nance which may affect system performanc The following maintenace activities were observed / reviewed:

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. Repair of Unit 2 Emergency Feedwater Isolation Valve, 2CV-1075 t j (J.0. 26623 and 26646)

. Repair of weld leak on Unit 2 Reactor Coolant Pump 2P32A middle seal ,

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i pressure sensing line (J.0. 24895)

No violations or deviations were identifie . Emergency Preparedness Exercise (Units 1 and 2)

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The licensee conducted its annual emergency preparedness exercise on bby 19, 1982. This exercise involved participation by NRC Region IV, including the NRC resident inspectors, as well as by the local and state i authorities. A detailed discussion of the NRC findings during this exercise are found in NRC Inspection Report 50-313/82-11; 50-368/82-0 . Exit Interview

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The NRC inspectors met with Mr. J. M. Levine (Plant General Manager)

and other members of the AP&L staff at the end of various segments of this inspection. At these meetings, the inspectors summarized the

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