ML19316A147

Notice of Violation from Insp on 780616

ML19316A147
Person / Time
Site:	Oconee
Issue date:	06/16/1978
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19316A144	List: IR 05000269/1978012 ML19316A143 ML19316A145 ML19316A146 ML19316A147
References
50-269-78-12, 50-270-78-11, 50-287-78-11, NUDOCS 7911280688
Download: ML19316A147 (1)

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APPENDIX A NOTICE OF VIOLATION Duke Power Company License Nos. DPR-47 Based on the results of the NRC inspection conducted on May 9-12, 1978, it appears that certain of your activities were not conducted in full compliance with NRC requirements as indicated below. These items have been categorized as described in our correspondence to you dated December 31, 1974.

10 CFR 20.203(c) statas in part: "(2) Each entrance or access point to a high radiation area shall be:

(1) Equipped with a control device which shall cause the level of radiation to be reduced...;

or (ii) Equipped with a control device which shall energize a conspicuous visible or audible alarm signal... ; or maintained locked except during period when access to the area is required, with positive control over each individual entry.... (4) In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for the control required by subparagraph (2) of this paragraph."

w Contrary to the above, a high radiation area surrounding a de-watered resin cask, located outside the Unit 2 auxiliary building was not under direct surveillance from 11:00 a.m. on May 9,1978 to 12:00 p.m. on May 11, 1978 nor was the area locked or alarmed.

This is an infraction.

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h RII RIpert N:s. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-1 DETAILS I Prepared by:

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W R6~actfr Infpector Date Nuc1 ar,pport Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection:,y.

9-12, 978 I

if 8gY Reviewed by:

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/Date Nuc ea Support Section No. 2 Reactor Operations and Nuclear Support Branch 1.

Persons Contacted J. E. Smith, Plant Manager

• R. C. Adams, I&E Engineer M. Alexander, Technical Support Engineer R. T. Bond, Project License Engineer

• W. A. Brown, Staff Chemist C. Burns, I&E Foreman

• R. M. Koehler, Superintendent Technical Services

• J. M. Davis, Maintenance Superintendent

• H. J. Sefick, Security

• C. T. Yongue, Health Physics Supervisor

• J. N. Pope, Operations Supervisor Five instrument technicians and two plant operators were also contacted.

• Denoted those attending exit interview.

2.

Licensee Action on Previous Inspection Findings Not inspected.

3.

Unresolved Items Unresolved items are matters about which more informaticn is required in ceder to ascertain whether they are acceptable items, items of noncompliance or deviations. One unresolved item disclosed during the inspection is discussed in paragraph 6.

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-2 4.

Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on, May 12, 1978. The inspectors summarized the scope and findings of the inspection as discussed in paragraphs 5, 6, 7, 8 and 9.

The licensee acknowledged the item of noncompliance and indicated a review of responsibilities between departments would be conducted.

5.

Surveillance (Periodic) Test Procedure and Results Verification The inspectors conducted a review of test procedures and results and witnessed testing as follows:

(Procedures and Results)

IPO O A 0310 07A, ES Logic Subsystem 1 HPI CH.1 PT-0 A 0110 01, Spent Fuel Pool Ventilation Test PT 0 A 0200 46, Reactor Coolant System Leak Rate Test PT 0 A 020212, HP Injection System ES Test PT 0 A 029'

..a stop Valve Closure Time Test PT 0 A 060015, CRD Movement Test PT 0 A 060017, Group 7 Control CRD Withdrawal PT 0 A 0620 09, Keowee Hydro Emergency Start Test PT 1 A 025104, LP Borated Water Pump Performance Test PT 2 A 060011, Emergency Feedwater System IP 3 A 0340 15, CRD Position Indication Tube Alignment The inspectors used one or more of the following acceptance criteria for the above items:

I DPC0 Topical Report - 17.2.11 - Test Control I

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i RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-3 Technical Specification - Section 4.0 ANSI N45.2-1971 ANSI N18.7-1972 Inspector Judgement Quality Assurance Program The test procedures and test results were reviewed to verify:

Test prerequisites and plant conditions were specified, and reviewed, and approvals had been performed.

Technical contents of the procedure were correct, and the test was performed on schedule.

Test instruments were listed in the procedure and the instruments used identified in the test results.

Test results were recorded and compared with acceptance criteria, and return of equipment to service was veritied upon t;&;'-tion of test.

Within the areas inspected no items of noncompliance or ieviations were identified.

(Test Witnessed)

PT 2 A 6001/1 - Periodic Instrupc3t Surveillance (Encle sure 13.1)

PT 3 A-305/3A - RPS - CH. A Functional Verification Surveillance tests were witnessed to verify:

Correct procedure was being used for testing and that technicians and operators understood equipment being tested.

Data was correctly recorded and verified.

Calibrated test equipment was in use where requi ed.

Verification of return of equipment to service and removal of test equipment was done, u-)

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 1-4 i

Within the areas inspected no items of noncompliance or deviations were identified.

6.

Instrumentation Calibration Program Verification The inspector conducted a review of the following calibration procedures and test results:

1 P 0 A 0150 O1G, Reactor Building Temperature Recorded Calibration IP 0 A 020010, RC Pressure Instrument Calibration IP 0 A 020101A, CF Tank Pressure Instrument Calibration IP OA 020101 B, CF Tank Pressure Instrument Calibration IP 0 A 030103D, NI 4 Calibration (Annual)

IP 0 A 0.$05 01 M, RPS CH. A Pressure Calibration IP 0 A 0305 05 H, RPS CH. A RB High Pressure Trip IP 0 A 0305 05 D, Pressure Trip RPS CH. D RB High IP 0 A 0310 05B, ES Analog CH. 3 RC Pressure IP 1 A 0305 01I, RCS Ch. A Flow Calibration IP 1 A 0305 01E, RPS Ch. A Temperature Calibration IP 2 A 0305 011, RPS Ch. "A" Flow Calibration IP 3 A 0305 01 H, RPS Temperature Calibration IP 0 A 0202 01 D, Emergency HP Injection Flow Instrument Calibration IP 0 A 0202 01F, LST Level Instrument Calibration IP O A 0203 01 A, BWST Level Instrument Calibration IP O A 0203 01 A, RB Emergency Sump Level Instrument Calibration IP 0 A 0231 07, CS Concentrated Boric Acid Storage Tank Level and Temperature

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-5 IP 1 A 0340 04, Absolute Position Indicator Calibration IP 0 A 036101 A, Monitor System Calibration IP 0 A 0210 04, Auto Gas Analyzer Instrument Calibration The procedures and calibration results were reviewed to verify:

Reviews and approvals were being conducted, and data was recorded and evaluated.

Test instruments were listed and identified in test results.

Adherence to Technical Specifications requirements and limiting conditions for operations.

Technical contents were correct and verification of return of equipment to service and removal of test equipment was being done.

The inspectors conducted an inspection of the following measuring and

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test equipment storage facilities and records:

Instrumentation and control standards laboratory.

Measuring and test tool storage and issuing room.

These facilities were inspected to verify:

That standard test instruments were labeled and included in the calibration program.

Instruments were being calibrated on schedule and labeled with cal.bration status.

Storage facilities were proper for protecting the equipment.

Certification and calibration records were available and being maintained for test equipment.

The inspectors used one or more of the following acceptance criteria i

for evaluating the above items in the calibration program:

VEPCO Topical Report - 17.2.12 Control of measuring and Test Equipment

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-6 ANSI N45.2-1971 ANSI N18.7-1972 Inspector Judgement Quality Assurance Program Within the areas inspected no items of noncompliance or deviations were identified.

In one area inspected the inspectors found resistance decade boxes not under quality assurance control as required by Section 13 of ANSI N45.2 (1971). The licensee reported that this equipment was regularly calibrated, but had been inadequately left out of the regular l

calibration program for instruments used for safety-related systems.

The licensee will place this equipment under safety system's instrument calibration control and NRC will verify this at a subsequent inspection.

This item will remain unresolved pending the incorporation of the decade boxes into the calibration program.

I (269/78-12-01,270/78-11-01,287/78-11-01) 7.

Inspection of Chemistry Laboratory 4

An inspection of the chemistry laboratory and associated equipment was j

conducted by the inspector to verify that procedures and equipment were

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available for determining coolant chemical concentrations and status j

as required by Technical Specifications. The method of preparation and verification of shelf life of chemical standards were also reviewed.

The inspector used the requirements of 'the Technical Specifications for conducting this inspection.

Within the areas inspected no items of noncompliance or deviations were identified.

8.

Inspection of Control Room Operations The inspector toured the control room and reviewed the plant status and operations in progress with the operators. During this inspection Unit No. I operators were conducting a pressurization test on the steam generators to check for leaks following tube plugging.

The inspector used the requirements of the Technical Specifications for performing this inspection and review.

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 I-7 Within the areas inspected no items of noncompliance or deviations were i

identified.

9.

Control of High Radiation Areas During a tour of the facility the inspector noted a dewatered resin cask outside the Unit 2 auxiliary building. Discussions with licensee personnel indicated the cask had been moved from auxiliary building on May 9, 1978.

A survey conducted at 11:00 a.m. on May 9, indicated general area readings of 100 mrad /hr., cask bottom 1,000 mrad /hr., cask side 200 mrad /hr. A radiation control boundary was established around the cask. The cask was then left in a unsupervised condition until about noon on May 11, 1978. At that time the cask was placed under the direct surveillance of a security guard.

10 CFR 20.203 requires, in part, that high radiation areas either be directly surveilled to prevent unauthorized entry or be locked and ala rmed. The absense of either direct surveillance or locks and alarms constitutes an item of noncompliance with 10 CFR 20.203.

This item (270/78-11-02)is an infracti< 1.

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RII Report Nos. 50-269/78-12, 50-270/78-11 and 50-287/78-11 II-1 l

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DETAILS I_

Prepared by:

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D. R. McGuire, Physical Security Date i

Specialist Security and Investigation Section Safeguards Branch CLt (c ll &

C. L. Davis, Physical Security Date Intern l

Security and Investigation Section Safeguards Branch I

Dates of Insp tio:1: Ma 1 -12, 1978 Approved by:

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C.E.Miderson,ActingChief Date Security and Investigation Section Safeguards Branch 1.

Persons Contacted R. Koehler, Supervisor of Technical Services (Acting Station Manager) l J. Suffick, Contract Services Supervisor Capt. G. Cooper, Southern Security Guard 2.

Followup on Immediate Action Letter f

The inspectors conducted a followup of the Immediate Action Letter l

sent to Duke Power Company by Region II on March 17, 1978. Wile on site the inspectors walked through the facility and observed access controls, protected area barriers, and guard personnel.

The inspectors were informed that Duke Power Compatiy had recently concluded a QA audit of Oconee's security program. The audit was conducted from April 3, 1978 through May 8, 1978 and required 885 manhours by four licenree auditors.

The findings of the audit were to be issued by DPC on May 12, 1978. The audit findings and correc-tive actions will be reviewed during future inspections.

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