IR 05000321/1989030

Insp Repts 50-321/89-30 & 50-366/89-30 on 891030-1103. Violations Noted.Major Areas Inspected:Actions on Previous Insp Findings

ML19332F767
Person / Time
Site:	Hatch
Issue date:	12/07/1989
From:	Jape F, Casey Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19332F765	List: IR 05000321/1989030 ML19332F764 ML19332F766
References
50-321-89-30, 50-366-89-30, NUDOCS 8912180229
Download: ML19332F767 (6)

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hA#pmKEro ' g REGION il i*

UNtTED STATES

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'o NUCLEAR REGULATORY COMMISSION

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101 MARIETTA STREET,N.W.

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ATLANT A, GEORGI A 30323

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Report Nos.: 50-321/89-30,and 50-366/89-30 Licensee: Georgia Power Company P. O. Box 1295 Birmingham, AL 35201 Docket Nos.:' 50-321 and 50-366 License Nos.:

DPR-57 and NPF-5 Facility Name:' Hatch 1'and 2 Inspection Conducted: October 30 - November 3, 1989 Inspectors:

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Date Signed

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L Inspector:

W. Poertner

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, Approved by:). Jape'. Section Chief QualityPerformanceSecti[on//

Date Signed l

Operations Branch

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Division of Reactor Safety l

Ls SUMMARY-L-

. Scope:

.This routine, unannounced inspection was conducted in the area of Actions'on Previous. Inspection Findings.

Results:

In the area inspected, one violation was identified (paragraph 4).

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.. violation -involved inadequate design controls related to the preparation..

review, and. approval of DCR 85-007,' Revision 1, which installed commercial

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grade. relays on the 120V Class IE instrument system.

8912180229 891208

PDR ADOCK 05000366

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l REP %T DETAILS 1.

Persons Contacted Licensee Employees

• K. Brietenbach, Engineering Support S. Brunson, Senior Plant Engineer

• R. Davis QA Audit Supervisor W. Flowers, Plant Engineer

• J. Haninonds, Nuclear Safety and Compliance Supervisor

• H. Nix, General Manager - Plant Hatch J. Robertson, System Engineering Supervisor

• L. Summer, Assistant General Manager Plant Hatch

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• S. Tipps, Nuclear. Safety and Compliance Manager Other licensee employees contacted during this inspection included engineers and administrative personnel.

NRC Resident Inspectors

• J. Menning - Senior Resident Inspector

• R. Musser

' Resident Inspector

• Attended exit interview 2.

Action on Previous Inspection Findings _(92702)

L (Closed) Violation 50-321/366-87-31-07, Part A. RWCU System Inadequate l-Post Maintenance Testing.

l The licensee response dated July 5,1988, was considered acceptable by Region II.

The inspector reviewed DCR 85-007, Revision 1, installed on January 12, 1935, and verified that this plant modification. corrected the logic design

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deficiency which prevented simultaneous closure of the RWCU system primary l-containment isolation valves, 1G31-F001 and IG31-T004.

Additional corrective actions implemented by the licensee included preparation and implementation of procedures AG-MGR-27-0687N, " Root Cause Determination",

Revision 1; and 95IT-0TM-001-05, " Maintenance Work Order Functional Test Guideline", Revision 1.

Procedure AG-MGR-31-0787N,." Event Investigation",

referenced in the licensee response, has been replaced by 10AC-MGR-012-0S,

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" Plant Event Analysis and Resolution Program", Revision 0.

The inspector reviewed the above procedures and verified that the corrective actions l

stated in the licensee response have been completed.

l This item is closed.

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j (Closed) Violation 50-321/366-89-08-01, Failure to perform timely corrective actions relative to emergency generator fuel oil problems identified in various QA audits.

The inspector reviewed the licensees response, dated _ September 14, 1989,

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and verified that procedure 62CH-SAM-003-0S, " Diesel Fuel Oil Sampling",

had been revised to change the Fuel Oil Storage tank sampling methodology to comply with ASTM D270-65 requirements and that the procedure had been

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revised to require that the fuel oil in the storage tanks be analyzed periodically to ensure that the fuel oil quality requirements of-the vendor were met.

The inspector also reviewed a management bulletin that was issued to all personnel emphasizing the importance of timely incorpo-ration of. FSAR requirements into procedure revisions when discrepancies were identified.

This item is closed, j

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The inspectors concluded that the licensee had determined the full extent L

of the violations, taken action to correct current conditions, and developed corrective actions needed to preclude recurrence of similar problems, Corrective actions stated in the licensee responses have been implemented.

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Action on Previous Inspection Findings (92701)

(0 pen)IFI 50-321/366-89-08-02, Seven Day Fuel Storage Capacity.

I The inspector verified that plant procedures have been revised to require

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175,000 gallons of fuel oil on site and that the operating and emergency procedures were revised to limit the Emergency Diesel Generators load to 13,000 kw until additional quantities of fuel oil are obtained onsite. The site has submitted a proposed TS change to reflect the increased fuel oil storage requirements. This item will remain open pending incorporatirsn of the higher fuel oil storage requirement into the plant's technical specifications.

(Closed)IFI 50-321/366-89-08-06, Revised Emergency Diesel Generator Load.

The inspector verified that Unit 2 calculation number 88-had been revised to document a brake horsepower of 520 for Plant Service Water pump 2B and that the total load calculated on Diesel Generator 2C is 3212.21 kw, which is below the maximum design limit of 3250 kw.

This item is closed.

(0 pen) IFI 50-321/366-89-08-08, Seismic Qualification of EDG Low Lubricating 011 Switches.

The licensee received a letter dated August 29, 1989, from the vendor stating that the low lubricating oil switches supplied with the Diesel Generators were Model Number 222-10 Detroit Switch pressure switches and

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that they are the same as the tested switc.

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The switches on Unit 2 are Model Number 222-10 Detroit Switch pressure switches; however, the switches installed on Unit 1 are Allen Bradley 836-C3 - switches.

The licensee obtained dynamic performance criteria directly from Allen Bradley and completed a seismic margins assessment on the switches and determined that the switches are adequate for an earthquake at least twice the magnitude of the Unit 1 design basis earthquake.

The licensee has also contacted the seismic lualification utility group to include the Allen Bradley switches in testing that was scheduled to be performed in October 1989 to provide further quantitative seismic qualification documentation.

Subsequent to the licensee's evaluation, the vendor determined that their files did not contain seismic qualification documentation for the Allen Bradley switches.

This item will remain open pending receipt of the seismic qualification

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documentation for the Allen Bradley pressure switches.

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(Closed)IFI 50-321/366-89-08-12, DC Battery Sizing.

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The inspector verified that Battery sizing calculation numbers 82 and 83, for Units 1. cd 2, had been revised to incorporate a design basis temperature or 45 degrees Fahrenheit.

This item is closed.

(Closed)IFI 50-321/366-89-08-18 Fuel Oil Sampling Program.

The ' inspector reviewed procedure 62CH-SAM-003-0S, " Diesel Fuel Oil Sampling", and verified that the following. improvements to the procedure had been incorporated:

Upgraded chemical specifications for Emergency Diesel Generator fuel oil to include'the requirements of the Emergency Diesel Generator manufacturer.

Sampling and analysis requirements for fuel oil delivery trucks prior to off-loading to the main storage tanks, previously covered by procedure 62CH-SAM-029-0S, Instructions for obtaining representative samples from the fuel oil storage tanks in accordance with ASTM D270-65, as required by Technical Specifications.

Sampling and analysis requirements for fuel oil day tanks.

' Instructions for the addition of biocide to the main fuel oil storage tanks, previously covered by Chemistry Standing Order 50-CHM-05-1288, December 21, 1988.

• Sampling and analysis requirements for the fire pump and Security Emergency Diesel Generators.

This item is close ~., :

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(Closed)IFI 50-321/366-89-08-20, Access to Vital Areas

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The inspectors reviewed the. closure package and determined that keys to

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vital area doors are maintained in the shift supervisors office for use in

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. emergencies.

High usage areas will have security personnel posted in-

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'the area on a loss of power to the security system.

This item is closed.

(Closed)IFI 50-321/366-89-08-22, Accuracy of Local Frequency Meter.

The inspectors determined that the frequency meter ir, question (1R43-R766C)

was replaced on June 21, 1989, and verified that the functional test

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associated with the plant work order required verification that the meter was operating properly while the associated diesel was running.

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licensee also increased the calibration frequency of the local meters fromL 60 months to 24 months.

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This item is closed.

(Closed)IFI 50-321/366-89-08-26 Plant Service Water Valve Lineup.

The licensee evaluated whether valves F553A and F553C, the Unit 1 Emergency Diesel Generator IA and IC Plant Service Water discharge valves, should be included in a monthly valve position verification procedure and whether these valves should be-locked open. The licensee' determined that (_

the valves did not require a monthly position verification and were.not I

required to be locked open. This determination was made based on the fact l

that the diesels are run monthly and the Unit I technical specifications do not require a monthly valve position verification of the Plant Service l

Water system.

This item'is closed.

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'(Closed) IFI 50-321/366-89-01-04, Bottom Sampling of EDG Fuel Oil Day and Storage Tanks.

The inspector verified that procedure 62CH-SAM-003-0S, " Diesel Fuel Oil Sampling", had been revised to require bottom sampling of the Diesel Fuel

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Oil Day Tanks and the Fuel Oil Storage Tanks.

This item is closed.

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Inadequate Design Controls Independent design review of DCR 85-007 revealed that this plant modification installed two commercial grade Agastat Time Delay relays on the Class IE 120V 60HZ instrument buses A and 8.

The detailed safety evaluation concluded that the use of non-safety related relays for the RWCU system primary containment isolation valves did not impact plant safety.

The safety evaluation further concluded that the relays would remain structurally intact during a seismic event and would not affect safety related circuits in the same pane y

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The inspectors determined, however, that a design basis for the statement concerning seismic adequacy of TDRs G31-R616C and D did not exist.

The licensee has neither (1) performed on engineering evaluation to determine the failure mode of the commercial grade relays and its effect on other safety related components within-the panels, nor (2) performed a seismic analysis or test to verify the seismic adequacy of the relays.

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these design engineering activities are mandatory requirements per IEEE-l 308-1974 and IEEE 344-1974 respectively.

Review of drawing number 10-502 i

Sheet H-17176, Figure 3, showed'that failure of TDR G31-R616C coil, with

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consequent blowing of the installed fuse, de-energizes alarm Unit G31-N603A and the associated analog computing elements located in panel H11-613.

Similarly, an electrical fault precipitated by failure of TDR G31-R616D coil prevents alarm unit G31-N603B from performing its design function.

This failure to provide adequate design-controls regarding the use of commercial grade relays on Class 1E 120 VAC instrument power. supply is-identified as violation 50-321/366-89-30-01, Inadequate Design Controls Related to the Use of Commercial Grade Relays.

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Exit Interview

l The inspection scope and results were summarized on November 3,1989,

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with those persons. indicated in paragraph 1.

The inspectors described I

the areas inspected and discussed in detail the inspection results listed below. Proprietary information is not contained in this report.

Violation 50-321/366-89-30-01. Inadequate Design Controls, related to the installation of two commercial grade Agastat relays listed in DCR 85-007, was discussed with the licensee.

Licensee management stated at the exit interview that this violation would be denied.

However, in subsequent discussions with the licensee by phone on December 1, 1989, the issue was clarified and the licensee stated that the violation may be valied. A review will be performed upon receipt of the report.

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Acronyms and Initialisms API

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ASTM -

Direct Current DC

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-Design Change Request DCR

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Emergency Diesel Generator EDG

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FSAR -

Final Safety Analysis Report IEEE -

Inspector Followup Item IFI

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-Kilowatt KW

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RWCU -

Reactor Water Clean-Up Technical Specification TS

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VAC -

Voltage Alternatin Current

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