ML20027B001

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Corrected IE Insp Repts 50-321/82-20 & 50-366/82-20 on 820526-0621.Noncompliance Noted:Failure to Follow Procedure for Plant Svc Water Valve Locking & Tech Specs for RHR Operability
ML20027B001
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 07/22/1982
From: Brownlee V, Holmesray P, Rogers R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20027A989 List:
References
50-321-82-20, 50-366-82-20, NUDOCS 8209160253
Download: ML20027B001 (5)


See also: IR 05000321/1982020

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Report Nos. 50-321/82-20 and 50-366/82-20

Licensee: Georgia Power Company

P.O. Box 4545

Atlanta, GA 30302

Facility Name: Hatch 1 and 2

Docket Nos. 50-321 and 50-366

License Nos. DPR-57 and NPF-5

Inspection at Hatch site near Baxley, Georgia and Licensee requested management

meeting at NRC Region II Off ce, Atlanta, Georgia

Inspectors:

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R. F. Rogers

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Date Signed

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P. Holmes-Ray ~

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Date Signed

Approved by:

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V. Jf/ Brownlee, Syffon rgrief, Division of

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Project and Res1d6nt Programs

SUMMARY

Inspection on May 26 - June 21, 1982

Areas Inspected

This inspection involved 194 inspector-hours on site in the areas of Technical

Specification compliance, operator performance, overall plant operations, quality

assurance practices, station and corporate management practices, corrective and

preventive maintenance activities, site security procedures, radiation control

activities, surveillance activities, previous enforcement items, and Licensee

Event Reports.

Results

Of the 11 areas inspected, no violations or deviations were identified in nine

areas, two violations were identified in two areas (Failure to follow procedure

- PSW valve locking, paragraph 5; Failure to follow Technical Specifications - RHR

operability, paragraph 6).

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DETAILS

1.

Persons Contacted

Licensee Employees

  • H. C. Nix, Plant Manager
  • T. Greene, Assistant Plant Manager
  • C. T. Jones, Assistant Plant Manager
  • S. Baxley, Superintendent of Operations
  • C. Belflower, QA Site Supervisor

Other licensee employees contacted included technicians, operators,

mechanics, security force members and office personnel.

  • Attended site exit interviews

2.

Exit Interview

The inspection scope and findings were summarized on June 9 and 21, 1982,

.with those persons indicated in paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings

a.

Violations

(Closed)(366/81-23-01) Failure to notify the NRC operations center

within one hour.

The corrective actions described in the licensee's

response of November 24, 1981 have been completed. This item is

closed.

(Closed)(366/81-34-03) Failure to notify the NRC regional office

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The corrective measures discussed in the licensees

response dated March 2,1982 have been completed. This item is closed.

(Closed)(321/81-28-01,03,06) Failure to review reports and documents

in accordance with Technical Specifications requirements. The

corrective actions described in the licensee's response dated April 22,

1982 have been implemented. These items are closed.

4.

Unresolved Items

Unresolved items were not identified during this inspection.

5.

Plant Tours (Units 1 and 2)

The inspector conducted plant tours periodically during the inspection

interval to verify that monitoring equipment was recording as required,

equipment was properly tagged, operations personnel were aware of plant

conditions, and plant housekeeping efforts were adequate. The inspector

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also determined that appropriate radiation controls were properly estab-

lished, critical clean areas were being controlled in accordance with

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procedures, excess equipment or material is stored properly and combustible

material and debris were disposed of expeditiously. During tours the

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inspector looked for the existence of unusual fluid leaks, piping vibra-

tions, pipe hanger and seismic restraint settings, various valve and breaker

positions, equipment caution and danger tags, component positions, adequacy

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of fire fighting equipment, and instrument calibration dates. Some tours

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were conducted on backshifts.

On June 18, 1982, during an inspection at the intake structure, the

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inspector noted that the cooling water isolation valve for ID plant service

water (PSW) pump was not locked open as required by HNP-1-1200, Plant

Service Water. This valve was also required to be double verified in the

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proper position by the procedure. The required chain locking device was

laying on the process pipe next to the valve. The inspector requested that

the valve position be immediately verified by the licensee and it was found

to be partially open. A similar situation was reported in IE report

50-321/82-12 issued on April 8,1982 involving another cooling water valve.

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This failure to maintain the valve properly is a repeat violation

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(321/82-20-01).

6.

Technical Specification Compliance (Units 1 and 2)

During this reporting interval, the inspector verified compliance with

selected limiting conditions for operations (LC0's) and results of selected

surveillance tests. These verifications were accomplished by direct obser-

vation of monitoring instrumentation, valve positions, switch positions, and

review of completed logs and records. The licensee's compliance with

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selected LC0 action statements were reviewed on selected occurrences as they

happened.

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On April 19, 1982, on a control room tour, the inspector noted that the

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vertical section of panel 2H11-P601 over "A" loop Residual Heat Removal

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(RHR) was not energized as all instrumentation indicated zero. The inspec-

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tor pointed out to the operator on shift that all flow indication had been

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lost on the RHR loop which was required to be operable during fuel loading.

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The operator was not aware that the panel had been de-energized. The system

was then declared inoperable (LER 50-366/82-30 refers) and fuel loading

stopped. Further investigation by the inspector indicated that this panel

section which contains flow indication for both RHR and RHR service water had

been de-energized for approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. The licensee's failure to enter

the LC0 and suspend refueling activities in a timely manner is a violation

(366/82-20-01). The existence of this condition over three shifts without

notice or comment by licensed operators is also of concern.

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7.

Plant Operations Review (Units 1 and 2)

The inspector periodically during the inspection interval reviewed shift

logs and operations records, including data sheets, instrument traces, and

records of equipment malfunctions.

This review included control room logs

and auxiliary logs, operating orders, standing orders, jumper logs and

equipment tagout records. The inspector routinely observed operator alert-

ness and demeanor during plant tours. During normal events, operator

performance and response actions were observed and evaluated. The inspector

conducted random off-hours inspections during the reporting interval to

assure that operations and security remained at an acceptable level.

Shift

turnovers were observed to verify that they were conducted in accordance

with approved licensee procedures.

Within the areas inspected, no violations or deviations were identified.

8.

Physical Protection (Units 1 and 2)

The inspector verified by observation and interviews during the reporting

interval that measures taken to assure the physical protection of the

facility met current requirements. Areas inspected included the organi-

zation of the security force, the establishment and maintenance of gates,

doors and isolation zones in the proper condition, that access control and

badging was proper, and procedures were followed.

Within the areas inspected, no violations or deviations were identified.

9.

Review of Nonroutine Events Reported by the Licensee (Unit 2)

The following Licensee Event Reports (LERs) were reviewed for potential

generic impact, to detect trends, and to determine whether corrective

actions appeared appropriate. Events which were reported immediately were

also reviewed as they occurred to determined that Technical Specifications

were being met and that the public health and safety were of utmost con-

sideration. Asterisked reports were followed up indepth onsite.

LER No.

Date of Report

Description

50-366/81-92

10/27/81

Rod out permissive lost

50-366/81-94

10/20/81

2C D/G start failure *

50-366/81-99

10/22/81

Radiation monitor lost

50-366/81-100

11/12/81

2C D/G start failure *

50-366/81-105

12/01/81

L.P. alarms CRD hydraulic control

units

50-366/81-106

12/04/81

SBGT Train 2T46-D0018 failed to

start *

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50-366/81-107

12/01/81

Torus /RB vacuum bkr inoperable *

50-366/81-108

12/01/81

Rx pressure switch out of

calibration *

50-366/81-109

12/01/81

RB/ Torus vacuum bkr opened on high

d/p

50-366/81-110

12/01/81

RHR 2C inop/ valve 2E11-F004C

inoperable

50-366/81-111

12/15/81

HPCI inoperable *

50-366/81-113

12/10/81

Test Procedure change not approved

by plant management

50-366/81-114

12/17/81

LPCI injection valve failed *

50-366/81-117

12/17/81

LPCI inverter failed

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50-366/81-118

12/15/81

DW temperature recorder inoperable

50-366/81-119

12/31/81

MS line rad instrument HI-HI trip

OOC

50-366/81-122

12/29/81

Pressure Control Valve 2E11-F126A

failed to operate

50-366/81-123

12/22/81

SBGT train inoperable

50-366/81-125

01/08/82

RCIC inoperable *

50-366/81-126

01/05/82

Hydrogen recombiner inoperable

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50-366/81-128

12/31/81

Radwaste door 2RW21 found open

50-366/81-129

01/07/82

2C D/G inoperable due to engine

failure *

50-366/81-130

01/07/82

L.P. alarms on CRD hydraulic units *

50-366/81-132

01/19/82

HPCI injection alarm inoperable

50-366/81-133

01/19/82

Rx water shroud level switch 00C

50-366/81-134

01/19/82

2C D/G tripped on attempt to sync

to bus *