IR 05000207/1978007

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IE Insp Rept 50-269/78-07,50-207/78-07 & 50-287/78-07 on 780328-13.Noncompliance Noted:Radiation Area Not Conspicuously Posted
ML19316A204
Person / Time
Site: Oconee, 05000207  Duke Energy icon.png
Issue date: 04/17/1978
From: Gibson A, Jenkins G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19316A196 List:
References
50-269-78-07, 50-269-78-7, 50-270-78-07, 50-270-78-7, 50-287-78-07, NUDOCS 7911280735
Download: ML19316A204 (5)


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Report Nos.:

50-269/78-7, 50-270/7S-7 and 50-2S7/78-7 Docket Nos.:

50-269, 50-270 and 50-287 Licensee:

Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 23242 Facility Name: Oconee Nuclear Station Inspection at:

Seneca, South Carolina Inspection conducted: Parch 28-31, 1978

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Inspector:

G. R. Jenkins

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A. F. Gibson, Chief Date Radiation Support Section Fuel Facility and Faterials Safety Branch Inspection Summary Inspec_t_lon on P.arrS 28-31, 1978 (Report Nos. 50-269/7S-7, 50-270/78-7

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and 50-2S7/_78-7)

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Routine, unannounced inspection of radiation controls i

and followup on noncompliance, unresolved, and IE Circular items.

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inspection involved about 26 inspector-hours on-site by one NRC inspecter.

Results: Of two new areas inspected, one item of noncompliance was.

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identified (Infraction:

Radiation area not conspicuously posted (7S-07-01)).

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In addition, one deviation was identified during followup on a previous item of noncompliance (Deviation:

Oil Collection Basin not sampled at 2-hour frequency (7S-07-02)).

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50-270/78-7 and 50-287/78-7 1-1

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DETAILS I Prepared by:

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G. k. Jen9'.s, nadiation Specialist Date i

Rad ia ti n support Section Fuel Fa lity and >bterials safety Branch Dates of Inspection:

Ma;c. 28-31, 197S

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A. F. Gibson, Chief Date Radiation Support Section Fuel Facility and >bterials Safety Branch 1.

Individuals Contacted

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Duke Power Company

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  • J. E. Smith, Manager, Oconee Nuclear Station
  • R. M. Koehler, Superintendent of Technical Services
  • C. T. Yongue, Station Health Physicist

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R..T. Bond, Technical-Services Engineer

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D. L. Davidson, Health Physics Supervisor G. F. Davis, Health Physics Supervisor M. D. Thorne, nealth Physics Supervisor J. A. Long, Health Physics Supervisor L. A. Blue, Associate Health Physicist S. Nickles, HP Lab Assistant J. Stewart, HP Labman T. S. Barr, Perfornance Engineer R. C. Adams, I6C Supervisor

  • Denotes those attending exit interview.

2.

Licensee Action on Previous _Inspec_ tion Findines (Open) Unresolved Item (73-12-01):

Calibration of effluent moni-

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tors. An inspector reviewed procedures and data, and discussed

with licensee representatives the progra= for correlation of radiation

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monitors with laboratory analyses.

This item remains open.

(Details I,

pa ragraph '7).

(Closed) IE Circular 76-03 (76-Cl-03):

Radiation exposure in reactor cavities. An inspector reviewed the licensce's documenta-tion as referenced in Duke's letter of November 1,1976, and had no further questions.

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RII Rpt. Nos. 50-269/78-7, 50-270/78-7 and 50-287/78-7 1-2

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(Closed) Infraction (77-01-01):

Inadequate surveys. An inspector reviewed corrective actions as stated in Duke's letter of June 24, 1977. Although the corrective actions outlined in the response appeared adequate, the inspector found that the co==itment to initially sample the oil collection basin every two hours was not carried out subsequent to a Unit 2 primary to secondary leak identified on September 27, 1977.

This is cited as a deviation in this report.

(Details I, paragraph 8).

(Closed) Unresolved Item (77-04-01):

Releases of gaseous radioactivit:.

to the auxiliary building. Through review of shift supervisor logs and survey records, and discussions with licensee representatives, an inspector evaluated health physics actions associated with auxiliary building gaseous releases on November 4, 1977, January 8, 1978, and March 27, 1978.

There were no further questions on this item.

(Closed) Inf raction (77-21-01):

Improper setpoint for R1A-45 vent gas monitor. An inspector reviewed a revision to procedure Ip/0/A/360/1C and held discussions with licensee representatives, and deter =ined that corrective actions stated in Duke's. letter of November 22,-1977, __._ _

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had been accomplished.

3.

Unresolved Items No new unresolved items were identified during this inspection.

Radiation and High Radiation Area Doors a.

During a tour of the auxiliary building on the afternoon of March 28, 1978, an inspector observed that the door to Roc =

304, solid waste drumming room, was propped open and the roon was unattended.

The door was posted with a high radiation area sign, as well as a sign with insJructions to keep the

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door closed and locked.

A health physics supervisor surveyed the room and found that, although posted as such, the roo: was no longer a high radiation area.

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Later in the tour, the inspector observed that the gate to Room 258, Unit 3 waste gas compressor room, was f ully open and t he room una t t end ed.

The gate was posted with a radiation area sign, as well as a sign with instructions to keep the gate closed and locked. With the gate open, the fronts of the signs were not visible. A licensee representative stated that a survey made earlier that day showed radiation levels in the room of 2-5 mrem /hr general area and 30 mrem /hr maximum.

The inspector identified this as noncompliance with 10 CFR 20.203(b),

which requires that each radiation area be conspicuously posted.

(78-07-01).

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IO RII Rpt. Nos. 50-269/78-7, l

50-270/78-7 and 50-287/78-7 I-3

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Upon investigation, licensee management determined that three c.

contractor employees were responsible for leaving the above described door and gate open.

Disciplinary action was taken against those employees.

In addition, the Station Manager issued a letter to all station supervisors on March 31, 1978, informing them of the incident and instructing them to caution all employees to heed station rules. The Station Health Physicist stated at the exit interview that all locked doors are checked by health physics at least once per day.

The inspector stated that corrective action appeared adequate and that no further response would be required for this iten of noncompliance.

5.

Compressed Gas Bottles During the tour of the auxiliary and turbine buildings, the inspector observed numerous compressed gas bottles which were not well secured.

The inspector noted the potential hazard of a gas bottle being knocked over and becoming a missile.

Licensee management acknowledged the inspector's comments, and stated that the item

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would be brought to the attention of the Station Safety _Co_mmittee.

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Receipt of Spent Fuel Element A spent fuel element which had been sent to Babcock and k'ilcox, Lynchburg Research Center for analysis was received back at the station on the evening of March 28, 1978.

The inspector reviewed receipt documentation and survey results, and observed an additional radiation survey of the shipment on the morning of March 29.

The inspector had no questions regarding the station's surveys and handling of the shipment.

7.

Correlation of Radiation Monitors An inspector reviewed Station Directive 3.8.6, dated 6/10/77,

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" Radiation Monitor Responsibilities", which categorizes the various

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station radiation monitors and assigns responsibility for calibration, correlation, set-points, etc.

The inspector reviewed HP/0/B/1000/60/F,

" Procedure for Correlation of Effluent RIA Monitors", dated 7/30/76.

A licensee representative stated that this procedure was not suffi-ciently detailed to accomplish its purpose, and that a draf t of an extensive revision had been completed.

He said the revised procedure was expected to be approved within about two weeks. An associtte health physicist has been assigned to develop the procedure ar.d coordinate the correlation of monitor readouts with laboratory

analyses and, where needed, coordinate the resolution of monitor problems. The inspector reviewed selected correlation data collected

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j s s RII Rpt. Nos.,50-269/78-7,

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50-270/78-7 and 50-287/78-7 I-4 i

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t under the revised (draf t) procedure for RIA-33, RIA-37, RIA-38, RIA-40, and RIA-44.

The inspector stated that this item would remain unresolved until all ef fluent and area gaseous RIA monitors have b correlated in accordance with the revised procedure, and

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reasonab.e results obtained.

(73-12-01).

8.

Sampling of 011 Collection Ba' sin Duke's letter of June 24, 19j7' /,in response to noncompliance item 1 of IE Rpt Nos. 50-269, 50-270, 50-287/77-1, stated in part that, in the event a primary to secondary leak is identified, the oil collec-tion basin is initially sampled every two hours and analyzed for tritium and gam =a isotopes. This requirement is incorporated in procedure HP/0/B/1000/62/Q, " Environmental Surveillance Following a

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Primary to Secondary Leak".

The inspector reviewed turbine building sump and yard drain (oil collection basin) sample records subsequent to an indicated Unit 2 primary to secondary leak on September 27, 1977.

Sampling of the turbine building sump appeared to be in accordance with the licensee's procedure and commitment; these samples indicated the presence of cobalt and cesiu= activity. Yard drain samples and results for September 27 and S_eptember_26 were_as J llows: _

Date Time Results 9/27 2047 No detectable activity 9/28 0001 No detectable activity 9/28 1130 Xe-133, Co-60, Cs-134 9/28 1530 co-60 9/28 1930 Cs-134 9/28 2330 No detectable activity Based on the above data, the inspector stated that the failure to collect yard drain samples at 2-hour intervals until the activity stabilized was a deviation from the commitment in Duke's letter of June 24, 1977.

(78-07-02).

9.

Exit Interview The inspector met with management representatives (denoted in paragraph 1) on March 31, 1978, and summarized the scope and findings of the inspection.

Items discussed included one new noncompliance item and a deviation from licensee commitment, as well as status of previously identified noncompliance and unresolved items. Additional discussions with management were held by telephone on April 3,1978 and April 4, 1978.

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