IR 05000219/1986029

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Safety Insp Rept 50-219/86-29 on 860930-1003.No Violations Identified.Major Areas Inspected:Effluent Control Program, Including Status of Previously Identified Items,Mgt Controls,Monitor Calibr & Surveillances
ML20213D847
Person / Time
Site: Oyster Creek
Issue date: 10/30/1986
From: Mark Miller, Pasciak W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20213D841 List:
References
50-219-86-29, NUDOCS 8611120280
Download: ML20213D847 (4)


Text

{{#Wiki_filter:. _.. . . _ - - _ _ _ - _ _ _ _ . f . . . s U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

50-219/86-29 Docket No.

50-219 License No.

DPR-11 Priority Category C - ' Licensee: GPU Nuclear Corporation Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731 Facility Name: Oyster Creek Nuclear Station Inspection At: Forked River, New Jersey Inspection Conducted: SeptemL2 30 - October 3,1986 Inspectors: _ . /19 a M lc 3O M. 7. Mil r, R ation Speciali U [date[ N I Approved by: _ l J.

/~r cq d f.e/3o &L ' W.~ J. Pdh.,ciaY, Chief / dap ' Effluchts Radiation Protection Section e Inspection Summary: Inspection on September 30-October 3, 1986 (Inspection Report No. 50-219/86-29) Areas Inspected: Routine unannounced safety inspection of the licensee's Effluent Control Program including: status of previously identified items, management controls, effluent release records, testing of air cleaning systems, monitor calibration and surveillances.

Results: No violations were identified.

. 8611120280 861104 PDR ADOCK 05000219 G PDR l J

. . . . " . .. . _ . ' ___ ... .- DETAILS 2E 1.0 Fersonnel Contacted . . 1.1 General Public Utilities ' ' ..

  • P. Fiedler, Vice President and Director - Oyster Creek
  • J. Sullivan, Plant Operations Director

_

  • D. Turner, Radiation Control Director

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  • C. Halbfoster, Manager, Plant Chemistry, Acting Manager, Radwaste

- . Operations D. Chandler, Engineering Process and Instrumentation j ' J. Charterina, Plant Engineering r W. Dunphy, Senior Chemist R. Hillman. Senior Chemist C. Hagar, Plant Engineering -== J. Stevens, Process Instrumentation E,,i 1.2 NRC Per_sonnel s ' E L

  • B. Bateman, Senior Resident Inspector, OC

-

  • J. Wechselberger, Resident Inspector, OC
  • denotes attendance at exit interview on October 3, 1986.

2.0 Status of Previously Identified Items (0 pen) Inspector Follow-up Item 50-219/86-01-01: Improvements to Post ' Accident Sampling System (PASS) including: verification of aliquot gh_ . delivered by ball valve for a diluted sample; procedure guidance to reduce exposure, evaluation of pressure measurements to ensure critical y flow, and use of 0 rings between the cartridges in the iodine sampling ' canister.

The licensee addressed the required procedure changes to __ ensure critical flow was established at time of sampling, and to reduce C" exposure while drawing a sample of cissolved gas.

License action of the [p other recommended improvements had not been completed.

- (0 pen) Inspector Follow-up Item 50-219/86-01-02: Additional improvements - to PASS including performing six month sur;eillance on PASS; establishing =,_ calibration and spare parts program for PASS instrumentation; QA Program lEE verification of sample flow.

The inspector noted that the PASS had been -]h[ for PAS-cask; and use of radiation monitors and panel indications for -- added to the surveillance schedule.

However, the frequency was denoted [[[ as a one year cycle.

The license had previously committed to a six month ne-J schedule in a licensee submittal to NRR on March 6, 1984.

The license PE stated a six month surveillance would be conducted as previously com-mitted.

The license revised procedure 831.10 to instruct the operator to

verify the proper panel indication was illuminated to ensure sample flow.

The license also issued procedure 351.48 " Post Accident Sampling Cask"

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Y .. hy; With regard to the other concerns, the licensee's action had not been

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t ....n iO 3.0 Radioactive Waste Management and Effluents Control . ,. R.'. y.

. < '.1 The responsibility for the administration, direction and proper processing

cQ of radioactive waste and effluents at Oyster Creek presides with the ('

-g Radwaste Operations and Chemistry Manager. The inspector discussed the .) licensee's Radwaste Operations and Effluents Control Program for the . J j > ' period February 1985 to date.

L.. t.[.- 1 The licenseestated that no overboard liquid releases had been made for 21 , j y months (since December 1984). The license stated that the Water Balance s i.4..K Program had been successful in tracking system inleakage, identifying .;

, mechanical problems and operator errors.

Daily review and trending of

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data was being performed by the Radwaste Engineer.

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With regard to gaseous effluent releases, gaseous radioactivity, although Q.' below Technical Specifications, had significantly increased in late 1985, .; y.; peaking in December 1985 and remaining above normal until the outage and a . !; subsequent isolation of the off gas system in March 1986.

The license

'

' &$g; - stated that higher radioactivity was attributed to leaking fuel, bypass . f a - leakage from the Augmented Off-Gas (A0G) Facility and down tine of the - v . 93.1 A0G.

The license replaced the leaking fuel (47 bundles), repaired the

]~q bypass valve and improved the A0G Facility equipment during this outage.

1, "i The inspector stated that gaseous effluents data would be reviewed within ' Gj six months upon completion of the outage.

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>. 4.0 Effluent and Process Moaitor Calibration and Surveillance Program

.

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M.C The inspector examined the liquid and gaseous effluent and process monitor

'l calibrations, sampling program, and functional test records to determine

j

% compliance with Technical Specification 4.6, " Radioactive Effluents." The Q inspector noted that the liquid overboard discharge monitor had been out

1? of service. However, no discharges had been made. With regard to the 7. E Reactor Building Closed Cooling Water and Service Water System monitors, g.

yp both monitors were subjected to high radiation background levels.

The

'g{ licensee stated these monitofs were being evaluated to reduce background y and to meet. the new Radiological Effluent Technical Specification Lower

.g; Level of Detection (LLD).

I v. ;.- , ' / With regard to planning for a thorough implementation of the RETS, the f licensee had completed most of the surveillance procedures, were upgrading . N.O the gaseous effluent monitoring systems and developing training courses.

.i . (l f Within the scope of this review, no violations were identified.

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_ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ - - _- _ _ oe .

5.0 Air Cleaning System Testing The inspector reviewed the licensee's air filtration system testing with regard to Technical Specification 4.5.K, Standby Gas Treatment System (SGTS). The testing of the air filtration systems was conducted by the licensee,with the exception of laboratory testing of carbon absorber filters, which is performed by a contractor. The inspector reviewed the completed surveillance procedures for the period, May 1983 through August 1986, including; 651.1.006, SGTS Charcoal Filter Radiological Methyl Iodine Removal Efficiency Test, 651.3.002, SGTS Particulate Filter In-Place Leak Test, and 651.4.001, SGTS Testing.

In addition, the con-tractor laboratory results were reviewed for the above period.

Within the scope of this review, no violations were identified. However, the inspector noted that the latest methyl iodine test for charcoal efficiency for the SGTS A-train had failed at 80%. The acceptance criteria is 90%. Although Technical Specification related actions were taken in a timely manner, the cause of the failure was not investigated.

Further, the charcoal efficiency for the B train was not determined to ensure the 90% efficiency had been maintained.

The inspector discussed this concern with the Chemistry Manager and Plant Operations Director.

During the exit interview, the licensee stated that a test canister - - would be collected at the first opportunity, when the B train would be - available.

The results of the methyl iodine test will be reviewed during a subsequent inspection (50-219/86-29-01).

6.0 Exit Interview The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on October 3, 1986.

The inspector summarized the purpose, scope and findings of the inspection. At no time during this inspection was written material provided to the licensee by the inspectors.

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