IR 05000259/1985027

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Insp Repts 50-259/85-27,50-260/85-27 & 50-296/85-27 on 850603-07.No Violation or Deviation Noted.Major Areas Inspected:Liquid & Gaseous Radwaste Mgt
ML18029A630
Person / Time
Site: Browns Ferry  
Issue date: 06/19/1985
From: Mongomery D, Montgomery D, Stoddard P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18029A629 List:
References
50-259-85-27, 50-260-85-27, 50-296-85-27, NUDOCS 8507100271
Download: ML18029A630 (10)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323 JUN p p }yg Report Nos.:

50-259/85-27, 50-260/85-27 and 50-296/85-27 Licensee:

Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Docket Nos.:

50-259, 50-260 and 50-296 II Facility Name:

Browns Ferry 1, 2, and

License Nos.:

DPR-33, DPR-52, and DPR-68 Inspection Conducted:

June 3-7, 1985 Inspector:

A/4 P.

.

toddart Approved by:

D.

M. Montgomery, Sect n Chief Emergency Preparedness and Radiation Protection Branch Division of Radiation Safety -and Safeguards Date Signed Date Signed SUMMARY Scope:

This routine, unannounced inspection entailed 36 inspector-hours at the site during normal duty hours, in the areas of liquid and gaseous radwaste management.

Results:

No violations or deviations were identifie REPORT DETAILS

" Persons Contacted Licensee Employees

"J.

A Coffey, Plant Site Director

~J.

F. Swindell, Plant Superintendent, Operations and Engineering

"W.

C. Thomison, Results Supervisor

"J.

R. Clark, Chemistry Supervisor D.

C.

Mims, Engineering Group Supervisor

~A; C. Smith, Radwaste Engineer J.

Pleva, Chemical Project Engineer K. Skinner, gA Evaluator D.

Nye, Engineer R.

Shiremen, Radiochemical Lab Analyst

'.

E. Burns, Instrument Maintenance Supervisor D. Nix, Engineer E. Scott, Engineer H.

C.

Le, Shift Technical Advisor C. J. Wright, Planning and Scheduling Coordinator

~J.

D. Carlson, gA Supervisor NRC Resident Inspectors

~C.

Brooks, Resident Inspector G.

L. Paulk, Senior Resident Inspector

~Attended exit interview Exit Interview The inspection scope and findings were summarized on June 7, 1985, with those persons indicated in paragraph 1 above.

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.

Licensee Actian on Previous Enforcement Matters This subject was not addressed in the inspection.

Audits and Appraisals (84723, 84724)

Technical Specifications 6. 2. A. 1 and 6. 2. A. 8 require the licensee's Nuclear Safety Review Board to conduct audits of unit activities.

The inspector reviewed audits involving liquid and gaseous radwaste management topics in audit reports CH-8400-15, November 26, 1984; CH-8400-18, October 5, 1984;

BF-8400-13, July 13, 1984; BF-8400-07, May 1984; and BF-8400-14, August 24, 1984.

No violations or deviations were identified.

5.

Major Changes to Plant Radwaste Treatment Systems (84723, 84724)

The inspector discussed plant radwaste treatment systems with plant personnel and toured portions of the liquid and gaseous radwaste systems accompanied by licensee personnel.

The inspector also reviewed the Semi-Annual Effluent Release Reports for January -

June 1984 and July-Oecember 1984 which, under the guidance in Regulatory Guide 1.21, should contain reports of major changes to plant radwaste systems.

On the basis of the above, the inspector determined-that no major changes had been made to plant radwaste treatment systems.

No violations or deviations were identified.

6.

Procedure Reviews (84723, 84724)

-Technical Specification 6.3 requires the licensee to prepare, approve, and adhere to procedures including, under the category of radiation control, procedures covering liquid and gaseous radwaste management.

The inspector noted that the licensee had accomplished revisions to a major portion of procedures and instructions since the last inspection (84-25, July 23-27, 1984).

The inspector reviewed the following procedures and instructions:

SI-4.8.A.6, Release Procedure, May 14, 1985 SI-4.8.A.7, Appendix I Oose Calculations, Liquid Effluents, February 15, 1984 SI-4. 8. 1. a, Airborne Effluent Release Rate, May 1, 1985 SI-4.8.B. l.b, Unmonitored Airborne Effluent Streams, February 12, 1985 SI-4.8.B.2, Airborne Effluent Analysis, May 7, 1985 SI-4.8.B.3, Airborne Effluents, April 10, 1985 SI-4.8.B.A-1, Airborne Effluents, Main Stack Monitoring Systems, May 7, 1985 SI-4.8.B.4-2, Turbine Building Vent Monitoring Systems, May 25, 1984 SI-4. 8. B.4-3, Reactor Building Vent Monitoring Systems, April 23, 1985 SI-4. 8. B. 4-4, Radwaste Building Exhaust Vent Monitoring System, May 7, 1985

SI-4. 8. B. 5, Appendix I Dose Calculations, Airborne Release, May 25, 1984 TI-38, Sections 1301-1313, and Appendix A, March 19, 1985 TI-15, Airborne Effluent Release Rate Determination, May 7, 1985 TI-16, Dioctylphthalate (DOP) Test of High Efficiency Particulate Filters, August 24, 1984 TI-47, Offsite Dose Calculation Manual, November 20, 1984 TI-45, Liquid Process Radiation Monitors, March 19, 1985 All of the above procedures and instructions had been reviewed and approved by the appropriate management, as provided in the specification.

No violations or deviations were identified.

7.

Reactor Coolant Chemistry and Radiochemistry (84723, 84724)

Technical Specification 4.6.B establishes sampling and analysis requirements for reactor coolant, including conductivity, chloride, pH, isotopic analysis for I-131, I-132, I-133, and I-134, and dose equivalent I-131.

The inspector reviewed sampling and analytical procedures and instructions and reviewed selected logs and surveillance instructions for reactor coolant determinations from the period of August 1, 1984, through June 1,'1985.

No violations or deviations were identified.

8.

Radioactive Liquid Wastes and Liquid Effluent Treatment Systems (84723)

Technical Specifications 3/4.8.A. 1 through 3/4.8.A.5 and Table 4.8-A define the operating requirements, radioactive effluent limits and surveillance requirements for the liquid radwaste treatment system.

The inspector reviewed sampling and analytical procedures and instructions and reviewed selected logs and completed surveillance instructions for liquid radwaste effluent releases for the period of August 1, 1984, through June 1, 1985.

No violations or deviations were identified.

9.

Radioactive Gaseous Wastes and Gaseous Effluent Treatment System (84724)

Technical Specifications 3.B. 1 through 3.B.8, 4.B. 1 through 4.8.4 and Table 4.8-B define the operating 'r'equirements, radioactive gaseous effluent release limits, and surveillance requirement Cl

The inspector reviewed sampling and analytical procedures and instructions and reviewed selected logs and completed surveillance instructions for the period of August 1, 1984, through June 1, 1985.

The inspector, accompanied by a

licensee representative, toured the gaseous effluent monitoring facilities and the radiochemical analytical facilities.

No violati ons or devi ati ons were identi fied.

10.

Radioactive Liquid and Gaseous Effluent Monitoring (84723, 84724)

f Technical Specifications 3.8.A.3, 3.8.8.6, 3.8.8.7, 3.8.B.8, 4.8..A.2, 4.8.A.3, 4.8.A.4.

4.8.B. 1, 4.8.B.2, 4.8.B.3, and 4.8.B.4 define the operating and surveillance requirements for monitoring, sampling, and analysis of radioactive liquid and gaseous effluent streams.

The inspector reviewed procedures and instructions for the monitoring, sampling and analysis of liquid and gaseous effluent streams and reviewed logs and completed surveillance instructions for the period August 1, 1984, through June 1, 1985.

The inspector discussed monitoring, sampling and analysis experience with licensee personnel.

No violations or deviations were identified 11.

Engineered Safety Feature HEPA and Charcoal Filtration Systems (84724)

Technical Specifications 3/4.7.B, 3/4.7.E, and 3/4.7.F define the operating and surveillance requirements for Engineered Safety Feature (ESF)

HEPA and charcoal filtration systems.

The inspector reviewed selected logs and records of ESF filter systems in-place DOP and halogen leak tests and methyl iodide retention efficiency laboratory tests of system charcoal absorbers.

No violations or deviations were identified.

12.

Records Retention (84723, 84724)

Technical Specification 6.6.B requires the licensee to retain records of gaseous and liquid radioactive material released to the environment for the duration of the operating licensee.

The inspector verified from searches of selected records of liquid and gaseous radioactive effluent releases made during the period from August 1, 1984, through June 1,

1985, that the records requieed by the Technical Specification were retained in terms of frequency and context and were accessible for recall and review.

No violations or deviations were identified.

13.

Post Accident Sampling System (92706)

The inspector, accompanied by a licensee representative, reviewed progress on modifications to equipment to be used in the interim post accident sampling system (PASS) at Units 1, 2 and 3.

These modifications, together with other modifications completed since the date of the previous inspection

(84-25, July 23-27, 1984)

were discussed with a group of licensee repre-sentatives.

During the subject discussion, licensee representatives informed the inspector that the licensee plans to perform an evaluation of the final PASS systems, which have been procured for all three reactor units but not yet installed, to determine if the PASS systems meets current criteria or if the procurement of an alternative design PASS should be recommended.

If the proposed evaluation were to conclude that the currently available PASS design is acceptable, the tentative dates for start of installation would be:

Unit 1 Cycle 8 outage, October 2, 1989; Unit 2 Cycle 7 outage, December 12, 1988; and Unit 3 Cycle 7 outage, March 24, 1988.

In the event the evaluation were to conclude that the available PASS design is not acceptable, a

new procurement and installation schedule would be developed at a later date.

No violations or deviations were identified.