ML13317A729

Confirms 811106 Telcon Re 811125 Meeting W/Util at Region 5 Ofc to Discuss Noncompliance Noted in Insp of Unit 1, Enforcement & Operational History,Nrc Enforcement Policies & Actions to Be Taken.W/Draft Notice of Violation

ML13317A729
Person / Time
Site:	San Onofre
Issue date:	11/13/1981
From:	Engelken R NRC Office of Inspection & Enforcement (IE Region IV)
To:	Dietch R Southern California Edison Co
References
NUDOCS 8111190647
Download: ML13317A729 (9)

Text

NOV 1 3 1981 Docket 20, 50-361 Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention: Mr. R. Dietch, Vice President Nuclear Engineering and Operations Gentlemen:

Subject:

NRC Enforcement Conference This will confirm the telephone conversation between yourself and Mr. J. L. Crews of our staff on November 6, 1981 concerning an enforce ment conference to be held between NRC management and Southern California Edison.management at 9:00 AM on Wednesday, November 25, 1981 at the NRC Region V Office. The following matters will be discussed:

1. Noncompliance observed during recent inspections at San Onofre Unit 1.

2. Enforcement and recent operational history at Unit 1.

3. NRC enforcement policies and procedures.

4. NRC actions to be taken in the present situation.

5. Possible future actions by NRC.

6. Other matters of concern to NRC including the outstanding item status of Unit 2.

The Notice of Violation related to the last inspection which concluded on November 5, 1981 has not been finalized, however a Draft Notice of Violation is enclosed for your information. We anticipate that the meeting will take between two and three hours.

• 7. Core Support Barrel misorientatjon occurrence of October 31, 1981.

91119047811113, PDR ADOCK 05000206 G

PD OFFICE RV/jk 2)Le SURNAM WENSLAWSKI E B ON........

NG.ELKER..

DATE

/81 71 11 8*.

/

81 11/i3/81 NRC FORM 318 (10/80VNRCM 0240 OFFICIAL RECORD COPY oUSGPO:1980-329-82

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region V NOTICE OF SIGNIFICANT LICENSEE MEETING Name of Licensee:

Southern California Edison Company Name of Facility:

San Onofre Nuclear Generating Station -

Unit 1 and 2 Docket No.:

50-206, 50-361 Date and Time of Meeting:

November 25, 1981, 9:00 AM Location of Meeting:

Region V, 1450 Maria Lane, Suite 210, Walnut Creek, California 94596 Purpose of Meeting:

Enforcement conference to discuss results of recent inspection findings and operational occurrences at Unit land Management Meeting to discuss the preoperational status of Unit 2.

IE Attendees:

R. H. Engelken, Director, Region V J. L. Crews, Director, Division of Residents, Reactor Projects and Engineering Inspection A. D. Johnson, Director, Division of Enforcement and Investigation G. S. Spencer, Director, Division of Technical Inspection Licensee Attendees:

R. Dietch, Vice President, Nuclear Engineering and Operations L. T. Papay, Vice President, Advanced Engineering J. G. Haynes, Manager of Nuclear Operations K. P. Baskin, Manager, Nuclear Engineering, Safety and Licensing J. M. Curran, Manager,.Quality Assurance H. B. Ray, Station Manager D. E. Nunn, Project Manager Units 2, 3 W. C. Moody, Manager Nuclear Licensing NOTE: Attendance by NRC personnel at this IE/Licensee meeting should be made known by November 20, 1981 via telephone call to F. A. Wenslawski FTS 463-3757.

Distribution:

Cognizant Director, IE/Region - R. H..Engelken Cognizant Assistant Director,.IE:HQ - H. Thornburg, J. Sniezek Director, Enforcement and Investigations, IE:HQ - D. Thompson Cognizant Branch Chief, IE Region - H. E. Book Cognizant Assistant D.irector,.NRR - G. Lains, R. Tedsco Cognizant Branch*Chief, NRR - D. Crutchfield, F. Miraglia

DRAFT Appendix A NOTICE OF VIOLATION Southern California Edison Company Docket No. 50-206 San Onofre Unit 1 As a result of the inspection conducted on September 28 - October 2, October 19-23, and November 4-5, 1981 it appears that several violations of NRC requirements and license conditions have occurred as noted in Items A-E below. The inspection focused on management of radioactive effluents released from the site. Problems identified during this inspection include failure to submit. the Semi Annual Effluent-Release Report until requested by our inspector, failure to perform adequate calibration of effluent monitoring equipment, failure to recognize and evaluate significant discrepancies between effluent monitoring data and sample results, failure to take compensatory measures when indication of stack gas monitor failure occurred, failure to maintain the liquid effluent monitor operable from October 1980 to October 19.81, failure to maintain the veracity of the Operational Radiation Monitoring System multipoint recorder, and failure to insure the individuals assigned responsibility for these areas executed their responsibilities. These problems indicate a significant programatic breakdown in the management of radioactive materials released to the environment.

-2 In accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified:

A. Technical Specification Appendix A paragraph 4.6 states in part that, "All radioactive wastes discharged through the stack shall be monitored continuously for gross activity."

Contrary to this requirement during July and August 1981, releases of radioactive noble gases were made through the stack which were not continuously monitored in that the Stack Gas Monitor R1214 was not operating in an acceptable manner as described by Surveillance Instruction S01-12.2-2 and Instrument and Test Procedure SO1-II-1.7 and neither approved alternate monitors R1211 or R1212 had been shifted to sample the stack. These releases included the contents of the North.Waste Gas Decay Tank which failed on July 17, 1981 and other batch releases from the Waste Gas Decay Tanks described by Release Permit No. 3298, 3329, 3340, 3341, 3342, 3343, and 3344.

This is a Severity Level IV Violation (Supplement 1).

-3 B. 10.CFR 20.106 establishes the limits of radioactive material which a licensee may release in effluents to unrestricted areas.

Technical Specification Appendix A, paragraph 4.6,."Radioactive Gaseous Waste Release" establishes a formularization of the release limit to meet this requirement of 10 CFR 20. In addition to the above requirements regarding radioactive effluents, 10 CFR 20-.201, "Surveys" states in subparagraph (b), "Each licensee shall make or cause to be made such surveys as may be necessary for him to comply with the regulations in this part."

(i.e. part 20).

a. Contrary to this requirement, during 1980 and 1981 a survey or.

evaluation of the airborne noble gaseous activity released from the Auxiliary Building during reactor operations via the ventilation system was not made. In addition, no accounting of this activity was addressed in the Semi Annual Effluent Release Reports..

b. Contrary to the above requirement, on March.7, 1980 two releases from the Waste Gas Decay Tanks were made through the. CVI system and a survey or evaluation of an apparent discrepancy between the activity calculated based on the CVI composite sample and the activity measured by ORMS monitor R1214 was not made.

-4

c. Contrary to the above, on March 10, 1980, the activity released during containment purge appears inconsistent with the activity measured by ORMS 1214 and a survey or evaluation to resolve the actual activity released was.not made.

This is a Severity.Level IV violation (Supplement IV).

C. Technical Specification Appendix B paragraph 5.5.1 states in part that, "Written procedures, including applicable check lists'and instructions, shall be prepared and followed for the activities involved in carrying out these environmental technical specifications. Procedures shall include sampling, data recording and storage, instrument calibration measurements and analyses, testing frequency of any alarms, and actions to be taken when limits are approached or exceeded."

Contrary to this requirement, written procedures have not been prepared to calibrate flow measuring devices such as. those.used in association with:

stack particulate and iodine samplers, ORMS. containment sphere monitors R1211 and R1212, stack dilution interlock delta pressure sensors DPS17 and 18, which prevent improper releases from the Waste Gas Decay Tanks, and the waste gas decay discharge flow indicator FT-11.

This is a Severity Level IV violation (Supplement IV).

D. Technical Specification Appendix B paragraph 5.6.2 states in part that, "Within 60 days after January 1 and July 1 of each year a report shall be submitted covering the radioactive content of effluents released to unrestricted areas and shipments of solid waste during the previous six months of operation."

Contrary to this requirement, as of September 29, 1981 a report covering the radioactive contents of effluents released to the unrestricted area and shipments of solid waste during the period January 1 thru July 1, 1981 had not been submitted.

This is a Severity Level V Violation (Supplement IV).

E.

10 CFR 19.12, "Instructions to Workers", states in part, that all individuals working in or frequenting any portion of a restricted area shall be instructed in the appropriate response to warnings made in the event of any unusual occurrence or malfunction that may involve exposure to radiation or radioactive material.

Contrary to this requirement, on September 30, 1981 an individual questioned by the inspector while working in a portion of the restricted area, as defined by San Onofre Nuclear Generating Station Radiation Protection Procedure S-VII-1.18, near Unit 1 containment, and responsible for escorting an untrained individual, was unaware of the site evacuation signal, what his response should be in the event that signal were initiated, and further stated that he had not been instructed in the signal or the appropriate response.

This is a Severity Level V violation (Supplement IV).

-6 Pursuant to the provisions of 10 CFR'2.201, Southern California Edison Company is hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged items of noncompliance;.(2) the reasons for the items of noncompliance if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further items of noncompliance; and (5) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1945, as amended, this response shall be submitted under oath or affirmation. Consideration may be given to extending your response time for good cause shown.

dated G. P. Yuhas, Radiation Specialist