IR 05000336/1980012

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IE Insp Rept 50-336/80-12 on 800826-28.No Noncompliance Noted.Major Areas Inspected:Unit 2 Refueling Outage Including Radiation Protection Program,Procedures,Planning & Preparation
ML19351E990
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/14/1980
From: Knapp P, Lovendale P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19351E989 List:
References
50-336-80-12, NUDOCS 8012190680
Download: ML19351E990 (7)


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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-336/80-12 Docket No. 50-336 License No.

DPR-65 Priority Category Licensee:

Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name:

Millstone Unit 2 Inspection at:

Waterford, Connecticut Inspectiotrco'niucted: p st 26-28, 1980 Inspecto

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P. Ct Lovendale, Radiation Spe'ciaNst, RIII date signed date signed date signed Approved by: '\\

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't 4 - 96 P. J.'Knapp, Chief, Fuel Facilit date signed Projects and Radiation Support Section, RI Inspection Sunnary:

Inspection on Auaust 26-28, 1980 (Report No. 50-336/80-12)

Areas Inspected; Routine, unannounced inspection of radiation protection program associated with the Unit 2 refueling outage, including: radiation protection procedures; advanced planning and preparation; exposure control; posting and control; instruments and equipment; surveys; and previous item of noncompliance.

In addition, the licensee's response to IE Bulletin Nos.

78-07, 78-08, and 80-10 were reviewed at both units.

The inspection involved 31 inspector-hours by one NRC inspector.

Results: No items of noncompliance were identified.

Region I Form 12 (Rev. April 77)

8012190(,Q

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DETAlt.S 1.

Persons Contacted

  • E. C. Farrell, Station Services Superintend (9t
  • A. G. Cheatham, Radiological Services Superv kor
  • E. R. Spruill, Health Physics Supervisor J. E. Laine, Health Physicist F. Whitaker, Radiation Protection Supervisor (U-2)

J. Gibson, Health Physics Foreman (Support)

J. Wood, Health Physics Technician (U-2)

L. Vanderhorst, Corporate Technical Advisor to Health Physics Super-visor The inspector also interviewed other licensee employees and contractors, including members of health physics, contracted health physics tech-nicians, and maintenance staff.

  • Denotes those present at the exit interview.

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2.

General The inspectic6, which began with a plant tour and visual observation of facilities and equipment, posting, labeling, and access controls at 8:00 a.m. on August 26, 1980, was conducted to examine the routine aspects of the radiation protection program during the refueling and maintenance outage of Unit 2.

During this and subsequent tours the inspector noted that housekeeping could use some improvement; no problems concerning access controls or postings were noted.

3.

Licensee Action on Previous Inspection Findings (Closed) Noncompliance (50-336/79-03-01):

Failure to post radioactive material area on 38'6" elevation.

During facility tours it was noted that this and all other radioactive materials areas were properly posted.

(Closed) Previously Identified Item (50-336/78-33-01):

Review evalua-tion survey associated with IE Bulletin 78-08. The-inspector reviewed the results of this survey as discussed in Paragraph 13b.

4.

Radiation Protection Procedures The inspector reviewed the following procedures to determine if they are consistent with the requirements of 10 CFR 20 and good health physics practices.

No problems were noted.

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Procedure No.

Title HPP 915/2915 Health Physics Surveys HPP 931/2931 Monitoring for Personnel Contamination HPP 932/2932 Personnel Decontamination HPP 936/2936A ALARA Deficiency / Suggestion Forms HPP 920/2920A Radiological Control Procedure for Steam Generator Work HPP 903/2903 Radiation Work Permits HPP 901/2901A Radiation Exposure Cards HPP 901/2901 Dosimeter and Exposure Control No items of noncompliance were identified.

5.

Planning and Preparation The licensee's planning and preparation for this outage has provided an adequate supply of equipment and personnel to insure the radiation protection program is fully implemented.

The station health physics staff has been augmented with 63 contracted health physics technicians and seven clerks. Approximately 40 of the contracted health physics technicians meet or exceed the qualifications required by Technical Specification 6.3.

The remaining 26 contracted health physics technicians do not meet these qualifications, but are only used as control point watches which does not entail a level of responsibility that would require them to meet ANSI N18.1-1971 standards.

No problems were identified.

The inspector noted an adequate supply of anticontamination clothing at each of the change areas visited. The licensee has contracted two portable dry-cleaning systems which are operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day by contractor representatives under this facility's license. The inspector toured this facility and determined that it was being operated in accordance with the licensee's radiation protection procedures and good health physics practices.

The facility appears to have an adequate supply of portable survey instruments for use in high radiation areas.

The inspector did not notice any job delays due to a lack of instruments.

No items of noncompliance were identified.

6.

Posting and Control During facility tours the inspector examined the osting of contaminated areas, radiation areas, and high radiation areas in containment, the auxiliary building, and various other areas throughout the facility.

No problems were found.

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The inspector observed access control at the personnel and equipment hatch control points for adherence to Radiation Work Permit conditions, contamination control, and exit procedures.

The inspector noted that personnel exiting the control area were generally very thorough about monitoring themselves for contamination.

No problems were found.

No items of noncompliance were identified.

7.

Surveys The inspector made independent measurements of radiation levels in several areas throughout the facility and compared the results with licensee survey records.

No problems were identified.

The licensee's ability to monitor for beta radiation has improved markedly since the last inspection.

There are 31 beta survey instruments available for use throughout the facility.

The inspector reviewed records of contamination and airborne radio-activity surveys conducted to meet the requirements of Radiation Work Permits and station procedures.

No problems were identified.

No items of noncompliance were identified.

8.

Exposure Control a.

External Exposure The inspector selectively reviewed personnel exposure records for compliance with 10 CFR 20.101.

No problems were identified.

A review of records for individuals who received greater than 1250 mrems during a quarter indicated that the licensee had completed forms NRC-4 for these individuals.

The inspector compared the assigned exposure authorization against the actual dose received on the exposure cards of several individ-uals.

No problems were identified.

No items of noncompliance were identified.

b.

Internal Exposure The licensee has obtained two additional whole body counting units for use during the outage.

Individuals are whole body counted upon start of work at the facility and just prior to leaving the facility upon termination or end of outage.

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The inspector reviewed the whole body scans of several individuals.

No body burdens indicative of an exposure greater than the 40 MPC-hour control measure were noted.

The inspector also reviewed the licensee's records of MPC-hours which indicated that the 40 MPC-hours control measure had not been exceeded.

No items of noncompliance were identified.

9.

Respiratory Protection The licensee does not take credit for protection factors per Regulatory Guide 8.15.

All workers who are required to wear respirators are fit tested prior to issuance of a respirator.

Engineering controls are utilized when possible to reduce airborne concentrations such as the HEPA filtered exhaust system used during steam generator work.

The inspector reviewed the licensee's respirator training and fitting program and inspected the steam generator ventilation system.

No problems were noted.

No items of noncompliance were identified.

10. ALARA The inspector noted that the licensee's ALARA program is apparently effective and is supported by management as evidenced by the following:

a.

Use of steam generator mockup for worker training prior to the start of work.

b.

Use of HEPA filtered exhaust ventilation and strict contamination control during steam generator work.

c.

Active review of planned outage work by health physics personnel.

d.

Continuous and effective health physics coverage of all high exposure work.

e.

Continuous effort to maintain contamination levels in containment at a very low level.

11. Radiation Work Permits (RWPs)

The inspector selectively reviewed RWPs written for work in progress during this outage.

Particular attention was given to the following RWPs.

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a.

Steam generator eddy current testing.

b.

Inservice inspection / insulation removal.

c.

Penetration installation.

d.

Reactor head cable removal.

No items of noncompliance were identified.

12. _IE Bulletins 78-07, 78-08, and 80-10 a.

IE Bulletin 78-07 The inspector reviewed the licensee's response to this bulletin.

All air-line supplied respirators used at the site are either continuous flow or pressure-demand type.

No protection factors are used to ensure compliance with 10 CFR 20.103.

The licensee has revised their procedures to incorporate the protection factors listed in Bulletin 78-07.

The inspector is satisfied that the licensee has taken appropriate action in response to this bulletin.

No problems were identified.

b.

IE Bulletin 78-08 The inspector reviewed the licensee's response to this bulletin and the results of a survey conducted during the last refueling.

The survey was conducted while fuel was in the transfer tube.

No increases in radiation levels above background were noted in accessible areas.

The highest reading noted was at contact with the overhead on the -25' level of the auxiliary building which was a few second spike averaging 400 1R/hr at contact.

The general area under this spot did not increase above background.

The inspector considers the licensee's response and action to this bulletin to be adequate.

No problems were identified.

c.

IE Bulletin 80-10 The inspector reviewed the licensee's response and actions to this bulletin as well as internal documentation of system evalua-tions. The licensee has an established-sampling program to detect any unmonitored releases from all nonradioactive systems that could possibly become radioactive.

The inspector is satisfied with the licensee's response and action to this bulletin.

No problems were identified.

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13. Exit Interview

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The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on August 28, 1980.

The inspector sumarized the scope and findings of the inspection as presented in this report.

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