ML20138L983

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Safety Insp Repts 50-317/85-31 & 50-318/85-26 on 851118-22. No Violation Noted.Major Areas Inspected:Radiation Protection Program During Outage,Including External Dosimetry Training
ML20138L983
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/12/1985
From: Clemons P, Shanbaky M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20138L974 List:
References
50-317-85-31, 50-318-85-26, NUDOCS 8512200158
Download: ML20138L983 (7)
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See also: IR 05000317/1985031

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report Nos. 50-317/85-31

50-318/85-26

Docket Nos. 50-317

50-318

License Nos. OPR-53 Priority --

Category C

DPR-69

Licensee: Baltimore Gas and Electric Company

P. O. Box 1475

Baltimore, Maryland 21203

Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 and 2

Inspection At: Lusby, Maryland

Inspection Conducted: November 18-22, 1985

Inspector: /2//$bT

P. Clemons, Radiation Specialist ' date

Approved by: kL dM b t t(itj h5

M. Shanbaky, Chief / date

PWR Radiation Safety Section

Inspection Summary: Inspection on November 18-22, 1985 (Report Nos. 50-317/

85-31 and 50-318/85-26).

Areas Inspected: Routine, unannounced safety inspection of the Radiation Pro-

tection Program during the outage including: external dosimetry training,

respiratory protection, exposure control, surveys, procedures, posting and

labeling, and outstanding items. The inspection involved 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> onsite by

one regionally based inspector.

Results: No violations were identified during the course of this inspection.

8512200150 851213

PDR ADOCK 050 g 7

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DETAILS

1.0 Persons Contacted

1.1 Licensee Personnel

N. Millis, General Supervisor - Radiation Safety

J. Carlson, Assistant General Supervisor - Radiation Safety

P. Rizzo, Supervisor - Technical Training

L. Smialek, Senior Plant Health Physicist

W. Putman, Senior Quality Assurance Auditor

E. Roach, Quality Assurance Specialist

1.2 NRC Personnel

~T. Foley, Senior Resident Inspector

D. Trimble, Resident Inspector

Other licensee personnel were contacted and interviewed during the

inspection.

2.0 Purpose

The purpose of this routine safety inspection was to review the perfor-

mance of the licensee's radiation protection program during the 1985

refueling outage with respect to the following elements:

  • external dosimetry program;
  • training of outage personnel; -

a respiratory protection program;

e exposure control;

  • surveys; _
  • procedures; and
  • posting and labeling.

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3.0 Licensee Action on Previous Findings

(Closed) Violation (317/85-20-01 and 318/84-20-01) Failed to adhere to the

criteria of Appendix B, Part 50. The inspector reviewed the corrective

action specified in the licensee's response dated October 26, 1984. The

corrective action appeared to be adequate.

4.0 External Dosimetry Program

The licensee's external dosimetry program was reviewed with respect to the

criteria contained in 10 CFR 20, " Standards For Protection Against

Radiation." i

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The licensee's implementation of the external dosimetry program was

evaluated by the following methods:

  • Interviews of the Dosimetry Supervisor and staff;
  • Review of dosimetry records of selected personnel.

Within the scope of this review, no violations were identified.

The following was noted:

  • The external dosimetry program was adequate and effective.
  • The licensee's dosimetry group was well staffed.
  • The licensee's External Dosimetry Program is NVLAP certified. This

certification demonstrates an acceptable level of minimum performance

in evaluating personnel radiation exposures.

5.0 Surveys

The licensee's survey program was reviewed against criteria contained in ,

10 CFR 20.201, " Surveys".

The licensee's performance relative to these criteria was determined by

discussion with the Radiation Controis-Ops Supervisor and by reviewing

appropriate radiological survey records.

The licensee's records indicate that the surveys taken throughout the

Controlled Area are adequate.

Within the scope of this review, no violations were identified.

6.0 Posting and Labeling

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The licensee's program for area posting and control was reviewed against

the criteria in 10 CFR 20.203, " Caution signs, labels, signals and

Controls".

The licensee's performance relative to these criteria was determined from

a tour of the Controlled Areas and from discussions with the staff

members.

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Throughout all of the areas inspected, posting and labeling were more than

adequate.

Within the scope of this review, no violations were identified.

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7.0 Respiratory Protection Program

The Itcensee's respiratory protection program was reviewed with respect

to the criteria contained in 10 CFR 20.103, " Exposure of individuals to

concentrations of radioactive materials in air in restricted areas".

The implementation of the licensee's respiratory protection program during

the outage was evaluated by:

  • interviews of the personnel responsible for various aspects of the

program;

  • reviewing records that indicated that breathing air had been sampled

and analyzed to assure Grade D quality.

Procedures for implementing the respiratory protection program appeared

.to be adequate.

Within the scope of this review, no violations 'iere identified.

8.0 Procedures

The adequacy and effectiveness of the licensee's procedures were reviewed

against the criteria contained in Technical Specification 6.8, "Proce-

dures", and Technical Specification 6.11, " Radiation Protection Program".

Procedures reviewed included:

  • RSP 1-117, " Selection, Issuance And Wearing Of Respiratory Protection

Devices Used At Calvert Cliffs Nuclear Power Plant",

  • RSP 2-306, " Operation And Maintenance Of The. Containment And Plant

Breathing Systems",

  • RSP 2-301, " Respiratory Protection Device Maintenance",

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  • RSP 3-201, " Personnel Dosimetry",
  • RSP 3-202, "Special Dosimetry".

Within the scope of this review, no violations were identified.

'9.0 Training

The licensee's training program was reviewed against criteria contained in

10 CFR 19.12, " Instructions to Workers" and ANSI N18.1, 1971, " Selection

and Training of Nuclear Power Plant Personnel".

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The licensee's performance relative to these criteria was determined by

discussion with a Training Instructor, and by review of documentation.

The lesson plans used in providing training for the Contractor Health

Physics Technicians appeared to be more than adequate.

Within the scope of this review, no violations were identified.

10.0 Exposure Control

The licensee's external exposure control program was reviewed against cri-

teria contained in 10 CFR 20.202, " Personnel monitoring". The licensee's

program for controlling personnel exposure and maintaining exposure ALARA

during the 1985 Refueling Outage was evaluated by:

  • Interviews of the ALARA and Radiation Control Supervisors and

selected members of their staff;

  • Review of procedure RSP-106, "Special Work Permit"; and

Review of activities and documentation associated with nozzle dam

installation and removal. ,

Within the scope of this review, the following was identified:

  • The inspector determined that 15-20 licensee employees participated

in the nozzle dam operations during this outage. The licensee's

exposure records indicated that this job was accomplished with the

expenditure of 9.9 man-rem. This represents a significant reduction

in exposure in performing this job. According to the Radiation

Control - ALARA Supervisor, the lowest exposure received in doing

this job, prior to this outage, was 47 man-rem.

The licensee is to.be commended for the tremendous effort that resulted in

this significant reduction in exposure.

Within the scope of this review, no violations were identified.

11.0 Control Room Habitability

Combined Inspection Report Nos. 50-317/85-27 and 50-318/85-25 provided

the results of a review of Control Room Habitability at the Calvert Cliffs

Nuclear Station, Units 1 and 2. Since the issuance of this inspection

report, additional findings relative to the acceptability of Control Room

Habitability at Calvert Cliffs have been identified by the NRR Review

Group. These additional findings are stated below along with NRC

requested action.

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Additional Findings

-(a) Leakage was measured (1000-2000 cfm) through the isolation dampers

with the system in the recirculation mode and flow (10-25% of rated

flow) was measured through the charcoal absorber unit when it was

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isolated. (317/85-31-01)

The licensee should provide the following:

the results'of the current evaluation to establish total inleakage

rate for the Control Room envelope, and

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the date as to when the identified deficiencies will be corrected.

(b) Missing screws and bolts were evident and, as a consequence, ducting

seam leakage was noted. Additionally, several holes were found at

stress points on the fabric expansion joints. It was stated that

inspection and repair of this system was needed to minimize inleak-

age during an accident. (317/85-27-01 and 318/85-25-01)

The licensee should provide the following:

  • status of maintenance deficiencies that have been corrected,
  • results of the evaluation of the walkdown of effected duct work, and
  • the date when all activities including identified deficiencies will

be corrected.

(c) Technical Specification 4.7.6.1.e.2 requires both isolation valves of

each outside air intake to close on a control room high radiation

test signal. At Calvert Cliffs, only the butterfly damper on each

intake closes on high radiation signal. (317/85-31-02)

The licensee should provide the following:

  • corrective actions to be taken, and

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the date when the deficiencies will be corrected.

12.0 Exit Interview

The inspector met with the personnel denoted in Section 1 at the conclu-

sion of the inspection on November 22, 1985. The scope and findings of-

the inspection were discussed at that time.

The licensee was given a copy of the NRR findings of the Control Room

Habitability Study that was performed in September, 1985. A copy of the

material provided to the licensee is attached to this inspection report.

No other written material was provided to the licensee.

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Attachment to Combined Inspection Report 50-317/85-31; 50-318/85-26

Control Room Habitability Findings

Leakage was measured (1000-2000 cfm) through the isolation dampers

with the system in the recirculation mode.

Flow (10-25% of rated flow) was measured through the charcoal

absorber unit when it was isolated.

  • The licensee representative knowledgeable about the control room

HVAC system was from BG&E headquarters. His understanding of the

system and its mode of operation differed from the manner in which

the system operated.

Missing screws and bolts were evident and, as a consequence, ducting

seam leakage was noted. Additionally, several holes were found at

stress points on the fabric expansion joints.

each outside air intake to close on a control room high radiation

test signal. At Calvert Cliffs, only the butterfly damper on each

intake closes on high radiation signal.

  • The location where equipment temperature was monitored to show

conformance with Technical Specification 4.7.6.1.a was not near

such equipment but on a control room wall.

The manner in which the control room HVAC system is operated and its

configuration is quite different from that which would be concluded

from Calvert Cliffs III.D.3.4 submittal.

  • Laboratory testing of charcoal should be at 30 C rather than 130 C

consistent with ASTM D3803-1979 and the allowable penetration for

this test should be 1% in accordance with Table 2 of Regulatory Guide

1.52.

  • - The cooling load for the control room is 116.5 tons. The capacity

-of the safety grade system is 96 tons. After a series of cooling

problems in 1980 a new non-safety grade system was added to handle

control room cooling during normal operation. The adequacy of the

revised HVAC system has not been analyzed.

  • The 19 cfm of inleakeage used by the licensee in the III.D.3.4

analysis has never been verified.

The leak rate assumed in the III.D.3.4 evaluation was based upon

factory test data and anticipated performance of the butterfly and

louvered dampers. The actual performance of the dampers shows

substantially greater leakage.

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