ML18086B032

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IE Insp Rept 50-272/81-20,on 810629-0702.No Noncompliance Noted.Major Areas Inspected:Followup & Verification of Commitments & Corrective Actions in Response to Health Physics Appraisal
ML18086B032
Person / Time
Site: Salem 
Issue date: 10/19/1981
From: Knapp P, Jason White
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18086B031 List:
References
50-272-81-20, NUDOCS 8111130755
Download: ML18086B032 (12)


See also: IR 05000272/1981020

Text

U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

Report No. 50-272/81-20

Docket No. 50-272

Region I

License No. DPR-70

Priority ---

Category __ c __

Licensee:

Public Service Electric and Gas Company

80 Park Place

Newark, New Jersey 07101

Facility Name:

Salem Nuclear Generating Station

Inspection at:

Hancocks Bridge, New Jersey

Inspection

1

Inspectors:

/t7-if!!!f'-Y/

A~~P--

P.J.~ility

Radiological Protection Section,

Technical Inspection Branch

date signed

10~1°1-~(

date signed

Inspection Summary:

Inspection on June 29-July 2, 1981 (Inspection Report No. 50-272/81-20)

Areas Inspected:

Special, unannounced inspeytion by a regional based

inspector to follow up and verify commitments and corrective actions performed

in response to the Health Physics Appraisal (Inspection Report No. 80-03,

dated June 13, 1980).

The inspection involved 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> onsite by one NRC

regional based inspector.

Results:

No items of noncompliance were identified .

( 8111130755 811026

PDR ADOCK 05000272

I G

PDR

DETAILS

1.

Persons Contacted

  • Mr. John Driscoll, Chief, Engineer
  • Mr. R. L. Swetnam, Radiation Protection Engineer
  • Mr. L. K. Miller, Performance Engineer

Mr. Frank Dickey, Technical Assistant (Rad Service Incorporated)

Mr. Paul Greenbaum, Training Assistant (Hydro-Nuclear Services)

Quality Assurance

In addition, other personnel including technicians, clerical assistants,

and operators were interviewed.

  • denotes those personnel present at the exit interview.

2.

Purpose and Scope

The purpose of the inspection was to verify and review the licensee's

corrective actions implemented as a result of the Health Physics

Appraisal.

The following references pertain~

a.

Letter from B. H. Grier, Director, USNRC Region I, to F. W.

Schneider, Vice President - Production; dated June 13, 1980;

b.

Salem Health Physics Appraisal, Report No. 80-03 (January 28 -

February 8, 1980);

c.

Letter from F. W. Schneider, Vice President - Production, to B. H.

Grier, Director, USNRC Region I, dated July 7, 1980;

d.

Letter from F. W. Schneider, Vice President - Production, to B. H.

Grier, Director, USNRC Region I, dated October 7, 1980.

The scope of this inspection effort involved verification and evaluation

of the licensee's responses (References c. and d.) to the Significant

Items and Items of Noncompliance contained in Reference a.

Section 3,

Status of Health Physics Appraisal Items, summarizes the findings of this

inspection.

3.

Status of Health Physics Appraisal Items

Reference a. identified the following Significant Appraisal Findings in

Appendix A:

a.

3

Organization - Technical Competency

Health Physics Appraisal Finding

There was a general lack of technical proficiency in the Health

Physics (HP) staff predominately due to:

Failure to select, qualify and train personnel in the Health

Physics specialty;

failure to develop and implement a technician retraining

program to assure that technician 1s skill and knowledge is

maintained at a satisfactory level; and

failure to have an adequate back-up for the designated

Radiation Protection Manager.

Licensee Response

The licensee 1s response, Reference c, indicated that a training and

retraining program would be developed and implemented by December 1,

1980; and that initial qualification and training would be completed

by July 1, 1981.

Followuo

The inspector determined that significant effort had been made to

train and qualify HP personnel (including supervisory personnel) as

well as provide for periodic retraining.

Training

The general training program currently implemented involves the

following:

Upon being selected to work in the Radiation Protection Department,

entry level personnel (HP Helpers) are required to pass a general

knowledge test (Steven 1 s Battery Test), a personality profile

evaluation and a medical examination.

If performance is satisfactory, the individuals attend a general HP

technician indoctrination course of 2-weeks duration.

The course is

formalized with developed lesson plans and is intended to introduce

the ~tudent to the nuclear power plant and the concepts relating to

radiation protection in the facility.

Such topics as plant layout,

power generation, organization, and the purpose and scope of

radiation protection are discussed .

4

Following the indoctrination the individual is designated as a

Technical Helper (TH) and for the next 6 months to a year, works in

a limited capacity under the direction of supervisory and qualified

technician personnel.

The individual is then given a 7-week course entitled

11Apprentice

Radiation Protection Assistant Course

11 , in which more in-depth

training is presented.

Such topics as atomic structure,

radioactivity, biological effects of radiation, radiation shielding,

radiation detection instrument fundamentals, respiratory protection,

and radioactive waste handling are discussed.

The course has been

formalized with written lesson plans.

Following the above, the student attends

11 Phase II School

11 at the

licensee's main training facility in Quinton, New Jersey.

The

20-week school provides training in electronics, instrument repair,

chemistry techniques, etc.

Ten weeks of this period are devoted to

intensive training in basic Health Physics in which generic

radiation protection theory, practices and methods are presented.

At the completion of the

11 Phase II School,

11 the student returns to

the station and, within the next 6 weeks, the individual is

subjected to an oral examination and a written examination

(involving over 200 essay type questions) on applied and theoretical

health physics.

Upon successful completion, the individual is

upgraded to the position of Technical Assistant (TA).

For at least the next 20 months, the individual works in this

capacity, at which time the person is eligible for promotion to the

position of Technician Nuclear (TN).

A training program called

11 Phase III School

11 is currently under

development by both the station staff and the main training center

in Quinton, to develop the technicians more fully prior to promotion

to TN.

Retraining

The retraining program was reviewed.

A formalized system currently

exists based on written lesson plans that are generated from

observed deficiencies, problems, weaknesses in the staff performance

as well as new regulatory requirements or information that has come

to the attention of the Radiation Protection Department.

Retraining

is performed at least annually and currently involves 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of

instruction. Additionally, personnel are familiarized with the

current Emergency Planning Program and their respective functions .

5

Documentation

The inspector reviewed the training records of five individuals and

determined that adequate documentation existed, including

qualification records, tests, and procedures.

Contractor Training

In accordance with the licensee's program, HP contractor

qualifications were reviewed for acceptance by management personnel.

Following this review, the contracted individual is tested by a

written examination containing at least 50 essay type questions, 70%

of which must be answered correctly in order to be retained by the

licensee.

Contractor personnel who are retained for long periods by the

licensee are subjected to the same training requirements as the

station's HP staff.

RPM Back-up Capability

The inspector reviewed the qualifications of the individual who had

been directed to act in a back-up capacity to the Radiation

Protection Engineer, the designated Radiation Protection Manager,

(RPM).

The licensee stated that the current Radiation Protection

Supervisor is assigned this responsibility.

The inspector reviewed the qualifications of the individual and

determined that the person had sufficient training and experience to

allow his designation as back-up RPM.

Summary

The inspector verified that the licensee has satisfactorily met the

committment specified in Reference c, and that the finding presented

in Reference a has been adequately addressed.

At the time of this

inspection all personnel had been trained or were completing the

training in accordance with the established program.

It was noted however, that Administrative Procedure No. 24, Rev. 5,

dated April 15, 1981, Radiological Protection Program, Section

2.3.3, "Radiation Protection - Personnel Training", and Section 2.4,

"Retraining," indicate that such training shall be as specified in

the Radiation Protection Instructions.

Review of the applicable

instructions, RP 2.012, "TN Retraining," and RP 2.013, "TN Training

Requirements," revealed that while a training program was

established, it was technically different from that described in the

procedures.

In response, the licensee stated the procedures (RP

2.012 and RP 2.013) were not currently applicable.

The inspector's

b.

6

review indicated that the currently established program was a

significant improvement compared to the program described in RP

2.012 and 2.013.

However, the current program was not described in

accordance with the licensee's procedures.

In further review, the inspector noted that the Radiation

Protection Department Administration Procedure, Revision 1, Section

3.4.3, indicates that the training program shall be in accord with

the

11 Personnel Training Manual

11 *

The licensee indicated that this

manual was currently being developed; and would completely describe

the established program.

This item was further discussed in the Exit Meeting on July 2, 1981.

At that time the licensee's representatives stated that the

procedures RP 2.012 and 2.013 would be withdrawn, AP-24 would be

revised to reflect the current training program, and the

11 Personnel

Training Manual 11 would be completed by September 1, 1981.

This item will be reviewed in a subsequent inspection.

(272/81-20-01).

Organization-Inordinate Reliance on Contractor Personnel

Health Physics Appraisal Finding

There was inordinate reliance of contractor personnel due to:

attempting to cross-train personnel to function as Instrument

and Control technicians, Chemistry technicians and Health

Physics technicians.

As a result very few personnel were ever

fully qualified to assume responsible positions as technicians.

As much as 80-90% of the HP staff positions were filled by

contractor personnel, who were predominately responsible for

the performance of the program in normal and off-normal

conditions, including emergency conditions.

Licensee Response

The licensee's response, References c and d, indicated that to

reduce reliance on contractor personnel, a schedule had been

developed to recruit additional station personnel and to

phase ,out dependence on the contractors, such that by July 1,

1981, the majority of the contractors would be replaced.

In

addition, the licensee indicated that the Peformance Department

would be reorganized to remove the Radiation Protection

Department from that division and to form a new department with

the Radiation Protection Engineer reporting directly to the

Station Superintendent.

It was further stated that in the

interim period, personnel (station and contractor) would be

7

trained in accordance with the Performance Department Manual

(which referenced the previously discussed training

procedures).

Followup

The inspector determined, that, in accord with the licensee's

commitment, a reorganization had occured in which the radiation

protection activity was removed from the Performance

Department.

The Radiation Protection Department, with the

department head (Radiation Protection Engineer) reporting

directly to the Station Superintendent, was formed.

It was noted that the Radiation Protection Department was

comprised of personnel specially dedicated to radiation

protection activities.

The Instrument and Control and

Chemistry activities were no longer a function of the Radiation

Protection Department, but rather remained in the Performance

Department.

The inspector verified that the interim personnel training was

performed in accordance with the licensee's procedures RP 2.012

and RP 2.013.

The training process has subsequently been

upgraded as previously discussed in this report.

As of July 1, 1981, the majority of radiation protection

personnel were noted to be employees of the licensee instead of

contractors; 33 licensee personnel and 26 contractor personnel

were directly involved in the radiation protection activity.

The licensee was still actively recruiting personnel.

The

Radiation Protection Engineer stated that it was anticipated

that the radiation protection function would be supported

entirely by licensee personnel by November 1981.

Summary

The inspector verified that the licensee was performing in

accordance with the commitment specified in Reference b.

c.

Radioactive Waste Management - Responsibility

Health Physics Appraisal Finding

There was no formalized program implemented in the area of

management of the disposition of radioactive waste materials

(solid, liquid and gaseous).


----

--- -----

-

Summary

8

Licensee Response

The licensee's response~References band c, indicated that a

radioactive waste management program would be implemented in

accordance with a new administrative procedure, AP-29,

11 Radioactive Waste Management

11 , and a Radwaste Manual

containing implementing procedures.

Such actions were to be

completed by October 1, 1980.

Followup

The inspector verified that AP-29 had been established and

implemented.

The Radwaste Manual, Volume II, which describes

the responsibilities and authorities of the Radiation

Protection Department in regard to solid radioactive material

disposition, was verified to have been issued prior to October

1, 1980.

Volume I, which describes the responsibilities and

authorities of organizations in regard to liquid and gaseous

radioactive waste, was issued during this inspection on July 2,

1981.

However, the lateness of the implementation of this

volume did not appear to compromise or impede actions in the

area of radioactive waste management.

The inspector verified that the licensee was currently performing in

accordance with the commitment specified in References b and c.

d.

Radioactive Waste Management-Effluents

Health Physics Appraisal Finding

Deficiencies noted in this area included:

failure to develop a system for reviewing anomalous noble gas

~elease that might occur between the time that routine samples

are collected;

an erroneous formula in procedure PD-3.8.016 used to estimate

Waste Gas Decay Tank releases;

lack of procedures for primary coolant sample collection in

emergency conditions;

failure to install a high-range noble gas measurement

capability in accordance with NRR ~irectives issued October 30,

1979.

,

'

e .

9

Licensee Response

The licensee 1 s response, Reference c, indicated that procedure

PD-3.8.023

11 Chemistry Analysis Summary Forms,

11 was amended to

provide for daily review and documentation quantifying anomalous

releases.

Further, the response stated that procedures PD-3.3.020,

11 Plant Vent Sample Analysis,

11 and PD-3.8.016,

11Gaseous Radwaste

Release Calculations,

11 were similarly amended to provide for

additional review and control to assure that all gaseous releases

were subject to evaluation.

The response stated that all of these

actions were completed as of July 7, 1980.

Followup

The inspector determined that none of the actions described in the

licensee 1 s response had been implemented.

Review tif procedures

PD-3.8.023, PD-3.3.020 and PD-3.8.016 indicated that the procedures

had not been amended or revised; and that at the time of this

inspection there was still no system established to review and

quantify anomalous noble gas releases.

The inspector verified that the erroneous formula previously noted

in procedure PD-3.8.016 had been corrected.

The licensee 1 s actions on post-accident sampling capability (primary

coolant collection and high-range noble gas monitoring) were

previously verified in NRC Combined Inspection Report 50-272/81-07

and 50-311/81-08.

Summary

With the exception of the licensee 1 s failure to meet the commitment

to revise and amend existing procedures to provide review and

control of anomalous noble gas releases, the licensee actions were

verified to be in accordance with References c and d.

With regard to the failure to amend and revise the specified

procedures, the licensee was not able to offer any explanation, but

did state that such procedures would be amended by August 1, 1981.

Further discussion of this item is included in Section 5,

11 Exit

Meeting

11 *

This item will be reviewed in a subsequent inspection.

(272/81-20-02)

Health Physics Surveillance Activities

Health Physics Appraisal Finding

The following specific deficiencies were noted:

.

, .

a.

b.

c.

d.

10

An acceptable Respiratory Protection Program was not developed;

Station personnel did not perform reviews of instrument

calibration performance or documentation;

Actual efficiency determination was not performed for HP-210

personnel frisking detectors; and

The bioassay program did not provide for baseline data on

personnel that may be subjected to exposure to airborne

radioactivity.

Licensee Respon~e

The licensee 1 s response, Reference c, indicated that:

a.

A Respiratory Protection Program had been developed and

implemented on March 14, 1980;

b.

Personnel were trained in instrument calibration, and

supervisors were directed to perform routine reviews of

performance in this area;

c.

Efficiency factors for HP-210 detectors were determined; and,

d.

A bioassay procedure was developed to provide for baseline

determinations on all personnel expected to be subject to

exposure to airborne rad1oactive material.

The procedure,

PD-15.3.027, was implemented on July 30, 1980.

Summary

The inspector verified the licensee 1 s performance in these areas to

be in accordance with References c and ~-

f.

Emergency Preparedness

Health Physics Appraisal Finding

The following deficiencies were noted:

a.

Failure to assign emergency duties and responsibilities for

radiation protection personnel, the Station Manager, and

response teams;

b.

c.

Failure to establish a clearly defined training program for

individual~ assigned to emergency functions;

I

Failure to develop emergency procedures in the area of

radiation protection and security.

11

Summary

The licensee's action on these items and other related areas were

reviewed and reported in NRC Combined Inspection Report 50-272/81-07

and 50-311/81-08.

4.

Status of Previously Identified Items

(Closed) Noncompliance (50-272/80-03-01)

Failure to identify radioactive

material in accordance with 10 CFR 20.203(f).

The licensee has

established a program that provides for the proper identification of

radioactive material.

Pre-labeled polyethylene bags are currently

utilized in this regard.

(Closed) Noncompliance (50-272/80-03-05)

Failure to adhere to Station

Procedures PD-15.9.004 and PD-15.9.009 in accordance with Technical

Specification 6.8.1; failure to establish a procedure covering

calibration of air sampling equipment.

The procedures in question were

subjected to revision to assure that user instructions could be followed

and personnel were instructed in the revised technique.

A specific

procedure for calibration of air sampling equipment was established and

implemented.

(Closed) Noncompliance (50-272/80-03-07)

Failure to make changes to

Station Procedure 15.9.002 in accordance with Technical Specification 6.8.2.

Procedural control has been strengthened by the implementation of

a Radiation Protection Administrative Manual.

All unapproved procedures

have been removed and controlled procedures have been implemented.

(Closed) Unresolved Item (50-272/79-07-04) Training of Health Physics

Technicians.

The current training program has been significantly

upgraded; and has adequately addressed previously identified

discrepancies.

5.

Exit Interview

0

The inspector met with the licensee's representatives (denoted in Section

1 of this report) on July 2, 1981.

The findings of the inspection were

presented.

The licensee made the following comments regarding the failure to

implement the corrective actions described in Section 3.d of this report

as specified in the letter from Mr. Frederick W. Schneider, Vice

President - Production to Mr. B. H. Grier, Director, NRC Region I, dated

July 7, 1980;

The commitment as specified in the letter will be implemented by

August 1, 1981;

A review will be conducted to determine why the stated commitments

were not initially implemented;

12

In response to this inspection, a report will be submitted

identifying the specific degradation in management controls that

permitted inaccurate information to be submitted in response to an

NRC request; and the upgraded management controls established to

preclude recurrence.