ML20127F424

Discusses Investigation of 850210 Contamination Incident

ML20127F424
Person / Time
Site:	Peach Bottom
Issue date:	02/18/1985
From:	Barron D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Nelson C PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20127F413	List: ML20127F409 ML20127F424
References
FOIA-85-175 NUDOCS 8506250153
Download: ML20127F424 (13)

Text

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, FEAW 302TCH ATCHIC FOWER STATION -

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, DELTA, PENNSYLVANIA -

17314 .

FEBR ARY 18, 1985 To: C.S..NE! ON .

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.TROM: D.A.BhN. ,".- r.

RE: INVESTIGATION OF C0hTAMINATION INCIDENT FEBRUARY 10, 1985 ,

. I. Calcuation of HPC Bours ,

The following is a calcuation of ucuries / mpc.'-hour for the isotope cobalt 60. The maximum permissible concentration (MPC) for" the insoluble form of cobalt 60 is 9.0 E-6 9 uci/ml (10 cfr 20 , appendix B table 1 ). The respiratory rate for an adult male doing light work is 20 liters / ainute a

' (IpRP 23 p 346). ~ Therefore,1 HPC-hodr for cobalt 60 is:

-(9.0 E-9 9 uci/ml) (3,1FE4 4 al/ min) ( 60 min /hr) = 1.082 E-9 2 6ci/mpc-hour The following individuals were assigned MPC b.ouT for the week of February 10,1985. These values were determined by dividing initial uptake

values, determined by stole body counting, and dividing them by the values, .

. calcuated above ( 1.08E-5 2). ., . . .

NAMES S.S f UPTAKE (na) MPC BOUP.S b

440 (-% 41 %h L 1 25 2.3 1 i 158 14.6

'41 3.8 f[LL 1 .

f 1. 128 11.9

- l' 61 5.6 ScndT -

Other individuals investigated were found to have rece.ived less than 2 MPC hours.

O,k k50 II. Dose Assesment for Internal Contamination ,

L 3 & *-

The attached graph of( lwhole body counts would indicate that he initally had 392 nanocuries of cobalt 60 present as internal contamination.

Bowever, a more conservative approach would be to base the initial uptake on long tern lung retention. . The model adopted by ICRP 2 suggest that for insoluble comp-cunds the long term retention is 12.5% of the total uptake. Using this method the inital uptake is 440 nonocuries (55/.125-440). This amount would deliver the following doses:

- Dose to the lung (ICRP 10)

D (rems) = (Q) (51.2) (E/M) 8506250153 850424 PDR FOIA r- 4 /

MLEIN85-175 PDR *~ M ( ! J /

~- -

- 3

• Q (uci-days) = hbb'= (%) (10 days) (0.055 uci)' =.,0.275 M= Mass. of ths; lung (grams) = '1170 (ICRP 2'3)' -

E= effective absorbed energy (MeV):= 0.72 .

D (rem) = (0:275) (51.2) (0.72/1170) = 8.7E-93 or 8.7 millirem Dose the GI tract for( .

Q (uci-days) = bh = ( ) (4.0 days) (0.46uci) = 0.'92 M= mass of the gastrointestinal tract (grams) = 160 (ICRP23)

E= effective absorped energy (MeV) = 0.44 D (rem) = (0.92) (51.2)' (0.44/160) = 0.130' or 130 millirem O see attached WBC graph forb ~ land ( ]

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! Dose to the lung D (rem) = (Q) (51.2) (e/m) .

. Q = (uci-days ) '= bh= ( ) (10 ' days) (0.016uci) = 0.08 M= mass of the lung (grams).= 1170 (ICRP23)

E = effective energy absorbed (MeV7,= 0.72  :

l i D (rem) = (0.08) (51.2) (0.72/1170) = 2.5 E - 9 3 or 2.5 millirem '

DosetotheGItractfor[ 7 -

Q (uci-days) = bb = ( )- (3.0 days) (.128 'uci) = .192 M = cass of the gastro 16testinal tract (grams) = 160 (ICRP23)

E = effective absorbed energy ( MeV ) = 0.44 l

D (rem) = (0.192) (51.2) (0.44/160) = 2.7 E - 6 2 or 27 millirem r

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4 'o UNITED STATES

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f 'g NUCLEAR REGULATORY COMMISSION L E REGION 1 0,

' #9

/[ s31 PARK AVENUE

% KING oF PRUSSIA, PENNSYLVANIA 19406

• * * * * ,o#

APR 021965 Docket Nos. 50-277 50-278 Philadelphia Electric Company ATTN: Mr. S. L. Daltroff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:

Subject:

Inspection No. 50-277/85-14 This refers to the special inspection conducted by Mr. H. Bicehouse on March 11, 1985, at the Peach Bottom Atomic Power Station, Delta, Pennsylvania, of activities authorized by NRC License No. DPR-44 and to the discussion of our findings held by Mr. Bicehouse with Mr. R. Fleischmann at the conclusion of the inspection.

Areas examined during this inspection are described in the NRC Region I Inspection Report which is enclosed with this letter. The inspection of your radiation protection program reviewed your staff's external and internal dose assessments for workers potentially affected by the events described in Inspection Report No. 50-277/85-11 and examined the implementation of certain actions described by your staff during the Enforcement Conference on March 4, 1985.

Within the scope of this inspection, no violations or deviations were observed. No reply to this letter is required. Your cooperation with us in this matter is appreciated. /

Sincerely, W O-Thomas T. Martin, Director l

Division of Radiation Safety and Safeguards

Enclosure:

NRC Region I Inspection Report No. 50-277/85-14 C'1 r% / I n G n r n /

D V 7 y) 0 V J W t7 "

, i Phildelphia Electric Company 2 l

cc w/ enc 1:

R. S. Fleischmann, Station Superintendent I John S. Kemper, Vice President, Engineering and Research l Troy B. Conner, Jr. , Esquire  !

Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)

Raymond L. Hovis, Esquire '

Thomas Magette, Power Plant Siting, Nuclear Evaluations (Without Report)

Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Pennsylvania bec w/ enc 1:

Region I Docket Room (with concurrences)

Senior Operations Officer (w/o encis)

Section Chief, DPRP c

U.S. NUCLEAR REGULATORY COMMISSION REGION I Report No. 85-14 Docket No. 50-277 License No. DPR-44 Priority -

Category C Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, PA 19101 Facility Name: Peach Bottom Atomic Power Station, Unit 2 Inspection At: Delta, Pennsylvania Inspection Conducted: March 11, 1985 Inspectors: .)b -

H. J.,Cicehouse, Radiation Specialist

.l f 2 7/ ? i date kwkcs L' E. Myefs, Ra iation Speaialist SI27/6 date Approved by: e _ U 6'E 71fE W.9asci nk, Chief /datp BWRRahiologicalProtectionSection Inspection Summary: Inspection on March 11, 1985 (Report No. 50-277/85-14)

, Areas Inspected: Special unannounced inspection to review the licensee's assessments of external and internal exposures resulting from events described in Inspection Report 50-277/85-11 and the licensee's corrective actions as described in Meeting Report 50-277/85-13. The inspection involved 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> on site by two regionally based inspectors.

Results: No violations or deviations were noted in the areas reviewed.

t l

l cr.

D)h j -l: f

E -

Details

1. Persons Contacted During the course of this special radiation protection inspection, the following personnel were interviewed:

1.1 Licensee Personnel

• R. S. Fleischmann, Station Superintendent, Peach Bottom Atomic Power Station

• N. F. Gazda, Applied Health Physicist

• A. E. Hilsmeir, Senior Health Physicist

• C. S. Nelson, Support Health Physicist Other licensee employees were also contacted or interviewed during this inspection.

1.2 Contractor Personnel L. Davis, ALARA Engineer, Bartlett Nuclear Corporation W. Smith, ALARA Engineer, Bartlett Nuclear Corporation T. Stafford, Supervisor Operational Health Physics - Unit 2 Drywell, Bartlett Nuclear Corporation Other contractor personnel were also contacted or interviewed during this inspection.

1.3 NRC Personnel

• T. Johnson, Senior Resident Inspector

• Attended the exit meeting on March 11, 1985

2. Purpose The purpose of this special . inspection was to review the licensee's assessment of external and internal exposures resulting from events described in Inspection Report 50-277/85-11 and the licensee's corrective actions as described in Meeting Report 50-277/85-13.

3. External Exposures The estimated external exposures for the following workers were reviewed against criteria provided in 10 CFR 20.101:

the contractor pipefitter who attempted to remove the purge bag on

, February 3, 1985; i

the contractor engineer who inspected weld joint 206 on February 3, 1985; l

2 the welding coordinator who examined weld joint 206 on February 10, 1985; the two pipefitters who ground weld joint 206 on February 10, 1985; the welder and his helper who repaired the weld joint on February 10, 1985; and the health physics technicians who made radiation / contamination measurements of the work area on February 10-11, 1985.

The licensee's external exposure calculations were reviewed and discussed with the Support Health Physicist and a member of his staff.

The licensee derived the estimates of time and work location from interviews of the workers and conservative assumptions concerning placement of the workers' bodies within the nonuniform radiation fields.

Beta protection factors based on previous licensee measurements and confirmed on contamination samples taken from the work area were used in the calculations. The calculations estimated exposures to the whole body, lens of the eyes, skin and extremities of each of the workers. All calculated exposures were within 10 CFR 20.101 radiation dose standards.

Within the scope fo this review, no violations were noted. The licensee's external exposure estimates appeared to be generally sound and thorough, timely and demonstrated a general understanding of the issues.

4. Internal Exposures The licensee's assessments of the intake of radioactive materials by the workers identified in Detail 3 were reviewed against criteria provided in 10 CFR 20.103. Performance relative to these criteria was determined by review of internal exposure assessments and discussions with the Support Health Physicist and a member of his staff.

The licensee's assessments showed that one individual exceeded the '

40-hour control measure in 10 CFR 20.103(b)(2) while the other workers' intakes were less than the 40-hour control measure. The licensee's assessments showed that no worker exceeded quarterly limits in 10 CFR 20.103(a)(1).

Within the scope of this review, no violations were noted. The licensee's internal exposure assessments appeared to be generally conservative, sound, thorough and timely.

5. Corrective Actions The following corrective actions described by the licensee at the Enforcement Conference on March 4, 1985 were reviewed:

[

3 improvements in communications to ensure that radiological controls personnel were aware of the daily planned work activities and the scope of those activities; increased visual surveillance and reporting of observations of ongoing Unit 2 drywell work activities by radiological controls personnel; increased attention to detail in ALARA Job reviews to ensure that each task was fully described and reviewed; and discussions with contracted health physics technicians to reiterate their duties and responsibilities and review the events described in Report No. 50-277/85-11.

The licensee's performance relative to these commitments was evaluated by review of documents, interviews of selected radiological controls personnel and observations of operations at the Unit 2 drywell control point.

Within the scope of this review, no deviations from commitments made during the Enforcement Conference were noted. The licensee appeared to be completing the corrective actions as described.

6. Exit Interview ,

The inspector met with the licensee's representative (denoted in Section 1.1) at the conclusion of the inspection on March 11, 1985. The inspector summarized the purpose and scope of the inspection and identified findings as described in this report.

At no time during the inspection was written material provided to the licensee by the inspector. No information exempt from disclosure under 10 CFR 2.790 was discussed in this report.