ML20206U426

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Forwards IE Circular 77-15,for Info.No Written Response Required.List of Circulars Issued in 1977 Also Encl
ML20206U426
Person / Time
Site: 07001489
Issue date: 01/27/1978
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Feldscher J
GOODYEAR AEROSPACE CORP. (SUBS. OF GOODYEAR TIRE
Shared Package
ML20206U346 List:
References
FOIA-98-341 IEC-77-15, NUDOCS 9902160023
Download: ML20206U426 (20)


Text

{{#Wiki_filter:. t ' 3 1 l l J A N 2 ', .8 Docket No. 70-01489 Goodyear Aerospace Corporation i-ATTN: Mr. J. C. Feldscher Manager, Business

Planning Akron, OH 44315 Gentlemen:

The enclosed IE Circular No. 77-15 is forwarded to you for infor-mation. No written response is required. Should you lave any questions related to your understanMng of this matter, please contact this office. Sincerely, James G. Keppler Director Enclosures

1. IE Circular No. 77-15
2. List of IE Circulars Issued in 1977 cc w/encia:

Central Files Reproduction Unit NRC 20b PDR NSIC

                                  .  ..A orrics >      RIII            RIII
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                . . , , ,   1/26/78                                                                  . . . . . . . . _ .

NRC PERM Sig (9 76) NRCM 0240 k un s. oovsnmu sur enintme or rica. sete - ese4: 4 9902160023 990209 A fy PDR FOIA '

 #,/ 9           POST 98-341            PDR                                                                              //

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSFECTION AND ENFORCEMENT REGION III November 29, 1977 IE Circular No. 77-15 DEGRADATION OF FUEL OIL FLOW TO THE OdERGENCY DIESEL GENERATOR During surveillance testing on July 14, 1977, personnel at the Cooper Nuclear Station noted a degradation of fuel oil flow to the day tank for the emergency diesel generator. Although the fuel oil transfer pump capacity is 13.8 gpm for each of the two redundant pumps, flow to the day tank for number one diesel generator was only 3 gpm. At full load, engine consumption is 4.5 gpm. Investigation of this occurrence revealed a clogged strainer in a float l operated shutoff valve on the day tank inlet. This valve operates as a l backup to level switches which start and stop the fuel oil transfer pumps to maintain normal day tank level. The strainer is an integral part of the float valve assembly and is not shown on the as-built I system drawings. This valve was manufactured by McDonnell-Millen Company. Station personnel were thus unaware of the presence of this strainer and did not schedule it for routine strainer cleaning under the preventive maintenance program. Normal testing of the system under the Technical Specification surveillance requirements does not verify system flow rates. This occurrence represents an example where the as-built system configuration was not accurately indicated on the system drawings, and that adequate system description was apparently not available to Station personnel. All holders of construction permits or operating licenses should be aware of the potential for variance between as-built configurations and system drawings. This is especially true for support systems to the engineered safeguards features where all required system conditions such as pressure and flows may not receive routine testing under the surveillance testing program. It is recommended that the following be considered in your review of this matter: I

1 ( v IE Circular No. 77-15 November 29, 1977

1. A field verification of the drawing against the as-built system configuration should be made for the entire diesel generator fuel oil delivery system from the storage tanks to the engines.

Appropriate changes should be made to the drawings and preven-tive maintenance program to account for any components or configurations not previously covered. I

2. Conside etion should be given to revising surveillance test procedutu; to include a flov test on the fuel oil system to ensure the system continues to ceet design spccifications.

In addition, the following information relating to the maintenance ! of fuel oil cleanliness should be considered in your review:

1. During long-time storage, degradation of fuel oil is a common occurrence. The rate of degradation is not easily predicted since it is a function of the source of the crude oil, the  !'

process utilized in making the fuel (e.g., straight distillation or the method of catalytic cracking), and the conditions under which the fuel oil is stored.

2. It is known that cer,tain detrimental processes are accelerated in fuel oils when they are in contact with certain metals. The presence of zinc, such as from galvanizing, has a tendency to form soluble soaps in the fuel oil which are deposited on the diesel engine's injection nozzles. A buildup of this deposit will eventually degrade the engine's performance. The presence of cepper promotes the formation of gums which degrade the stored fuel oil and tends to clog filters.
3. The presence of water in the fuel oil promotes the growth of fungi or slime that also degrades the fuel and has the potential for clogging filters.

No written response to this Circular is required. If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office. i

k. . .

IE Circular No. 77-15 November 29, 1977 LISTING OF IE CIRCULARS ISSUED IN 1977 CIRCULAR SUBJECT FIRST DATE OF ISSUED TO NO. ISSUE 77-01 Malfunctions of 1-4-77 All holders of Limitorque Valve OLs or cps Operators 77-02 Potential Heavy 2-15-77 All affected Spring Flooding holders of OLs 77-02A Potential Heavy 2-16-77 All affected Spring Flooding holders of cps 77-03 Fire Inside 2-28-77 All holders of a Motor Control OLs and cps Center 77-04 Inadequate Lock 3-17-77 Safeguard Group Assemblies I, II, IV, V, Licensees 77-05 Liquid Entrapment 3-24-77 All holders of  ! in Valve Bonnets OLs and cps f 77-06 Effects of Hydraulic 4-1-77 All holders of Fluid on Electrical OL's and cps l Cable 77-07 Short Period During 4-12-77 Holders of Reactor Startup BWR OLs 77-08 Failure of Feedwater 4-13-77 All holders Sample Probe of OLs 77-09 Improper Fuse 5-25-77 All holders of Coordination In BWR BWR OLs or cps Standby Liquid Control System Control Circuits 77-10 Vacuum Conditions 7-15-77 All holders of Resulting in Damage to OLs Liquid Process Tanks Page 1 of 2

k .. November 29, 1977 IE Circular No. 77-15 l LISTING OF IE CIRCULARS ISSUED IN 1977 (Continued) FIRST DATE OF ISSUED TO CIRCULAR SUBJECT ISSUE NO. Leakage of Con- 9-6-77 All holders of OLs 77-11 and cps tainment Isolation Valves with Resilient Seats Dropped Fuel Assem- 9-15-77 All holders of BVR 77-12 OLs or cps blies at BWR Facili-ties Reactor Safety Signals 9-22-77 All holders of OLs 77-13 and cps Negated During Testing 11-22-77 All Power and 77-14 Separation of Test Reactor, Contaminated Fuel Cycle, and Water Systems major By-product From Noncontaminated material processor Plant Systems facilities with OLs or cps Page 2 of 2

FORM NC4C-591 U.S. NUCLEAH HEGUL AT OHY COMMibb40fd (S Fr*

  • OFF 'OF INSPECTION AND ENFORCEMENT LNSPECTION FhDINGS AND LICENSEE ACKNOWLEDGMENT
s. ucENsEE . n Es.oN nt Or r.c.

4 U. S. Nuclear Regulatory Coisaission Goodyear Aerospace Corporation Office of Inspection and Enforcement Ragion III 1210 Massillon Road Akron, OH 44315 799 Roosevelt Road Glen Ellyn, IL 60137

4. LICENSE MUM BE R{$) s. DnTE OF $NSPECTION
s. OOCMET NUMBER {$)

070-1489 SNM-1461 4/12-13/78

s. INSPECTSON FINDING 5 The inspection was an raamination of the activities conducted under your license as they relate to radiation safety and to compliance with the Commission's rules and regulations and the conditions of your license. The inspection consisted of selective examinations of procedures and repre.

sentative records, interviews with personnel, and observations by the inspector. The fmdmgs as a result of this insecttian are as follows: No items of noncompliance or unsafe conditions were found. The following items of noncompliance related to records, signs, and labels were found: O A. Rooms or areas were not properly posted to indicate the presence of a RADI ATION AREA.10CFR 20.203(b)or 34.42 O B. Rooms or areas were not properly posted to indicate the presence of a lilGil RADI ATION AREA. 10 CFR 20.203(c)(1) or 34.42 C. Rooms or areas were not properly posted to indicate the presence of an AIRBORNE RADIOACTIVITY AREA. 10 CFR 20.203(d) D. Rooms or areas were not properly posted to indicate the presence of RADIOACTIVE M ATERIAL.10 CFR 20.203(e) E. Containers were not properly labeled to indicate the presence of RADIOACTIVE M ATERI AL. 10 CFR 20.203(f)(1) or (f)(2) O F. A current copy of 10 CFR 20, a copy of the license, or a copy of the operating procedures was not properly posted or made available.10 CFR 20.206(b) G. FormNRC 3 was not properly posted.10 CFR 20.206(c) O H. Records of the radiation exposure ofindividuals were not properly maintained.10 CFR 20.401(a) or 34.33(b) O 1. Records of surveys or disposals were not properly maintained.10 CFR 20.401(b) or 34.43(d) J. Records of receipt, transfer, disposal, export or inventory oflicensed material were not properly mair.tained. 10 CFR 30.51,40.61 or 70.51 K. Records of leak tests were not maintained as prescribed in your license, or 10 CFR 34.25(c) j L. Records of inventories were not maintained.10 CFR 34.26 i O M. Utilization logs were not maintained.10 CFR 34.27 O N. Records of radiation survey instrument calibration were not maintained.10 CFR 34.24 O O. Records of teletherapy electrical interlock tests were not maintained as prescribed in your license. O P. Other i f a C (hRC Irapector)

        ' The NRC Inspector has explained and I understand the items of noncompliance listed above. The items of concompliance will be corrected within the next 30 days.

s ', , (Licensee Representati"e - Dtle or Positson) [ (Dare) ORIGINAL TO LICENSEE h[h/fjkY{1 -

I

   \

t UNITEo STATES o**"'8%

                                 **,                   NUCLEAR REGULATORY COMMISSION l               ;,                                                    fiEGION lli E                     E E                     f                            799 ROOSEVELT MO AD coca ettvu. itunOis soin
               $              j#

l . ....+ Attached INSPECTION REPORT NO. N8 ~/YY9!M-6 / ( ) Appendix A DVEAR k M PACE CEF, (Licensee name/ address),,_, ( ) Appendix B

                          / "2./ O A /Mtf/(. c 04/ KD,                                            ( ) Appendix C M4/ . 8d/O 4///f/f~                                           .

Telephone No: "2lla-7N -Y07I bdI- /Y0/ Last amendment & date: #v4 Rf i / / 7 '[ License No. Docket No. 76 A. ~/Y 79 & Priority: 2 ,as of last amendment. Category: Inspection date(s): Yf/A- 7 E Type of inspection: E44.7y + 4FE7V l /

                                                       /

l

SUMMARY

OF FINDINGS AND ACTION o noncompliance, clear 591 ( ) Noncompliance, 591 issued ' ( I I+ ( ) Regional action ( ) Eq action ( ) Noncompliance, Appendix A ( ) Supplemental info, App C ( ) Action on previous n/c, App B RECOMMENDATIONS I See basis in Appendix C or attached memo. ( ) Change Priority to: ( ) Change Category to: ( ) Next inspection date: N~29

                                                                  /
  • l l

PERSONS CONTACTED (NAME AND TITLE)

                       # Ji Ce EEtpscHER                                    $/4UACER Sp1WECC -4WD bbeUNf'C.C                i
                       " W L , SDu.8 Y                                      W/AWAesR             SEcuein' i  0OER                                 H'dICif 0STL57/US. sis /DfleTOFXYO             !
  • Indicates those attendin management meetings Y 7!~/ F Inspector:

Approved:

                                                                                                       ~

i (date' signed) l

           '                                        (signature)                                                             }
                                                                                                                            \

MC 1005 4/77 i i

( Procedure No. 77710B l INDUSTRIAL - ACADEMIC INSPECTION REPORT Licensee: Per r' V + / - r- d4/> Lic. No.fkk//'/f / Amendment No. / Date of Inspection: i

                                    / Z -/7h7
1. INSPECTION HIS*IVRY
a. Items of noncompliance or safety items noted during last inspection conducted on 9' / 4 - 2 (> )77 Yes No
b. Requirement Corrected Not Corrected 100 f ld !), // f f~ V ID ef c' v'l: :,;c C." n- .: ( t, c.'[gr f. >c< .;,~ '
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c. If f'any tems of,'non mpliance or safety items noted during the last inspection were not corrected, explain: +
2. ORGANIZATION
a. Organizational structure as described in appifcation or letter Dated , Or .
                                                                                                                     ,      f 2f 2 GM-
                                                                                                                                 /

t Fet.usc ur r<. _Te1epnene No.: es6 -7e/- w,7<i-

b. List primary licensee contact:

[ b'fG-R ida.S.< d< tc5 n . < ' Ec t.r,~ . :c e

c. Comment: -
                                                                                                                  ? Il -76'/ ;:N'i b l.p' L_ C ( c Y tf             ,

2 Ms R - !Ce:i en ?f t - 4 et [f flf,4 fft .*" Qf G Yf n 9a.s %%s , .h4/ac. ~6d e4 i ted- a:1s'r<<.!pc:,c,, ' V a c u -u.~ 4!x [ & f ,b , d c 'avc/ tb l viewy en, /MLus twcf ^ wsuics k' a dua h &s h%eco y ju,yJu - ,a~ et Gww L.ata m yu Itu ca vMue.e'j(tt L /us}n.w%KM }+t - .cMt. wb'e.L 2.w c.Lu el.< es .emiI a.a6d.< bec , w%%., ,

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                                                                                                                                                         )
5. TPAINING RETRAINING AND INSTRUCTION TO WORKERS
a. Training program specified in L/C or application: Tes No
b. If training program is required, describe scope of program:
c. Retraining required: Yes No If "Yes" is retraining: ' Complete Incomplete
1) Are tests and/or examinations required: Yes No V If "Yes" are records available: Yes No 2)
3) Reviewed test results: Tes No
4) Period reviewed:
5) Comment (per cent conpleted, test results, etc.): ,

l

d. Training provided, but not covered above:

J4

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e. Instructions to workers in accord with 10CFR 19.12: Yes / No 9
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b. Capability of radiation survey instruments adequate for program:

Yes [ No

c. Calibration of instruments required: Yes No
d. If "Yes" instruments calibrated in accord with requirements: )

i Yes No

e. Consent: , J. < * / ' c 'C ' ' .
                      -   " .;, : "       ;. . < - - w:       .
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8. MATERIALS
a. Radioactive material secured to prevent unauthorized removal from:

l i 1) Restricted area: Yes / No ! No j 2) Unrestricted area (20,207): Yes \ l l Method of control appears adequate: Yes / No _

b. l I

NY4%'t& .c w d lat 6l( .<< < h./ [ b eEe Y ef it-c :fc .

c. Comment:
                     $ uw<jWw- nw ne t s'e r t n4ml$A - tctrn<L. W n'ss.i:cC.                       '
                    . h e u r w l L L / w c. d 4 . ,                                                                                 -

6

9. FACILITIES - (0/ft G '6-Facilities described in letter or application: Yes / No_

a. Facilities inspected: Yes

                                                            #           No b.
c. Comment: !A Y Oc x e EC t:'S[.t % e { v ccle.c_ s w Q A Y4c'f
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    -                fBCESAVy u/be'tAA- AA .tv c leenr.c k- .L . O . bht wh<; ocC/sctsh 4. hd hc'd Yl, r&

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d. Records of receipt and transfer of material available (30.51(a); 40.61(a);
70. 51(b) (1)): Tes No
                                                                            /      No
1) If "Yes" review of records was made by inspector: Tes
2) Period Reviewed:

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                                                 / 7 -        h' /f II

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3) Coments: l l

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e. Packages on hand meet labelling requirements (49CFR 173.399):

Yes No I Comments: l l l l l I f. Reports to commission required by L/C or regulation submitted: l Yes No Comments: 00)lM tf/WusS/H *te'bkitt.$ Chrtrcot:1h&$a

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12. PERSONNEL RADIATION PROTECTION - EXTERNAL
                                                                                 #M/!,
a. Film or TLD badge supplier /b [re h C. ,

Badge exchange frequency 2 IhW44ZA[W.f7 c 4'wd4 b.

c. Reports reviewed by__ W/44/tt(JN. 4f A t/ g.R < (-stc.e 65 Records reviewed for p'eriod 77 to V!7F dy NRC inspector e.
                                               /               I
f. NRC forms or equivalent Complete: Yes No
    ,.         1) NRC-4 (20.102(b)): Yes [ _No No    __ Complete: Yes         :o
2) NRC-5 (20.401(a)): Tes _

ht?8-2TM#r4def[ <t/ p d 2 F h a , Maximum whole body quarterly exposure:

                                                           / A/f_      q Maximum extermity quarterly exposure:

12/76

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c. Respiratory protection program required by L/C or appifcation:

Tes No

1) If '"Yes" were respiratory protection procedures reviewed:

Yes No

2) Respiratory protection procedures appear adequate: Yes 7 No
3) Comments: GCLtLt L kM ,arej / ~ $% /t?$htl AYYZ
             + bu mbw de- 6 c% uf, (Q&

ber,cwe,a ju dda w n/ Tfuu. aC ~Aug Of/ t$[(A f tf<uh2< ef , f n Bioassay program required: Yes ( No d.

1) If "Yes" was bioassay program reviewed: Yes [ No
2) Bioassay program appear adequate: Yes # No
3) Comments:

d 8 YM /C4M4< frf e t ' b[t t 2eah%Alje Sbn. 'blev falsvY U] n s'c. u c "aa <wd jvac atu c , Wc M W l x /977tuc/ l$ 7I b[ L. O d e'd er Y (,, h C .f $ b it t i Smears and air samples

                                            << a s s a (i m - v <,ca: 4                            Ju . l e.
1) Monitoring for airborne radioactivity is conducted (20.103):

Yes # No

a. Records of monitoring reviewed: Yes / No
b. Period reviewed: 7 ~2 0 N
c. Records of monitoring appears adequate: Yes / No
                                                                                #         No
2) -Smear surveys being conducted (20.201, b): Yes
a. Records of smear surveys reviewed: Yes No_
b. Period reviewed:

Records appeared adequate: Yes No c.

3) Comments:

1 $N 3

                                                     ' / Ebb Y     Y{~l Yh'                c:'/b b 'if
                                                                /
                                                                            - i h w ' ll 'i." ? -
                                                                                      /            /

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16. SHIPPING INCIDENTS
a. Have any shipping incidents occurred since (date)  %
1) Was incident documented: Yes No [

If "Yes" documentation appears adequate: Yes No 2)

b. Comments (reports to DOT, etc.):

I i

                                                                                                    )
17. NOTIFICATIONS AND REPORTS
a. Licensee in compliance with 10CFR 19.13 (reports to individuals):

Yes No

b. Licensee in compliance with 10CFR 20.405 (over exposures):

Yes No Licensee in compliance with 10CFR 20.403 (incidents): c. Yes No

d. Licensee in compliance with 10CFR 20.402 (thef t or loss):

Yes No

e. Comments: y hf/al, kg.c kl.t4f A# &tAJW Y A4W dl
     ~   ~~

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21. INDEPENDENT ?NSPECTION EFFORT j
a. Coment on type of independent inspection ef fort conducted:

kYS Yt G

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22. CONTINUATION FROM PREVIOUS PARAGRAPHS - USE BACK OF PAGE IF NECESSARY ,

e 4 g 0 em - 12/76

MAY 121978 Docket No. 70-1489 Goodyear Aerospace Corporation ATTN: Nr. J. C. Feldscher Manager Business Planning Akron, 0 11 44315 Gentlemen: The enclosed Circular No. 78-03 is forwarded to you for information. No written response is required. Should you have any questions related to your understanding of this matter, please contact this office. Sincerely, James G. Keppler Director

Enclosures:

1. IE Circular No. 76-03
2. Listing of IE Circulars Issued in 1978 cc w/encis:

Central Files PDR NSIC RIII y RIII I OFFICE > / ------ <. - - - - - - - - - - - - - - - - - - - - - - - - - - < - - - - - - - - - - - - - - - - - - - - - ' Davis /;p...-m..

                                         .s                    pler                                                                                                             j suRwauc > _______...-..__... _ _ - . . . . . . - - - - - -- - - - - - - - - - - - - .. - - - - - - - - - - ~ - - - - - - - - - - - - -         - - - - - - - -

5/10/78 - - - - - - - - - - - - - - - - - - - - - - o Atr > . - _ _ _ _ _ _ _ ..____-___-_-__.- - _ - - - - - - - - - - . - - - - - - - - - - - - - - NRC Form 318A (R2EE) (5-76) NRCM 02040 *U. S. GOVERNMENT PRINTING OFFICE: 1978-253-83 , i A /l l uonsown

l l IE Circular 78-03 May 12, 1978 PACTAGING GREATER THAN TYPE A QUANTITIES OF LOW SPECIFIC ACTIVITY RADI0 ACTIVE MATERIAL FOR TRANSPORT This circular describes a situation that has occurred at nuclear power facilities and that could occur wherever greater than Type A quantities of low specific activity (LSA) radioactive material are packaged for transport. Some licensees subject to the requirements of 10 CFR Part 71 have shipped packages containing greater than Type A quantities of LSA material in packages which are not authorized by NRC. These unautho-rized shipments have resulted from inadequate understanding of Part 71 regarding LSA material. Differences between Part 71 and the Department of Transportation requirements in 49 CFR Parts 170-189 have apparently contributed to these misunderstandings. Specifically, 49 CFR 173.392 authorizes the shipment of LSA material in " strong, tight packages" when transported in vehicles assigned for the sole use of the consigner. DOT regulations make no mention of the total activity that may be shipped in this manner. On the other hand, NRC regulations (10 CTR 71.3) require that no licensee shall (a) deliver any licensed materials to a carrier for transport or (b) transport licensed material except as authorized in a general or specific license issued by the Commission, or as exempted in Part 71. The general license of 10 CFR 71.12 has requirements for the type of container when more than a Type A quantity of radioactive material is to be transported. LSA material in excess of a Type A quantity is not exempt from the general license requirements. Several licensees have failed to recognize the difference in the DDT and NRC requirements and have packaged greater than Type A quantities of LSA material for transport in containers other than those authorized by the general license of 10 CFR 71.12. Compliance with Part 71 is the responsibility of the NRC licensee who delivers licensed material to a carrier for transport or who transports such material outside the confines of his plant or other place of use. No written response to this Circular is required. If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.

( IE Circular 78-03 ' May 12,1978 0 LISTING OF IE CIRCULARS ISSUED IN 1978 .. Circular Subject . First Date Issued To No. of Issue 78-01 Loss of Well Logging 4/5/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating Oil 4/19/78 All Holders of for Terry Turbines Reactor Operating Licenses or Construction Permits 9 9 L

s , 1 4 JUN 121978 Docket No. 70-1489 Coodyear Aerospace Corporation ATTri: tir. J. C. Feldscher Manager-Business Planning Akron, Oli 44315 Centlernen: Enclosed is IE Bulletin flo. 78-07 which requires action by you with regard to your fuel cycle facility. Should you have questions regarding this Bulletin or the actions required of you, please contact this office. l Sincerely, j James G. Keppler i Director

Enclosures:

1. Bulletin No. 78-07 l
2. List of IE Bulletins Issued in 1978 -

l cc w/encia: Central files  ; PDR tiSIC RII RIII orrece > - - - - - ..-- -- - - - - - - - - - - - - - - - - - . - - - - - - - - .. - - - - - - - - - - - - - - - - - - - - - - - Davis pier suRw Auc > _--_-------- -. - - - - - - - - - - - - - - -- - - - - - - - - - - - - . - - - - - - - - - - - -- - - - - - - - - - - - - oATc > _-_6/12/ 78- - - - - - - - - - ..- ---_--__---. - - - - - - - - - - - - . - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - NRC Form 318A (RIIE) ($~76) NRCM 02040 *U. 5. GOVERNMENT PRINTING OFFICE: 1978-253-838

.N, i 1 U.S. NUCLEAR REGULATORY COHHISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III l June 12, 1978 j IE Bulletin No. 78-07 i l PROTECTION AFFORDED BY AIR-LINE RESPIRATORS AND SUPPLIED-AIR HOODS Description of Circumstances: When the Nuclear P2sulatory Commission (NRC) established its current l regulations and guidance on acceptable programs for respirato n pro-tection (10 CFR Part 20, 20.103(c) and Regulatory Guide 8.15), it announced its intention to revise the guidance as better information could be obtained and made available. The Los Alamos Scientific Laboratory (LASL) has been developing pertinent information under NRC contract and has submitted a Progress Report on protection factors for air-line supplied-air respirators, LA-7098-PR, and an Informal Report on supplied-air hoods, LA-NUREG-6612-MS. A. Air-line supplied-air respirators The report on air-line respirators indicates that the protection provided (protection factor) by certain full facepiece and half-mask facepiece, demand-mode-operated, air-line, supplied-air respirators is significantly less than was previously estimated from the limited information that was available when the protection factors in the current NRC guidance were published (Regulatory Guide 8.15. Table 1) . Specifically, the current guidance lists protection factors of 10 for half-mask facepieces and 50 for full facepieces that are used with air-line equipment that is operated in the demand mode. The information in the LASL report indicates that much of the equipment of this type, even though NIOSH-MESA

  • tested and certified, does not achieve a protection factor greater than 5. The report recommends that such equipment no longer be certified by NIOSH nor approved by NRC for use.

B. Supplied-air hoods The report on supplied-air hoods emphasizes the importance of maintaining a minimum air flow of 6 cubic feet per minute (approximately 170 1pm), and recommends a protection factor of 1,000 at this air flow if calibrated

  • National Institute for Occupational Safety and Health-Mining Enforcement and Safety Administration, responsible for respirator certification.

MESA is now designated MSRA, Mining Safety and Health Administration.

a f - e IE Bulletin No. 78-07 June 12, 1978 air-line pressure gauges or flow measuring equipment are used. A protection factor of 2,000, as given in the current NRC guidance, is recommended for supplied-air hoods only when air flows are maintained l st the manufacturer's recommended maximum rate. The NRC will further evaluate the information in these reports and other I pertinent information and will revise its guidance as appropriate, e.g., 1 l by reducing the protection factors permitted, or by eliminating the f ( approvals for or specifying particular conditions for the use of such - equipment. It is recommended that the following actions be considered by all licensees who have respiratory protection programs:

1. A protection factor of no more than 5 should be utilized for l

half-mask and full f acepieces that are used with approved air-line equipment operated in the demand mode.

2. A protection factor of no more than 1,000 should be utilized for approved supplied-air hoods when the air flow is maintained at 6 cubic feet per minute and calibrated air-line pressure gauges l

or flow measuring equipment is used.

3. A protection factor of 2,000 should be utilized for approved l supplied-air hoods only when the air flow is maintained at the manufacturer's recommended maximum rate, this rate is greater than 6 cfm, and calibrated air-line pressure gauges or flow measuring equipment is used. ,

l Actions To Be Taken By Licensees: For all power reactor facilities with an operating license, all research reactors with an operating license, all fuel cycle f acilities with an l operating license and all material licensees receiving this Bulletin:

1. If your respiratory protection program includes the use of air-line supplied-air respirators operated in the demand mode (not respirators operated in continuous-flow or pressure-demand modes) or supplied-air hoods, describe the actions you plan to take to assure proper protection of personnel in consideration of the l inf ormation provided by this Bulletin.

l l

t W l l I June 12,1978 IE Bulletin No. 78-07 i I

2. If your respiratory protection program includes the use of air-line eupplied-air respirators operated in the demand mode i (not respirators operated in continuous-flow or pressure-demand I modes), determine the manuf acturer, model and number of half-

' mask and full facepiece equipment used in this mode. l j

3. Report in writing within 60 days the information required in items 1 and 2, if applicable. Reports are to be submitted to the Director of the appropriate NRC Regional Office listed in Appendix D of 10 CFR Part 20 and a copy forwarded to the Director, Division of Fuel Facilities and Materials Safety Inspection, U.S.

20555. NRC, Office of Inspection and Enforcement, Washington, D.C. Approval l Approval by GAO, B180225(R0072); clearance expires 7/31/80. l vas given under a blanket clearance specifically for identified generic problems. l l l l l l ll l I b , I l  !

 \'

1 4 IE Bulletin No. 78-07 June 12,1978 LISTING OF IE BULLETINS ISSUED IN 1978 Date Issued Issued To Bulletin Subject No. 1/16/78 All Power Reactor 78-01 Flammable Contact - Facilities with an Arm Retainers in G.E. OL or CP CR120A Relays 1/30/78 All Power Reactor 78-02 Terminal Block Facilities with an Qualification OL or CP Potentini Explosive 2/8/78 All BWR Power 78-03 Reactor Facilities Gas Mixture Accumula- with an OL or CP tions Associated with BWR Offgas System Operations

                                                    ~

2/21/78 All Power Reactor 78-04 Environmental Quali- Facilities with an l fication of Certain OL or CP Stem Mounted Limit l Switches Inside Reactor Containment Malfunctioning of 4/14/78 All Power Reactor 78-05 Facilities with an Circuit Breaker OL or CP Auxiliary Contact Mechanism-General Model CR105X 5/31/78 All Power Reactor 78-06 Defective Cutler- Facilities with an Hammer, Type M Relays OL or CP With DC Coils l Enclosure l l Page 1 of I  ! I

i

       =w*=*=~.'*'                                U.S. W U LL t.M M M e;t.cV L M 4 U M Y LUMMibblON E 3-773                                    OFFICE OF iMsP EC TION QMO ecd F ORC EMP
  • INSPEL(ION FINDINGS AND LICENSEE ACKNOWLe.DGMENT i

i

9. LeC E N 5 E E 2. R E ce00N AL OF FIC E
                                                   -                                  U.S. Nuclear Regulatory Com:nission
                     &            NN              b           -O        ~

Office of Inspection and Enforcement [O R P, Region III

              /2/O NM S /L. L O N NDa                                                 799 Roosevelt Road d/,mO A/ , 8M t/t/F / g--                                               Glen Ellyn, IL                 60127
3. DOCMET NUMBER (5)# e. L8 CENSE NUMBER ($) a. D ATE OF BNSPECT80N 070 O. eNSPECTION FINDINGS W W $h/M - /Wc / 32z 79
                                                                                                                                    /

The inspection was an esamination of the activities conducted under your license as they relate to radiation sarety and to compliance with the Commission's rules an'd regulations and the condstions of your license. The inspection consisted or selective esaminatmns or procedures and repre-sentative records. enterviews with personnel, and observations by the inspector. The rendings e a result or this mspection are as rollows: No items of foncompliance or unsafe conditions were found. The following items of noncomphance related to records, signs, and labels were found: O A. Rooms or areas were not properly posted to indicate the presence of a RADI ATION AREA.10CFR 20.203(b)or 34.42 B. Rooms or areas were not properly posted to indicate the presence of a lilGil RADIATION AREA. 10 CFR 20.203(c)(1) or 34.42 C. Rooms or areas were not properly posted to indicate the presence of an AIRBORNE RADIOACTIVITY AREA. 10 CFR 20.203(d) O D. Rooms or areas were not properly posted to indicate the presence of RADIOACTIVE M ATERI AL.10 CFR 20.203(e) E. Containers were not properly labeled to indicate the presence of RADIOACTIVE M ATER! AL. 10 CFR 20.203(f)(1) or (f)(2) F. A current copy of 10 CFR 20, a copy of the license, or a copy of the operating procedures was not properly posted or made available.10 CFR 20.206(b) G. FormNRC.3 was not properly posted.10 CFR 20.206(c)

11. R; cord, of the radiation exposure ofindividuals were not properly maintained.10 CFR 20.401(a) or 34.33(b)
1. Records of surveys or disposals were not properly maintained.10 CFR 20.401(b) or 34.43(d)

O J. Records of receipt, transfer, disposal, export or inventory oflicensed material were not properly maintained. 10 CFR 30.51,40.61 or 70.51 K. Records ofleak tests were not maintained as prescribed in your license, or 10 CFR 34.25(c) O L. Records ofinventories were not maintained.10 CFR 34.26 O M. Utilization logs were not maintained.10 CFR 34.27 O N. Records of radiation survey instrument calibration were not maintained.10 CFR 34.24 O o. Records of teletherapy electricalinterlock tests were not maintained as prescribed in your license. P. Other f (hRC In.snector) ~

        ' The NRC Inspector has explained and I understand the items of noncompliance listed above. The items of noncompliance will be corrected within the next 30 days.

( (Date) (Licensee Representati~e - Tetle or *osition) ORIGIN AL TO LICENSEE M/d-N h

e 4 UNITED STATES

               ** mas NUCLEAR REGULATORY COMMISSION p               *%                                               REGloN lll o

E 799 moostvELT mo Ao

                                                                                              ..n, U              'f                                      ou~ ru.va. itu o .
           #g,           j                                                                                             ;-

Attached INSPECTION REPORT NO. 70~ /M79 77-O/ ( ) Appendix A NdDtos 7",qer DORP r.> VEA R ( ) Appendix B (Licensee name/ addressl4 P: ( ) Appendix C 1 2 /O A4MC/L L.N/ -

                     'rhi<ROtl', 0l/                   4L/5 / 5"                                               (}
  • do c[ 54< A/0,W<dw
                                                   ,2./ b- 7 // Y        '/ (o ~lj~

Telephone No: ~ 7 7 7 /o S Last amendment & date: License No. k /A7 - /V G / Docket No. ~20 ~ /@ 9 & Priority: 7__ ,as of last amendment. Category: .4 y /1_7_ /79 Type of inspection:dE44.-/// 4 b Fery Inspection date

SUMMARY

OF FINDINGS AND ACTION { ( ) Noncompliance, 591 issued ([Nononcompliance, clear 591 ( ) Regional action ( ) Eq action i ( ). Noncompliance, Appendix A j ( ) Supplemental info, App C ( ) Action on previous n/c, App B RECOMMENDATIONS See basis in Appendix C or attached memo. ( ( Change Priority to: I f ( d Change Category to: F---- _ ( ) Next inspection date: 3 /Tr 2.  ! I , 1 PERSONS CONTACTED _ (NAME AND TITLE) _v c Fei.oscsien -- Aucer be a+ t cwwou l JfCR 0% ATE lWDFSTR//it. son svery YG-/E h$ NESS 5 D fDDt2 /AM7xu'MENr AND TE$r EN6/WEER*

                                                                                          &&ACEK, SEcu'nirf 1

ld/ l. $t 39' /

                                                            ^

tendin management meetings I

  • Indicates those 4' _

Inspector: b [fcI

                                                 ~       /jf(,'e#**"'4'1,<em~
                                                                           /jo
                                                                                      /)                     (d"'1**M*79 at /,Q            '

Approved: h, ' (date' signed) t ' (sigriatur e)~ l MC 10,05 4/77 t

Procedure No. 77710B

     ~

INDUSTRIAL - ACADEMIC INSPECTION REPORT Licensee: hMusn kpu s}y/w0t), Lic. No. (4//f~/V(s / Amendment No. l Date of V f Inspection: 2!2.'z.[ l76 l ( l

1. INSPECTION HISTORY
a. Items of noncompliance or safety items noted during last inspection conducted on 4/[/ 2. ~ /r /7 7 Yes No
                                  /           /
b. Requirement Corrected Not Corrected
c. If any items of noncompliance or safety items noted during the last inspection were not corrected, explain:
2. ORCANIZATION
a. Organizational structure as described i plica or letter Dated Il[W , Or
b. List primary licensee contact: V,C , Fre.asc /<ce _ _Telepbone No. :N/6-79</-</g,.
c. Comment: Y$ 2c Off2 &lMW f/ hf cd& tick 5, Y't , uh 42ecf <Y <he ^ bed /S G65 ekcll&o , aacauuYah2<$<, iAfoj<l andysa Jah al/

ak 6A-Js e , Opadst L, '/Asc, blaasx c/ khavak cSrsdha'al 4/ygada awl fap9'y au) Tscrit%a 'P.Asc% flan, his ed/ wfiM Ja n/Ay, .4dux& 4 r d 4 } p t rep cl'.' y 0

l 1

3.

SUMMARY

OF LICENSED PROGRAM (Kind of program, number of people, rate of use or j quantities on hand, places and frequency of use, type, quantity and use as j l authorized). l ls44M4SS .h/S/44tb t24<l 0(AV /t&Y W tt4Yh6CS y.nsaM /wnbws , Cadt guaakker ofltha ut: eu 4%<Lt2 rn(vop J)uix<<wl C-.ea a m m % v a. w d a m t x 4 b / w / c1'<' l6 d &f A ac?6u}qG c/<rfdx, , tif9 /cs Q nu& 9, an;&,&, nfhaldd/ e>yJ/uuad dc.au pn.As4 it aud'cl<aushne 4- Akeuur wash.'dajnd scujauf Admd UG <: Affw w a de- , ry d priority of this license is appropriate: Yes No I f "No" " b f'"f' Priority . WtenewCategoryaa A Mspy

                                                  &    t( _.2ir
4. INTERNAL AUDITS OR INSPECTIONS
a. Required by L/C or application: Yes No If "Yes":
1) By whom
2) Frequency Announced: Unannounced:
3) Scope
4) Records maintained: Yes No
5) Records reviewed: Yes No
6) Period Reviewed:
b. Comment (responsibility of auditor or committee, management control) 12/76

3-

5. TRAINING RETRAINING AND INSTRUCTION TO WORKERS
a. Training program specified in L/C or application: Yes V No
b. If training program is required, describe scope of program:

he Vta<u N 1 C L Y h h l u d N b b h Y tttiteE< c h hhSN< W juv x< of L444 tt .4 ccci Cxk5 McY4iY h L y b t h AA.fC2SStthef H-

                                                 $ tt Y & h 4. h b.u.           J. N
c. ng required: Yes No V~

If "Yes" is retrainging: Complete Incomplete

1) Are tests and/or examinations required: Yes No /
2) If "Yes" are records available: Yes No l 1
3) Reviewed test results: Yes No
4) Period reviewed: i 1
5) Comment (per cent completed, test results, etc.):
d. Training provided, but not covered above:
                                                                      'c b 45tc Y h ct &

cw cf kFY M<f L< 9 1 gb- & E UFs luusueL ,4 'cle es<8(nue-<L 2%ia, a<de g Jup<hasless, sUF had ksfabr,Ih-, @A ah<S ' V

          & s ' & m te a s b v p ,s I     V i       e. Instructions to workers in accord with 10CFR 19.12: Yes          No l
     .                                               I fi . RADit't.0Cll'AL l'ROTECTION l'ROCEDURES
o. espu6 el sHB Mll4 W8*6 eWH'aY PfH4#d4fS8'
1) Required by L/C = plication: Yes No j
2) Provided, but not required by L/C or application: Yes No
3) Procedures reviewed: Yes No
4) Appeared Adequate: Yes No
5) Comments (personnel's understanding of procedures): cI/t40t<u<M 6f4l 9Y YUE(4 GAc. WC,4 5 t
                                            /                        /

l l

b. Changes in procedures since last inspection: Yes No [

i

1) Were changes authorized: Yes No
2) Comments:
7. INSTRUMENTATION
a. Type (s) of radiation survey instruments on hand as per L/C, application or equivalent: Yes / No
1) If "No" list changes: [F S/1/ed E (A<4t.< Y+n/M 4/aa : 2. C4-<>dd L "* P-4 c h ) b a e s .

[6ashe se6%fa J.sc . Vie 8 % m dea WGo*7%ac, Tk Ah aNAt<nuz81 $ d azA 6.- nds9w%- /W 4ts4 Y den %udi '~B M6 typea , 12/76

                                            ?
b. Capability of radiation survey instruments adequate for program:

Yes No

c. Calibration of instruments required: Yes No
d. If "Yes" instruments calibrated in accord with requirements:

Yes No

e. Comment: W G Gt2bhba/ t2tlct4N<FY $4h15Ett.,

S hu <<rckb

8. MATERIALS
a. Radioactive material secured to prevent unauthorized removal from:
1) Restricted area: Yes No
2) Unrestricted area (20.207): Yes No
b. Method of control appears adequate: Yes / No
c. Comment: hNb H.Afd d $44AL/ N O' Y asaa. i G<& mN .hu'& N}'"O V

i

9. FACILITIES gg ,
a. Facilities described in letter or application: Yes No
b. Facilities inspected: Yes No
c. Comment: Oft swd @ i sa<W a&.,cu /

fil V & t l'  ! (/ 12/76

e i 10. POSTING AND LABELING

a. Posting and labeling in accord with 10CFR 20.203: Yes No
b. Comment : YV JtacG'tYesNt c tth f k C i Y l/kYl< 4.+.C aad & chag<. amas am pn/vd',
                             !               /                        /
11. RECEIPT AND TRANSFER OF MATERIAL
a. Procedures for picking up and receiving packages (10CFR 20.205 (b)(c)):

Yes [ No

1) Incoming shipments monitored: Yes [ No
2) Records of monitoring maintained (10CFR 20.401(b)): Yes No
3) Records reviewed by NRC inspector: Yes / No
4) Period reviewed: I 7 -

C[4- /i 7

b. Procedures for opening packages (10CFR 20.205(d)): Yes No
c. Comment: AlA Vk h/bNiS t s h.9 & d ,

914 k W M 4C Y VA dupei$q }wd& i i /

s

    .                                                                                              j i
d. Records of receipt and transfer of material available (30.51(a); 40.61(a);

1 70.51(b)(1)): Yes [ No l 1) If "Yes" review of records was made by inspector: Yes No

2) Period Reviewed: h N / 9 7 7 - } 4 h [< /9 7f f
3) Comments:

I i

e. Packages on hand meet labelling requirements (49CFR 173.399):

Yes [ No Comments:

f. Reports to commission required by L/C or regulation submitted:

Yes No TauMc Comments: d// b ' Nf 3 AM/ M2' kf84k

                         /
                          ,Y                               Dh          NCA. <

v j

12. PERSONNEL RADIATION PROTECTION - EXTERNAL
a. Film or TLD badge supplier t/v.,+t 4. , / #M , Mib
b. Badge exchange frequency 7I 4 . YJI N f III # M*
c. Reports reviewed by ##N > #
e. Records reviewed for N c[./V /b^

period Y&c%S $)fhilfk 7 )r to 7/79 i by NRC inspector

  • I
f. NRC forms or equivalent M Ot*<W 4,s.tl f
1) NRC-4 (20.102(b)): Yes No Complete: Yes No
2) NRC-5 (20.401(a)): Yes No Complete: Yes No h

l Haximum whole body quarterly exposure: a /20 h w/f/f N/fCYof<*sw WH _ffG<A, ata]

                                                                                            / Q Y t /,

j Maximum extermity quarterly exposure: #Y A+tf af.4dt'.</

i ,

3) Comment: .4.fl'tuY flu 4L JetxcA u d a b h 't h s it MR $ 1 b*d ,
                          ),u~un v

A k 4adu k.(&Jura w y #[ /// 7eV ,) V /

g. Pocket dosimeters used: Yes No
1) Type used:
2) Frequency of recharging:
3) Frequency of reading:
4) Comment:
h. Direct radiation surveys of restricted and/or unrestricted areas being made:

Yes No [

1) Records of surveys being maintained: Yes No
2) Records of surveys reviewed: Yes No
3) Period reviewed:
4) Counents:
13. PERSONNEL RADIATION PROTECTION - INTERNAL
a. Potential for exposure of individuals to airborne radioactive materials exists: Yes No
1) If "Yes" does program for monitoring and control exist: Yes 7 No
2) Program for monitoring and control appears adequate: Yes / No ,
b. Comments: 4N ^ Sh 4e
                                                                                          , >.a

3 J

c. Respiratory protection program required by L/C or application:

Yes No l l 1) If "Yes" were respiratory protection procedures reviewed: Yes No Respiratory protection procedures appear adequate: Yes No 2)

3) Comments: N --- C.L. .kvt/J.$4 .c ./,0.w.c,rff h
              &                             W baut         t,. fg, YL.L. .J u & g /

a o 'a - ')2 hee 4 Au w& cauugl& 4,&nedan4, i e r m l & c; W ,4 % % i u rs , i V

d. Bioassay program required: Yes [ No
1) If "Yes" was bioassay program reviewed: Yes No
2) Bioassay program appear adequate: Yes / No
3) Comments: 444 (r' <-(d k 4d/

wMu . -kbe n- W w.L d u s u J w <. 3 a r a a < N All G 2. d bf$ *

                                                                  * $                              bs$cc p[ l k'It'W ati/1. ,

V i

e. Smears and air samples
1) Monitoring for airborne radioactivity is conducted (20.103):

Yes [ No

a. Records of monitoring reviewed: Yes No
b. Period reviewed: N 'I i,
                    . Records of monitoring appears adequate: Yes                             No c.

Smest surveys being conducted (20.204, b): Yes No 2) ! a. Records of smear surveys reviewed: Yes No /

b. Period reviewed:

Records appeared adequate: Yes ----

c. No_
3) Comments:

4 # 0'< $44'I VNA '14 0 W '4fe YM Aw.e. sam </ aug%xwe.e-. at esu%a&: acmma $ % A rff a g % f g; j n , i V t o Mc

4

14. LEAK TESTS
a. Leak tests required: Yes No
b. If "Yes" leak tests conducted: Yes No
c. Records of leak tests maintained: Yes No
d. Imak tests records reviewed: Yes No
e. Period reviewed:
f. Records of leak tests appear adequate: Yes No
g. Comments:
15. RADIOACTIVE EFFLUENT CONTROL AND WASTE DISPOSAL
a. Byproduct material released to atmosphere and/or sewer (20.106 and 20.303):

Yes No

b. Records of releases or radioactive effluents maintained (20.401):

Yes No ,

1) Period reviewed:
2) Records appear adequate: Yes No
c. Solid waste disposal method: /-u 44EN4 ( t/ / *f ze' <<

f O d

1) Records of disposal maintained (30.51): Yes / No
2) Surveys of waste prior to disposal made (20.201): Yes No TVUs(4c/ tidCd.a.uWMu' /r/l@ t<</e/ ,
3) Period reviewed:
                .Aunu - a n w r m a m .w arx, Records of surveys appear adequate (20.401): Yes              No b/rT 4)
d. Comments: turcl LUdC YdCAC 41 h4%bu Au $$

ces& th & S<h *g d 6q c & stl. a u d SN h d M l 4 d.-. L au i 'OFs v&a %fbid u<6 s%g&w ' awl su%w e d de- (MTispa. . i9/74,

l

16. SHIPPING INCIDENTS
a. Haveanyshippingincidentsoccurredsince(date)/f7/c P
1) Was incident documented: Yes -

No -

2) If "Yes" documentation appears adequate: Yes - - -

No

b. Coaunents (reports to DOT, etc.):
17. NOTIFICATIONS AND REPORTS
a. Licensee in compliance with 10CFR 19.13 (reports to individuals):

Yes No

b. Licensee in compliance with 10CFR 20.405 (over exposures)

Yes / No

c. Licensee in compliance with 10CFR 20.403 (incidents):

Yes  ! No

d. Licensee in compliance with 10CFR 20.402 (theft or loss):

Yes V No

e. ' Connaen ts : YB - AAlld ltaf & c/ ttuu W a5 >w/4, '
                                       /

4

18. POSTING OF NOTICES No
a. Licensee in compliance with 10CFR 19.11(a) or (b): Yes
b. Licensee in compliance with 10CFR 19.11(c): Yes / No l
            ~c. Comments:

l l 19. ENVIRONMENTAL MONITORING PROGRAM 1

a. Environmental Monitoring Program required: Yes No /

No

b. If "Yes" records reviewed: Yes l c. Period reviewed:

Records appeared adequate: Yes No d.

e. If Environmental Program is not required, briefly describe any existing program:
                                                                                                )

l

20. CONFIRMATORY MEASUREMENTS Yes No
a. Independent measurements made by inspector:
b. Comments (describe type, results, comparison with licensee results):

stt$7%d Asdelafae.44st }uUak fc/, NW [64 ' V V f 12/76

v

21. INDEPENDENT INSPECTICN EFFORT
a. Cotment on type of independent inspection effort conducted:
                       .A<.thc'Ccl b< 'GZA<G <.J   k #ct                         k k.e4 Afu clJa^t du&&

Wi?am //e- d<aue,ss .sh gi4% or cls/w

                   'e/

we%'aL x/v/(wd u /k<sua/x< .Ju& ,

22. CONTINUATION FROM PREVIOUS PARAGRAPHS - USE BACK OF PAGE IF NECESSARY St.tcrok t h & Y d C C<. h 'c' S s c h c<a2Ia/ A ! '" VUc1 .AAna c a>e AscsA ccat iA V

60M1 sA'9%aud kE wl!'<A-- V i d'f JLtaY f(%<.tJ-- }p YJ h eA-. W }to W et,'t u $

  • W t

bu4/Y b rikA F6/<A k NY/sadYY" f ' ' ivw u tenua) .w 0G B 'LL &n > a. Gai a mJ.1.ha4<.Mp'<at laAl.4% 4u as,/ f

                      <4afs jw pnAs Aebm ef 24i , Wnm,
                     &J a. '.xwx au/ hwpa1e<i E(
                     "l<tudA.iu t, al l.c    A.u tb 7YC                            Lbd            h  b 'e-l A Am<h.                                                                    '
                                                                                            /f 2CylC}l, j E n s+t et.x      tuiW& a' UL e. d h b^t!da<W D-ahca & JA/Af' ]<s+-- .Jaczsk Lx oce<rb4aaak " P&6 wu<As tu TV i.FLeadI p/ 5 uiGcA uis<<.'td' .A.'g.c<d.s                              t

\ al<skrefa 8<."6; wery diAt yeah.c heZL V Wu. itsu u a.lfv' <

                                            /

12/76

e. .

INSPECTION PLAN NO REPCRT MMIER 3 Pl.ANNING SHEET Date: '/ P.7 7f Licensee: M r d s.9 LuN/amet - License no: N////-//6/ - f / / Scheduled for Post-inspection Wule M. 7 M Tim I m I Im m tion Ih m (Aspection status l . l Management meeting . Entrance j and EJtit Interviews 307038 tasoazazo; Initial Management Meeting 30800B Program requirements. 2 ac ta_ . 777/08 Y , Imacc1xsof l i I Licensee Event Followup 927006 l Followup on Inspector-identified problems 927018

  • Followup on Monconcliance and Deviations 927028 IE Bulletin /!senedtate Action Letter Followup 927038 l -
              ~. ~

Feltowup on .. "' .m _ . --

  • Headqua,rters Requests .

927048 Followup on . Regional Requests $270 5 l Independent Inspection III 92706B / . Insoczazol +

                         , taspector Dispatched to site             -                                                 937006
                                                                                                                                 ,p   , . .

Fo11owup on significant Event Occurring During, Inspection 93701B 6

                                   *=                                        e gum
  • p eu O

l l .

     ** M%g                                UNITED STATES f

f 1 NUCLEAR REGULATORY COMMISSION f $ REGloN 111 E ^f 799 ROOSEVELT RO AD D GLEN ELLYN, ILLINOIS 60137

   %,*****$[                                    ~

APR 3 01979 MEMORANDUM FOR: J. A. Pagliaro, Chief, Materials Radiological Protect on ect n No. 2 av THRU: W. L. Fisher, Chief, Fuel Facility Projects and Radiation Support Section FROM: C. C. Peck, Fuel Facilities Inspector l l

SUBJECT:

CATEGORY AND PRIORITY CHANGE FOR GOODYEAR AEROSPACE CORPORATION Goodyear Aerospace Corporation operates an Enrichment Equipment Research and Development Facility near Akron, Ohio. Special Nuclear Material License No. SNM-1461 permits this licensee to possess and use source and special nuclear material. Possession limits are 349 grams of uranium-235 contained in a maximum of 46.0 kilograms of total uranium. The licensee receives natural UF 6 in 50 pound containers from a DOE facility and enriches small quantities of the UF6 slightly in the course of research and development work. After use, the UF6 18 recovered and returned to the DOE facility, except for small quantities disposed of as contaminated waste. Since issuance of the license in 1974, receipt and return of UF6 have averaged only about one container per year. The licensee also possesses small quantities of UF6 laboratory standards having a range of enrichments. The licensee recently applied for renewal of his license. No increase in the possession limits was requested. The licensee stated during the inspection in March 1979 that no changes in his use of radioactive materials is expected in the foreseeable future. l l The licensee is now classified Category A, Priority II: "Use, processing, or possession of SNM in quantities and form which present some potential for radiological health hazards of potential for criticality." This I classification appears unsuitable because there is no criticality hazard and no external radiation hazard. The only health hazard, more chemical than radiological, is the possibility of a release of UF 6* Handling frequencies and quantities make the probability of such an occurrence low. 4h&/LWfCTC[~~ /

J. A. Pagliaro APR 3 01379 l l It is recommended that Goodyear Aerospace be reclassified Category E, Priority IV: "Use of byproduct, source, or SNM for research and development." The lower priority would require inspection every three i years rather than annually as required by the present classification. ' _) 1 - (..; / f f (: j C. C. Peck Fuel Facilities Inspector l l

r V l sv 18 m Y E__0W ii C0?Y Docket No. 70-1489 Goodyear Aerospace Corporation ATTN: Mr. J. C. Feldscher Manager, Business Planning l Akron, OH 44315 Gentlemen: 1

The enclosed IE Circular No. 79-08, is forwarded to you for information. If there'are any questions related to the contents or intent of the Circular or its attachments, please contact this office.

Sincerely, l James G. Keppler Director

Enclosure:

IE Circular i No. 79-08 , I cc w/ encl: Central Files i PDR NSIC RIII RIII d' Davis /blk Keppler 5/18/79 Q d9l-t 60$&lT0~ j

k d UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 May 18, 1979 IE Circular No. 79-08 l ATTEMPTED EXTORTION - LOW ENRICHED UPJWIUM

Background

In January 1979, a temporary contractor employee who was working at the General Electric plant in Wilmington, North Carolina, allegedly entered the plant and removed a drum containing two 5-gallon cans of low enriched uranium from the facility with the intention of extorting money for the return of the material. The Federal Bureau of Investigation conducted an intensive investigation leading to the arrest of the employee on February 1, 1979. All material was recovered and returned to the plant. l Discussion 1 i Based on preliminary information provided the NRC, the theft was allegedly carried out in the following manner: l l On Friday, January 26, 1979, the subject worked the day shift.  : At 10:50 p.m. the same day he drove back to the plant and entered with the night shift. He showed his Florida driver's license at the entrance gate instead of his yellow contractor badge because it had a blue background similar to that on the picture badge which he thought was required to gain access to the area of the plant that he wanted to penetrate. He had allegedly gained access using his driver's license on previous occasions. Once inside the plant, the subject would have been guided by gates and fences into a parking area had it not been for the fact that one gate had been removed to allow installation of truck scales. He proceeded down the unprotected road to an area adjacent to the building he wanted to enter. After the subject entered the building through a personnel door, he proceeded to his normal working station which was the Chem Tech Lab and entered, using his own key. In the lab he picked up his protective clothing, a two wheel cart used to move 55 gallon drums and a container used to ship chemicals. The container could hold two 5-gallon cans. l He then proceeded to a door leading up a stairwell into the radiation l

k i IE Circular No. 79-08 May 17, 1979 controlled area. The door was normally locked even though not required by regulations; however, at this time it was slightly ajar due to mal-function of the locking mechanism. Once inside the door, the subjcet put on his protective clothing and proceeded up the stairs to the Blend Queue Area. He removed two 5-gallon cans of UO2, carried them down the stairs and put them in the shipping container. He then removed his protective clothing and retraced his steps on to the Chem Tech Lab. Once back in the lab he opened one can and removed some of the material which he intended to use to effect his blackmail scheme. Using the 2 wheel cart, he transported the remaining material to his car and loaded it in his trunk. He retraced his steps and left the plant just before midnight on Friday, January 26. Procedures require anyone leaving the plant after midnight to sign out. He had ) been in the plant approximately one hour. He had come in with the i incoming plant change and had left with the outgoing shift. Conclusion The G. E. Wilmington plant had an industrial security system in operation at the time of the inci nt. This theft was facilitated by a failure of this system. The failcar to check the' subjects identification badge closely enough to distinguish a Florida driver's license from a General Electric badge authorizing access other than normal working hours and the failure to protect a disabled remotely operated gate which would have denied automobile access to the immediate area where material was stored were significant factors in the success of this theft. A third contributing factor was access to the

 . material through an emergency exit which was normally closed and locked against access to the area where the material was stored.

Although the circumstances surrounding the possible occurrence of an event similar to this will vary according to each licensee's operation and safe-guards system, the attached summary of this event clearly demonstrates the interrelationships of minor problems that seem insignificant if taken alone, but when combined, can allow a loss to occur. It also emphasizes that the possibility of an insider threat against a licensed facility does exist. l This Circular is issued for your information. No action is requested of you and no written response to this Circular is required. If you desire additional information regarding this matter, contact the Director of the appropriate NRC Regional Office. Attachments:

1. Sanitized Summary of GE Wilmington Incident
2. List of IE Circulars Issued ,

in the Last Twelve Months.

4 l (

     .                                                                             i 1 4 l                  Sanitized Summary of G.E. Wilmington Incident i

I. Summary On Monday, January 29, 1979, at 11:45 a.m., Region II was notified by telephone by the General Manager of the Wilmington, North Carolina, General Electric Company plant, that an extortion letter and a sample of UO2 powder were found at his office door when he came to work about 8:00 a.m. The letter stated that the writer had in his possession two 5-gallon containers of UO2 powder which he had taken from the plant. The containers were identified in the letter by j serial numbers and by the gross weight (approximately 145 pounds { total). The letter further stated that enough UO2 had been removed j from one of the containe',. .o furnish samples to newspaper editors, senators, anti-nuclear group leaders and others if his demand for

          $100,000 in cash was not met by Thursday, February 1. The writer further stated that after the samples had been delivered, if he had      I not received the money, one container of UO2 powder would be dispersed   {

through one unnamed large American City. The UO2 powder from the { second container would be dispersed through another large city if l an additional $100,000 in cash was not provided at that time. The General Manager verified the authenticity of the container numbers and the fact that the containers were not in their assigned locations. Region II advised the Office of Inspection and Enforcement, NRC, Head-quarters, and the Atlanta office of the FBI. The Atlanta FBI turned i the case over to the Charlotte, North Carolina FBI office. The FBI assumed investigative jurisdiction on Monday, January 29. It was decided not to send NRC investigators to the plant at that time, but that the NRC would wait for further developments and concentrate j on planning and related safety evaluations. On Tuesday, January 30, i two Region II investigators, knowledgeable in accountability and health physics, were sent to the plant to furnish technical expertise in the areas of material control and accountability and health physics, and to review GE activities to determine how the event occurred, with-out interferring with the FBI investigation. A temporary employee of a General Electric Company subcontractor was subsequently arrested by the FBI on 2/1/79. l The containers and all the SNM were recovered by the FBI and returned to GE. Attachment 1 Page 1 of 2 1 l l 1 l l l

t d IE Circular No. 79-08 May 17, 1979 II Conclusions The special inspection disclosed that: (a) the material control and accountability system functioned as designed and identified the missing containers in accordance with regulatory requirements; (b) health physics procedures were followed in accordance with regulatory i requirements; (c) normal industrial security procedures were followed; and (d) no items of noncompliance with regulatory requirements were identified. Attachment 1 Page 2 of 2

k (

 'l .

IE Circular No. 79-08 May 18, 1979 i LISTING OF IE CIRCULARS ISSUED IN ) LAST TWELVE MONTHS i Circular Subject Date Issued To l No. of Issue 78-03 Packaging Greater Than 5/12/78 All Holders of Type A Quantities of Reactor OLs, cps, Low Specific Activity Fuel Cycle. Radioactive Material Priority 1 Material for Transport and Waste Disposal Licenses 78-04 Installation Error That 5/15/78 All Holders of Could Prevent Closing of Reactor OLs or Fire Doors cps 78-05 Inadvertent Safety Injection 5/23/78 All Holders of During Cooldown Reactor OLs or cps 78-06 Potential Common Mode 5/23/78 All Holders of Flooding of ECCS Equipment Reactor OLs or Rooms at BWR Facilities cps 78-07 Damaged components of a 5/31/78 All Holders of

      -          Bergen-Paterson Series                            Reactor OLs or 25000 Hydraulic Test                              cps Stand                                                                ,

78-08 Environmental Qualification 5/31/78 All Holders of of Safety Related Equipment Reactor OLs or at Nuclear Power Plants cps 78-09 Arcing of General Electric 6/5/78 All Holders of Company Size 2 Contactors cps 78-10 control of Sealed 6/14/78 All Medical Sources Used in Licensees in Radiation Therapy Categories G and G1 78-11 Recirculation M-G 6/15/78 All Holders of l Set Overspeed Stops BWR OLa or cps Attachment 2 ) Page 1 of 3 l 1

IE Circular No. 79-08 May 18, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE M0hTHS Circular Subject Date Issued to No. of Issue 78-12 HPCI Turbine Control 6/30/78 All Holders of Valve Lift Rod Bending BWR OLs or cps for plants with HPCI Terry Turbine 78-13 Inoperability of Multiple 7/10/78 All Holders of Service Water Pumps Reactor OLs and cps except for plants located in: AL, AK, CA, FL, GA, LA, MS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of BWR Chamber Hold Down Bolting OLs or cps for plants with a ETCI Terry Turbine e.xcepting Duane Arnold and Monticello 78-15 Checkvalves Fail to 7/20/78 All Holders of Close In Vertical Reactor OLs or cps Position 78-16 Limitorque Valve 7/26/78 All Holders of 4 Actuators Reactor OLs or cps 78-17 Inadequate Guard Training / 10/13/78 All Holders of Qualification and Falsified and applicants Training Records for Reactor OLs 78-18 UL Fire Test 11/6/78 All Holders of Reactor OLs or cps 78-19 Manual Override (Bypass) 12/28/78 All Holders of ' of Safety Actuation Signals cps Attachment 2 Page 2 of 3

(.

   \

IE Circular No. 79-08 May 18, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Circular Subject Date Issued To No of Issue 79-01 Administration of 1/12/79 All Medical Unauthorized Byproduct Licensees except i Material to Humans Teletherapy Medical Licensees and each Radiopharmaceutical l Suppliers 79-02 Failure of 120 Volt Vital 2/16/79 All Holders of AC Power Supplies Reactor OLs and cps 79-03 Inadequate Guard Training- 2/23/79 All Holders of Qualification and Falsified and applicants Training Records for Special Nuclear Material Licenses in Safeguards Group I 79-04 Loose Locking Nut On 3/16/79 All Holders of Limitorque Valve Reactor OLs or cps Operators 79-05 Moisture Leakage In 3/20/79 All Holders of i Stranded Wire Conductors Reactor OLs or cps 79-06 Failure to Use Syringe 4/19/79 All Holders of and Battle Shields in Medical Licensees Nuclear Medicine except teletherapy licensees 79-07 Unexpected Speed Increase 5/2/79 All Holders of l of Reactor Recirculation BWR OL's or CP's i MG Set Resulted in Reactor Power Increase 1 l l Attachment 2 l Page 3 of 3 4 l

T

                                                         .;__0E _~ COPY UG 8 1979               CENTRAL Fll.ES Docket No. 70-01489 Goodyear Aerospace Corporation ATTN:   Mr. J. C. Feldscher Manager, Business Planning Akron, OH 44315 Gentlemen:

The enclosed IE Circular 79-15, is forwarded to you for information. If there are any questions related to your understanding of the suggested actions, please notify NIOSH at the telephone No. listed in the enclosure to the Circular. Sincerely, James G. Keppler Director

Enclosures:

1. IE Circular No. 79-15
2. Listing of IE Circulars Issued in the Last Six Months cc w/encls-Central Files PDR NSIC RI RIII
       .A)          drnJL Davis /gc         Keppler 8/7/79              /
               ~]4090684;ff                                                 f
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i y ' UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMEhT WASHINGTON, D.C. 20555 August 8, 1979 IE Circular No. 79-15 BURSTING OF HIGH PRESSURE HOSE AND MALFUNCTION OF RELIEF VALVE AND "O"-RING IN CERTAIN SELF-CONTAINED BREATHING APPARATUS Description of Circumstances: The Nuclear Regulatory Commission (NRC) has been informed by mailgram (copy cnclosed) from the National Institute of Occupational Safety and Health (NIOSH) of occurrences of bursting of the high-pressure hose assembly, and malfunction of the relief valve and of the "0"-Ring in the main line assembly of the SurvivAir Mark I self-contained breathing apparatus. Anyone of these failures would result in immediate loss of air supply to a user. Licensees who use the SurvivAir Mark I SCBA should:

1. Discontinue use of the apparatus until the units have been inspected by the manufacturer and all necessary repairs or replacements have been made.
2. Contact the manufacturer or supplier of the equipment for instructions on arranging for inspection and repair.

No written response to this circular is required. If you require additional information regarding this subject, please contact the office specified in the enclosed mailgram.

Enclosure:

Mailgram

\ d IE Circular No. 79-15 Enclosure August 8, 1979 Page 1 of 2

 '.                         LISTING OF IE CIRCULARS ISSUED IN LAST SIX MONTHS Circular     Subject                            Date of   Issued to No.                                             Issue 79-03        Inadequate Guard Training-         2/23/79   All Holders of Qualification and Falsified                  and applicants Training Records                              for Special Nuclear Material Licenses in Safeguards Group I 79-04       Loose Locking Nut on                3/16/79   All Holders of Limitorque Valve                              Reactor OLs or cps Operators 79-05       Moisture Leakage In                 3/20/79   All Holders of Stranded Wire Conductors                     Reactor OLs or cps 79-06       Failure to Use Syringe              4/19/79   All Holders of and Battle Shields in                         Medical Licensees Nuclear Medicine                              axcept teletherapy licensees 79-07       Unexpected Speed Increase           5/2/79    All Holders of of Reactor Recirculation                      BWR OL's or CP's MG Set Resalted in Reactor Power Increase 79-08       Attempted Extortion ' Low           5/18/79   All Fuel Facilities Enriched Uranium                              Licensed by NRC 79-09       Occurrences of Split or             6/22/79   All Materials Punctured Regulator Diaphragms                Priority I, Fuel In Certain Self Contained                    Cycle and Operating Breathing Apparatus                           Reactor Licensees 79-10       Pipefittings Manufactured           6/26/79   All Power Reactor from Unacceptable Material                   Licensees with a CP and/or OL 79-11       Design / Construction               6/27/79   All Applicants Interface Problem                            for, and Holders of Power Reactor cps

I . . sj 4 IE Circular No. 79-15 Enclosure August 8, 1979 Page 2 of 2 s l LISTING OF IE CIRCULARS ISSUED IN l LAST SIX MONTHS 1 Circular Subject Date of Issued to f Issued l No, 79-12 Potential Disel Generator 6/28/79 All Power Reactors Turbocharger Problem Operating Facilities l ' and all Utilities having a CP f l 79-13 Replacement of Diesel 7/10/79 All Power Reactor Fire Pump Starting Operating Facilities Contactors and all Utilities having a CP 79-14 Unauthorized Proe.trement and 7/13/79 All Medical Licensees l Distribution of IE-133 except Teletheraphy i Medical Licensees and to all Radiopharmaceu-tical Suppliers l l l i

    -                             ;                                 u 5  .

'y MAILGRAM RESPIRATOR USERS WARNING The National Institute for Occupational Safety and Health (NIOSH) advises workers to discontinue using the SurvivAir Mark I self-contained breathing apparatus until the units have been inspected by the manufacturer and all necessary repairs or replacements have been unde. NIOSH has leerned that the high pressure hose assembly installed by the manufacturer in some of these respirators is not the assembly originally tested and approved by NIOSH for this respirator. In addition, reports from two fire departments indicate the following serious malfunctions have occurred recently during use:

1. Bursting of the high pressure hose assembly (part no.

960627). Malfunction of the relief valve (part no. 912520).

3. Malfunction of the 0-ring in the main line assembly (part no. 824193).

Any one of these failures would result in imediate loss of air supply to the user. In response to a NIOSH request, SurvivAir has agreed to discontinue sale and distribution of the respirators until all three problems are - corrected. When NIOSH has determined that the three problems have been corrected, you will be advised that the stop sales request has been withi drawn page 1 of 2

                                                                                       ~
                   ^
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                               .                         ,       {}

I-MAILGRAM SurvivAir has also agreed to inspec't all units ,in the field and make necessary repairs in accordance with a plan to be approved by NIOSH. In the meantime, owners of SurvivAir Mark I self-contained breathing apparatus should contact the manufacturer or supplier for further instructions. For further information contact NIOSH, Division of Safety Research. 944 Chestnut Ridge Road. Morgantown, West Virgina 26505. Telephone: (304)599-7595 I i l l page 2 of 2

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                                       ,     .1/

Docket No. 70-1489 Goodyear Aerospace Corporation 1 ATTN: Mr. J. C. Feldscher l Manager, Business Planning Akron, OH 44315 Gentlemen: l This Information Notice is provided to inform licensees of a possible signif-j icant matter. It is expected that recipients will consider dissemination of I the information to all persons working at their licensed facilities. No specific action or response is requested at this time. If further NRC evalu-ations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions. If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office. 1 Sincerely, l James G. Keppler Director I

Enclosure:

IE Information Notice No. 79-12A cc w/ enc 1: Cerrtral Files PDR NSIC RIII RIII Davis /bk feppler 11/8/79

           ,7 !///2E# 09S~f                                                       g Ak

SSINS No.: 6300 United States Accession No.: Nuclear Regulatory Commission 7910250490 Office of Inspection and Enforcement Washington, D.C. 20555 November 9, 1979 IE Information Notice No. 79-12A ATTEMPTED DAMAGE TO NEW FUEL ASSEMBLIES This notice provides supplemental information concerning the identification and conviction of the persons respon;;ble for the introduction of a possibly damaging substance to the new fuel stored at the Virginia Electric and Power Company's Surry Power Station in Surry County, Virginia. Investigation of this incident by the FBI culminated in the surrender of William E. Kuykendall and James A. Merrill, Jr. , both VEPC0 employees at that time, to Surry County authorities on June 19, 1979. A Grand jury hearing was held in Surry, Virginia or, July 24, 1979. The certified charges of breaking and entering with intent to damage electrical facilities (felony), and willful destruction of utility company equipment (felony) were returned on a true bill for trial. An earlier charge for willful damage (mis-demeanor) which had not been certified to the grand jury was reapplied, certified and returned on a true bill for trial. Two additional charges against both men were introduced for conspiracy regarding the two felonies and returned on a true bill for a total of four felonies and one misdemeanor against each man. Trial commenced on October 10, 1979 in the Circuit Court, Surry County, Virginia. ' The presiding judge ruled that the prosecution failed to supply sufficient evidence to support the charges of conspiracy, breaking and entering, and damage to pro-perty as a misdemeanor. The primary reason for dropping the charges was that the subjects had been authorized unescorted access to Vital Areas by VEPCO. On October 17, 1979, the jury returned a verdict of guilty (both Kuykendall and Merrill) for violation of Virginia Code 18.2-162 (Intentional damage to a facility which furnishes electric service to the public) and set punishment as two (2) years in the State Penitentiary for both subjects, the minimum sentence provided by law. This Information Notice is provided to inform licensees of a possibly significant matter. It is expected that recipients will consider dissemination of the information to all persons working at their licensed facilities. If you have questions'regarding this matter, please contact the Director of the appropriate NRC Regional Office. No written response to this Information Notice is required.

Enclosure:

Recently Issued IE Information Notices 1

IE Information Notice No. 79-12A Enclosure Novel..ber 9, 1979 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No. Issued 79-26 Breach of Containment 11/5/79 All power reactor facilities Integrity holding OLs and cps 79-25 Reactor Trips At Turkey 10/1/79 All power facilities with  ; Point Unit 3 And 4 an OL or a CP l 1 79-24 Overpressurization Of 9/28/79 All power reactor facilities Containment Of A PWR Plant with a CP After A Main Stream Line Break 79-23 Emergency' Diesel Generator 9/25/79 All power reactor Lube Oil Coolers facilities holding OLs ) and cps i 79-22 Qualification of Control 9/14/79 All power reactor Systems facilities with j operating licenses and construction permits. 79-21 Transportation and Commercial 9/7/79 All power and research Burial of Radioactive Material reactors with' 0L's 79-20 NRC Enforcement Policy 8/10/79 All Holders of Reactor ~ NRC Lice'nsed Individuals OLs and cps and Production Licensees with Licensed Operators 79-19 Pipe Cracks In Stagnant 7/17/79 All Holders of Reactor Botated Water Systems At OLs and cps PWR Plants 79-18 Skylab Reentry 7/5/79 All Holders of Reactor OLs 79-17 Source Holder Assembly Damage 6.20/79 All Holders of Reactor From Misfit Between Assembly OLs and cps and Reactor Upper Grid Plate 79-16 Nuclear Incidnet at Three 6/22/79 All Research Reactors Mile Island and Test Reactors with OLs

9. .

4 Y

    ,                                                               YELLOW Fli.E C fyty   6 10R()'

Docket No. 79-01489 Goodyear Aerospace Corporation ATTN: Mr. J. C. Feldscher Manager, Business Planning Akron, OH 44315 Gentlemen: This Information Notice is provided as an early notification of a pos-sibly significant matter. It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time. If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions. If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office. Sincerely, James G. Keppler Director

Enclosure:

IE Information l Notice No. 80-18 cc w/ encl:

Central Files

! Director, NRR/DPM l Director, NRR/ DOR NSIC PDR I RIII RIII Davis /jp K er 5/5/80 J~ b)f $f ~~ ,

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UNITED STATES SSINS No. 6870 NUCLEAR REGULATORY COMMISSION Accessions No.: 0FFICE OF INSPECTION AND ENFORCEMENT 8002280673 WASHINGTON, D.C. 20555 i May 5, 1980 IE Information Notice No. 80-18 POSSIBLE WEAPONS SMUGGLING POUCH The NRC recently received information concerning a device used for smuggling that can preclude detection of weapons by security X ray machines. The device is described as a gray, metalfoil pouch measuring approximately 20" x 12" which can be folded to wallet size when not in use. When in use, X-ray images produce only a mottled picture with no indications of a solid mass such as that of a weapon or similar contraband. The same material used to construct the pouch has been used to line hollow compartments of hand-carried packages and parcels such as attache and cosmetic cases. The pouch is reported to look something like a leadlined pouch sold in the U.S. to protect film from harmful X-ray effect, except that the U.S. manufactured pouch distinctly reveals the silhouette of any solid mass content such as  ! that produced by a gun when subjected to X-ray. i l l l 1

k i IEInformationNoticeNo.80-18 Enclosure May 5, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No. Issued 80-17 Potential Hazards Associated 5/5/80 All radiography With Interchangable Parts Licenses On Radiographic Equipment 80-16 Shaft Seal Packing 4/29/80 'All power reactor Causes Binding In Main facilities in your Steam Swing Check And Region with an OL or CP I Isolation Valves  ! 80-15 Axial (Longitudinal) 4/21/80 All Light Water Reactor Oriented Cracking In Facilities holding power l Piping reactor OLs or cps 80-14 Safety Suggestions From 4/2/80 All power reactor

Employees facilities with an OL or CP l

80-13 General Electric Type SBM 4/2/80 All light water reactor , Control Switches - Defective facilities holding power L Cam Followers reactor OLs or cps l 80-12 Instrument Failure Causes 3/31/80 All holders of power Opening of PORV and Block reactor OLs and cps Valve ! 80-11 General Problems with ASCO 3/14/80 All holders of Reactor Valves in Nuclear Application OL, CP, fuel fabrica-Including Fire Protection tion and processing Systems facilities

     .80-10        Partial Loss of Non-Nuclear       3/7/80   All power reactor Instrument System Power                    facilities holding        l Supply During Operation                    OLs and cps l

80-09 Possible Occupational 3/7/80 All holders of Health Hazard Associated power reactor OLs l with Closed Cooling Systems and near term cps i 80-08 The States Company Sliding 3/7/80 All power reactor i Link Electrical Terminal facilities with an OL Block or a CP 1

4

  )                                                    Y:-- OW l:     _.:_ C0 3Y         .

j 1 i MJun 9 s *% \ Docket No. 70-01489 Goodyear Aerospace Corporation ATTN: Mr. J. C. Feldscher Manager, Business Planning { Akron, OH 44315 Gentlemen: The enclosed IE Circular No. 80-14 is forwarded to you for information. 1 If there are any questions related to your understanding of the suggested actions, please contact t s .A e 7 cyjely, p 4 n"N

                                                  \ ,A    y                              \

James G. Kep b l Director

Enclosure:

IE Circular i No. 80-14 cc w/ encl: Central Files PDR NSIC l RIII RII j

      &&                                                                                 i Davis /np        i   ler 6/24/80                                                                              l l
              #CC3/XA2X                                                           jf/)'$

, A lA l SSINS.: 6830 UNITED STATES Accession No.- i NUCLEAR REGULATORY COMMISSION 8005050074 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 June 24, 1980 IE Citcular No. 80-14 RADI0 ACTIVE CONTAMINATION OF PLANT DEMINERALIZED WATER SYSTEM AND RESULTANT INTERNAL CONTAMINATION OF PERSONNEL This circular describes an event which occurred at a nuclear power facility; however, the generic implications may be applicable to research reactors, and l fuel cycle facilities. On March 17, 1980, a licensee informed the NRC resident inspector that portions of the plant demineralized water (DW) system were found to be radioactively contaminated. A temporary hose used to add demineralized water to the spent fuel pool was the pathway for the cross-contamination. After this fuel pool makeup was completed on March 14, the temporary DW line (still connected to the DW header) was inadvertently left submerged in the fuel pool. Since the DW header pressure at the point of supply was relatively low (a DW booster pump had been secured), a siphoning action occurred, resulting in radioactive i contamination of portions of the DW header. l On March 17, 1980, while performing routine secondary system chemical analyses, thelicenseediscoveredthatthedemineralizedwatertapin_ghechemistrylab contained high levels of boron and had activity of 1.5 x 10 uCi/ml (mainly Cs-134, Cs-137, Co-58, Co-60 and Mn-54). It was subsequently discovered that demineralized water from the chemistry laboratory supply tap had been used to make five (5) pots of coffee. The remaining coffee was confiscated and the twenty-three (23) individuals who had consumed this coffee were whole-body counted. All involved individuals showed no intake greater than an equivalent 0.01 MPC-HRS. Analysis performed by the licensee's radiation consultant, based on the maximum concentration of radioactivity found in the coffee, indicated that the resultant 50 year dose commitment to an individual drinking eight ounces of this coffee would be less than 1 millirem. Further licensee investigation revealed that the non-radiological chemistry DW supply tap was the only DW supply point outside the Auxiliary Building controlled area. This DW supply tap was tagged prohibiting human consumption to prevent a similar event in the future. It is recommended that you review your facilities use of demineralized water I (DW) via temporary connections and give attention to the following:  ! I

1. Provisions should be made to assure that radioactive materials are not inadvertently introduced into your facility's DW system via the improper l use of temporary connections. A temporary cross connection between contaminated systems and the DW system without adequate physical controls to prevent cross-contamination should be prohibited.

l l

i l IE Circular No. 80-14 June 24, 1980 ' Page 2 of 2

2. In addition to some physical means of preventing backflow into the DW system, appropriate administrative controls should be established to ensure that the DW supply valve is secured and temporary hosing is disconnected from the DW supply header after use.
3. Use of plant-supplied DW for human consumption should be prohibited.

The potable water system should be the only authorized source of water for human consumption.

4. Examine potable and demineralized water systems to determine if pathways exist allowing or having the potential to allow contamination of these systems including temporary connections whereby siphons could cause situations described above.

No written response to this Circular is required. Your review of this matter to determine its applicability to your facility and any corrective and preven-tive actions taken or planned, as appropriate, will be reviewed during a subsequent NRC inspection. If you desire additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.

1

4 I i IE Circular No. 80-14 Enclosure l June 24, 1980 l RECENTLY ISSUED i 1

IE CIRCULARS l Circular Subject Date of Issued to No. Issue 80-13 Grid Strap Damage in 5/18/80 All holders of Reactor Westinghouse Fuel Assemblies OLs and cps 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of Reactor May Fall Out of Place When OLs and cps Mounted Below Horizontal Axis 1 80-11 Emergency Diesel Generator 5/13/80 All holders of a power Lube Oil Cooler Failures reactor OL or CP l 80-10 Failure to Maintain 4/29/80 All holders of Reactor OLs and cps Environmental Qualification of Equipment Problems With Plant Internal 4/28/80 All holders of a power 80-09 Communications Systems reactor OL or CP 80-08 BWR Technical Specification 4/18/80 All General Electric Inconsistency - RPS Response 8WR's holding a power Time reactor OL 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Oil System reactor OL or CP 80-06 Control and Accountability 4/14/80 Medical licensees in Systems for Implant Therapy Categories G and G1 Sources 4/1/80 All holders of a power 80-05 Emergency Diesel-Generator Lubricating 011 Addition and reactor OL or CP Onsite Supply Securing of Threaded Locking 3/14/80 All holders of a power 80-04 Devices on Safety-Related reactor OL or CP Equipment 80-03 Protection from Toxic Gas 3/6/80 All holders of a Hazards power reactor OL 80-02 Nuclear Power Plant Staff 2/1/80 All holders of Reactor Work Hours OLs, including research and test reactors, and cps

g(  ? 6 L SEP 3 01982 Goodyear Aerospace Corporation License No. SNM-1461 A'ITN: Mr. Daniel Gleghorn { l Administrator { l Corporate Industrial i Hygiene & Safety 1210 Massillion Road Akron, OH 44315 Gentlemen: This refers to the routine safety inspection conducted by Mr. W. J. Slawinski of this office on September 17, 1982, of activities authorized by NRC Special Nuclear Material License No. SNM-1461 and to the discussion of our findings with you and Mr. Fred Yoder at the conclusion of the inspection. The inspection was an examination of activities conducted under your license as they relate to radiation safety and to compliance with the Commission's rules and regulations and with the conditions of your license. The inspec-tion consisted of a selective examination of procedures and representative records, observations, independent measurements, and interviews with l personnel. During this inspection, certain of your activities appeared to be in non-compliance with NRC requirements, as specified in the enclosed Appendix. A written response is required. In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter, the enclosures, and your response to this letter will be placed in the NRC's Public Document Room. If this report contains any information that you (or your contractors) believe to be exempt from disclosure under 10 CFR 9.5(a)(4), it is necessary that you (a) notify this office by tele-phone within ten (10) days from the date of this letter of your intention to file a request for withholding; and (b) submit within twenty-five (25) days from the date of this letter a written application to this office to withhold such information. If your receipt of this letter has been delayed such that less than seven (7) days are available for your review, please notif,y this office promptly so that a new due date may be estab-lished. Consistent with Section 2.790(b)(1), any such application must be accompanied by an affidavit executed by the owner of the information which identifies the document or part sought to be withheld, and which contains a full statement of the reasons which are the bases for the l a%550/MOSl-7* kf/.$ 1

e O Goodyear Aerospace Corporation 2 SEP 3 01982 claim that the information should be withheld from public disclosure. I This section further requires the statement to address with specificity the considerations listed in 10 CFR 2.790(b)(4). The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit. If we do not hear from you in this regard within the specified periods noted above, a copy of this letter, the enclosures, and your response to this letter will be placed in the Public Document Room. The responses directed by this letter (and the accompanying Notice) are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511. We will gladly discuss any questions you have concerning this inspection. Sincerely, l 1 4 Ae D. J. Sreniawski, Chief Materials Radiation Protection Section 2

Enclosure:

Appendix, Notice of Violation f i 1 cc w/ enc 1: DMB/ Document Control Desk (RIDS) l 9.. l l l I RIII RIII Y Slawinski/np

                             /*

Sreniawski hh l l 9/g/82 ,- 1 i

Appendix NOTICE OF VIOLATION Goodyear Aerospace Corporation License No. SNM-1461 As a result of the inspection conducted on September 17, 1982, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following violation was identified: License Condition No. 14 states this license is subject to statements,  ; representations and conditions specified in the licensee's application dated March 19, 1979, as supplemented by the submission dated July 24, 1979. The above referenced application, part I, page 47, requires monthly environmental surveys to be accomplished during operation to provide assurance that applicable limits are not being exceeded at any point. l Contrary to this requirement, an environmental survey has been performed j only once since inception of this requirement. Specifically, the last such survey was performed in April 1980. This is a Severity Level IV violation (Supplement VI). Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written state-ment or explanation in reply, including for each item of noncompliance: (1) corrective action taken and the results achieved; (2) corrective action , to be taken to avoid further noncompliance; and (3) the date when full com-

 ~

pliance will be achieved. Consideration may be given to extending your response time for good cause shown. p, f~ o$O *h . D. J. Sreni'awski, Chief j Dated ' Materials Radiation Protection Section 2 [* .

Module No. 77710B TNmfRTFT AT. - ACADFMIC INSPECTION REPORT a Inspection Report No. 7e - / V89 7 2.-o , Licensee (Name and Address) 0 se k 4 e. a< herscoace ' (o r o. ' J I h *o /V\ Ass i fles a tZ ek. M (4 2 0 4 , O [o 4 'l 7/ [ Licensee

Contact:

D. E . 6le Lona csp Telephone No. lu _) 196 '//fe License No. SA/M IM l Docket No. O 70 -o IV ?? last Amendment No. A.s Rea, l F ;- - . Date of b N .* f : 972 'a N Eh/7T. !"#'8# ' not h fed. Category: E Priority: I Date of Inspection: 9 - / ~7 - i 1 Type of Inspection: (>4 Announced ( ) Initial ( ) Unannounced ( ) Special M Reinspection Summary of Findings and Action:, ( ) No Noncompliance, Clear 591 issued ( ) Action on Previous N/C ( ) Noncotcpliance, 591 issued ( ) Regional Action (>4 Noncompliance, Appendix A ( ) HQ Action Inspectort (A vw ,

                                                                                        $~ L ' A L (SfignaturV)                                         (Date Signed) t-          2275                  7- 2 Y-P 2__

Approved: (Signature) 0 (Date Signed) Revision: 10/81

Procedure No. 77710B \: . INDUSTRIAL - ACADEMIC INSPECTION REPORT As re n .) Licensee: bool4 co< A e rc 5 put- (u p. Mc. No. SMH @[ Amendment No.  ? -o - M Date of Inspection: #f ? L

1. INSPECTION HISTORY
a. Items of noncompliance or safety items noted during last inspection conducted on 3 7 'i Yes No [
b. Requirement Corrected Not Corrected I
c. If any items of noncompliance or safety items noted during the last inspection were not corrected, explain: Al 4 1

l

2. ORGANIZATION
a. Organizational structure as described in application or letter Dated Mc A l'T 3 I919 , a Sie B (ous

(:ur. )

b. List primary licensee contact: D. E. Clej lead Telephone No.: 7 % - 4( fo
c. Comment:
                % Do-iU            Gle d on o . CSP- AJ-.-.d do<, CorPase b s a.                                          bb
                                                                                                                             <y ' f 9
                                                                                                  - s g ...       s 4 bo.        90.sl.4 J

Smc$ =' C o < J.- .b c.c 0 Y Vre ck 0 tf ~

                                                           $ e s-    oE      N As     o          Et       S*A R 4 ce #* n i _

v g tv1 <. Ao dw s - p . < <.s ea II wo< k w:1L u Fr' . A l d. M 0 a ecc~ t A; Ii L4 ,s.kv.. o .. I, s ,-s _ o . .- so - ,,), , , %. m<. c t e 3 u 4', L. r u rs- . L: t .4 4< e<t u - J M. . i 1: M3

                      <-dJ.-j r s.1. p .l                    .x     4-dg a_    P ./            i        /                  .      >-

2 -- 3,

SUMMARY

OF LICENSED PROGRAM (Kind of program, number of people, rate of use or quantities on hand, places and frequency of use, type, quantity and use as orie dect bewo<le t L t. lb eds <<du dE 3 .M - cuthorized). Rs D e. n r .' YL ~ ~ .d . ce A r ;-(~ 3 e. eg. , p ,u + -fv v c a - . a ~. b- doe a .5 u Ft ,- 9 v ,, 4 f , , , ,f Ll r a - -~ Ret e i a,# u r - s ) {v e. asod9 't-Q -S~ rev 2te to lh ( s"A e fI o Ac<> ) .Preceda<as

                                                        ,                                                         ,)

m ahe e,0l Ar ke a .) shek h Yk C e Nr. 4vse s v (e.-4 a fuled . rka reder.ll es e ~,Iked ju ,, y +L flow flu.,3L 9 o

                                                                                                       $<m           .s o n lr - ,
               -h k       Ce Wek use s                   o->]er     kek.           bUssb r u'

a - I 3s.s , d c s k- o n. d<el er-pra.d. eat- . o c a. p ac.k e y) a) e v 5 {stensed wa de </< s p os t. [ aVSe - <' f . k e t.c v e<&

                -b c . s[e < < < d u Fu        is     t e.+u e a * .i     +e     't   k suprisir~

Yes No Category and priority of this license is appropriate: If No" state new Category Priority . J. . INTERNAL AUDITS OR INSPECTIONS Required by L/C or application: Yes No If "Yes": c.

1) By whom D. O le 1 bu j b N2W l
y Announced
Unannounced:
2) Frequency b => 4 < !
3) Scope c <.o rd s re s.c u b clc h em o s <. /h open we an ai c. c t es.] o m 'e w: {l f/C e e u Sf E L .1
                                                                                                                '        ~

No f 4) Records maintained: Yes l No l

5) Records reviewed: Yes
6) Period Reviewed:
b. Comument (responsibility of auditor or connaittee, management control):

42/76

1

5. TRAINING RETRAINING AND INSTRUCTION TO WORKERS, .

Training program specified in L/C or application: Yes No c. b. If training program is required, describe scope of program: Y r,,Ive/wi

                         <. 4,-e11         La -d le         u6 .          e s ,, ,         o ., . r (c -y
         ~

(+rdu) y k/ /Vle. a ee. Ou e . - 3 sppr e bs t-m e r,hs 4 s ve n b 1 s v J s h yv elib Of r lcl Jacl- h s L.e >. hJs u w kr a el v .A s r 'd supuva - g,

c. Retraining required: Yes No [

If "Yes" is retrainging: Complete Incomplete 1 l

1) Are tests and/or examinations required: Yes No No
2) If "Yes" are records available: Yes Reviewed test results: Yes No 3)
4) Period reviewed:
5) Comment (per cent completed, test results, etc.):

Training provided, but not covered above: krof ra- / / << E < [ / fir . f d. Gle 9 l, eas ru ps sll,lt. he h as-.-g e -f o,,,.,-e{

                  ~       '                                              u r., salved              su      +h        a n. sh         ra slu sk e           mlfr.

l l

o. Instructions to workers in accord with 10CI'R 19.12: Yes t / No 12/76
  *                                                         '.fi   RAUlt't. Lit:lt'M. l'ROl'EClit*N l'MOCEl't'EE,5
m. eer se el sHe *H4 W8*. sob *F PlHs-#44Fsai No
1) Required by L/C or application: Yes No .
2) Provided, but not required by L/C or application: Yes
3) Procedures reviewed: Yes / No
4) Appeared Adequate: Yes No
5) Comments (personnel's understanding of procedures): / eno et [

9p ,- le ' k..awic k" n Ale. u  ! l l 1 - l l i l l

b. Changes in procedures since last inspection: Yes No /

l'

1) Were changes authorized: Yes No
2) Comments:

1 1

7. INSTRIMENTATION
a. Type (s) of radiation survey instruments on hand as per L/C, .moolication or equivalent: Yes No i
1) If "No" list changes:

l 1 l 12/76

 =
b. Capability of radiation survey instruments adequate for program:

Yes No

c. Calibration of instruments required: Yes / No
d. If "Yes" instruments calibrated in accord with requirements:

Yes / No

       .. Co ent:        C o // h d <,/        ,.      ~d .-m              m.4 4     / , , , _ , ,. ,     , ,,; /, ,

(p a n + + ) . T1n su/IV on a Oc.~ fed 4 la ssi clu r i *I ' y g s i a f o .< S c, . s oaen oN s , [ llyheY<d a n en.d Eb e.- e sNr V () U 1 B. MATERIALS

o. Radioactive material secured to prevent unauthorised removal from:

l 1) Restricted area: Yes No

2) Unrestricted area (20.207): Yes A/!A No
b. Method of control appears adequate: Yes [ No
c. Comment: Sec - 64 1 S ia ds po /de [ul /;' df d ow l ar< e$

V U l I

9. FACILITIES
c. Facilities described in letter or application: Yes No [ * ' ' ' ' '
                                                                                                                        ,,A
b. Facilities inspected: Yes # No
c. Co ent: %d 4 a /, // , L /, y ce44se c m 2, y . -
                    , s A p , <. lab       ca d       us >lc       s /n o r,-    e, v e a    .

o 12/76

3, POSTINC AND LABELING

a. Posting and labeling in accord with 10CFR 20.203: Yes _No
b. Conment:

l l

l. RECEIPT AND TRANSTER OF MATERIAL
c. Procedures for picking up and receiving packages (10CTR 20.205 (b)(c)):

Yes / No

1) Incoming shipments monitored: Yes [ No
2) Records of monitoring maintained (10CFR 20.401(b)): Yes No [

s ~neet.

3) Records reviewed by NRC inspector: Yes No
4) Period reviewed:

L. Procedures for opening packages (10C11 20.205(d)): Yes [ No

c. Comment: Set e ~s Area De<wnes{ mh& Alescrs.

LJu w/0 u tta. (wr e,,-.-) e an..A Nk l SO A i 12/76 l

                                        -  7-
d. Records of receipt and transfer of material available (30.51(a); 40.61(a);

70.51(b)(1)): Yes No

1) If "Yes" review of records was made by inspector: Yes No
2) Period Reviewed: b /ffo - / hor I __
3) Comments:

1

c. Packages on hand meet labelling requirements (49CTR 173.399):

Yes No 4[A

                                             /

Comments:

f. Reports to commission required by L/C or regulation submitted:

Yes No Comments: &l$l ~ ~l Yl r &cbcn Y h c uis a *N feps IJ Su miOd 4 ogol. -

22. PERSONNEL RADIATION PROTECTION - EXTERNAL
c. Film or *n.D badge supplier A - b P9 D " /'/'I' E
b. Badge exchange frequency
c. Reports reviewed by
o. Records reviewed for period to by NRC inspector
f. MRC forms or equivalent
1) NRG-4 (20.102(b)): Yes No Complete: Yes No
2) NRC-5 (20.401(a)): Yes No Complete: Yes No Maximum whole body quarterly exposure:

Maximum externity quarterly exposure: g og g q g l

3) Comment:

Focket dosimeters used: Yes No 3

1) Type used:
2) Frequency of recharging:
3) Frequency of reading:
4) Consnent:
h. Direct radiation surveys of restricted and/or unrestricted areas being e.ade:

Yes / No

1) Records of surveys being maintained: Yes / No l
2) Records of surveys reviewed: Yes / No
3) Period reviewed: 1477- t9fL 9e-e.cI y aclu a bo k
4) Comments: C < c .o .. . ( 5% ;t se f.1 -{o a5sc>s V

suaLa e e du n ,- a bu . La kg <c J .-al v blo s pe s.; $ <. kyus-sq o< a rea s rey u, s V i y l

33. PERSONNEL RADI ATION PROTECTION - INTERNAL
o. Potential for exposure of individuals to airborne radioactive materials exists: Yes No If "Yes" does program for monitoring and control exist: Yes No 1)

No 2') Program for monitoring and control appears adequate: Yes

b. Comments: b 'h Ci w Eamp he V2 e mp lo4cl buo (vJ Cs ben ace!!f
a. .n u - s a . .. ~ . a . . ,.

aopinable Icah . 12/76

c. Respiratory protection program required by L/C or application:

e rn e < uit. Yes No / A v e.i l c Q t -iQ> r e-sf

                                                //n([-      a t <.        Ye. s ps e<         ,
1) If "Yes" were respiratory protection procedures reviewed:

Yes No

2) Respiratory protection procedures appear adequate: Yes No
3) Consments:
d. Bionssay program required: Yes [ No
1) If "Yes" was bionssay program reviewed: Yes No
2) Bioassay program appear adequate: Yes No
3) Comments: ()<s-a./4sr.1 r> < do # ~ cd a --sally e ., a n dav a cl- . ls J '
                                                                                    /

wLe L o Jie u A. J,;,J /v a ~.t c. - .i o/4,

                                                                                                  ,-.Li al s

wie m) here e d orus u s, U i idt% . l V fo , -) ash a fa c u b4[] .s a n r> le s t- l 9 'l l (o ve<)

e. Smears and air samples l 1) Monitoring for airborne radioactivity is conducted (20.103):

Yes No

a. Records of monitoring reviewed: Yes No
b. Period reviewed: 3 [71 - F/92_
c. Records of monitoring appears adequate: Yes No
2) Smear surveys being conducted (20.201, b): Yes No
a. Records of smear surveys reviewed: Yes No
b. Period reviewed: / f/4 - kresed
c. Records appeared adequate: Yes / No
3) Comments: b .5 ^ " 4 P ' < do ' ~ 'd o cc 4 5 e a a = /// <m aa a eau . Pe< 4.. ~ a a 4- d,, e<L & n.

Yociv. 12/76

l m

14. LEAK TESTS
c. Leak tests required: Yes No
b. If "Yes" lesk teste conducted: Yes No
c. Records of leak tests maintained: Yes No
d. Imak teste records reviewed: Yes No
o. Period reviewed:
f. Records of leak tests appear adequate: Yes No
g. Comments:
15. RADIOACTIVE EFTLUENT CONTR01. AND WASTE DISPOSAL p s) 0
c. Byproduct material released to_ atmosphere and/orj fwer (20.106 and 20.303):

Yes No IC#

b. Records of releases or radioactive effluents maintained (20.401):

Yes / No

1) Period reviewed: / 9 '? 4 - /r<" I
2) Records appear adequate: Yes / No
   ,% c . Solid /wa[te disposal method:                        TO          % /cc//* c                     1 obP'-'
1) Records of disposal maintained (30.51): Yes / No
2) Surveys of waste prior to disposal made (20.201): Yes / No
3) Period reviewed: Ox e. cf.sp a-[ /w a / e- .- l977
4) Records of surveys appear adequate (20.401): Yes t/' No d d. Comments: Al o - <- Se"c //77 Liem.;f w . rls r> lm d ik e l> s o 4 . . + m do ,2 I
               ,-! u b a,-ch                        1 - va l< U             u       7T(cJ,-e                  cd     sLnd ac            s.l;d             w.h Res k.(                       aF s           a            cold             be"rPd             'A      N 12/76 sn               yI< d.n           t, a             reb ~a                     6        o M L.

l

16. SHIPPING INCIDENTS -

a t,,

s. Have any shipping incidents occurred since 0$s(j) /l/o
1) Was incident documented: Yes No

! 2) If "Yes" documentation appears adequate: Yes No

b. Comments (reports to DOT, etc.):

l l I 17 NOTIFICATIONS AND REPORTS

a. Licensee in compliance with 10CFR 19.13 (reports to individuals):

Yes L/ No

b. Licensee in compliance with 10CFR 20.405 (over exposures)

Yes v' No

c. Licensee in compliance with 10CFR 20.403 (incidentw):

Yes ' No i d. Licensee in compliance with 10CFR 20.402 (theft or loss): Yes / No

e. Comments:

l l 12/76

6

18. POSTING OF NOTICES Yes No
o. Licensee in compliance with 10CTR 19.11(a) or (b):
                                                                                    /          No
b. Licensee in compliance with 10CFR 19.11(c): Yes
c. Comments:
19. ENVIRONMENTAL !ONITORING PROGRAM Yes No
c. Environmental Monitoring Program required:

No. If "Yes" records reviewed: Yes b.

c. Period reviewed: NPA [ /Nd Ee 1 v 8 d " t  ! N /t<='f -

No

d. Records appeared adequate: Yes

[4 . If Environmental Program is not required, briefly describe any J g eyeh c r c. refu,-v/ existing program: 6avvea me dc /

                                                                                                        .s pe < s kY.

mosY Y , Speu'Si. c. < s .:e s f {oca bosu s oso f

                                                                         .5 - ve f        b cs       be e n 6 pJi4    o ,1 e     E'n w cw e h {

km -,l s i s e e. t m e op ka b.i Y.s rer u ov-c s e b pa U

                      >A     feht         [ T19 .
20. CONTIRMAWRY MEASUREMENTS Yes No
a. Independent measurements made by inspector:
b. Comments (describe type, results, comparison,as'. with gicensee results):

a n ,l,r11le Lm - .e s u even l n<-c.r , ' _' , MidC 0^J

                                                                      \ C S C ** LE    _f   '-       (0 *'\

(0 sC li d Y$ $ 4 /%- h a nd . 12/76

INDEPENDENT INSPECTION EFFORT l l1.

o. Comment on type of independent' inspection effort conducted:

Swc l e m AT'rk'NW s cEl/$/, ch,La i - ~.. .- Alai..,- 4aL,- re m Lv d. 9 I

12. CONTINUATION TROM PREVIOUS PARAGRAPHS - USE BACK OF PAGE IF NECESSARY l

1 l I l l l. t l l 1 f

                                                                                         \

12/76

    ...                                                              7 W //h e o

GOODYEAR AEROSPACE fq - I f COR PO R ATION a nmow, owso as sis October 29, 1982 D. J. Streniawski, Chief Materials Radiation Protection ' Section 2 United States Nuclear Regulatory Commission l Region III { 799 Roosevelt Road Glen Ellyn, Illinois 60137 {

Subject:

Notice of Violation License No SNM-1461 Dated September 30, 1982

Dear Sir:

f i Pursuant to the provisions of 10CFR2.201 we submit the following: 1.0 Air Effluent 1.1 Per Goodyear Aerospace's license application Part 1, Page 43, " Air discharges are limited to inside the l large hanger, in which this facility is located where monitoring is readily done". The above monitoring has been carried on for a considerable length of time. The attached records, (see Attachment I) since the inspection of March 22, 1979, are attached for your review. Sampler #4 (see Attachment 2A) is the sampler inside the hanger. On August 9, 1982 this sampler was moved to sample at the exit of the exhaust stack from the lab hood in the component preparation and assembly area. The hood is located where the cleaning of con-taminated components is performed and where the greatest contaminate could be expected. 1.2 We believe we have complied with the terms of our appli-cation as stated above in Part I, Page 43 and the samples which are forty (40) hours long have shown no significant levels of alpha-radiation. We have taken four (4) air samples, one at each compass point as shown on Attach-ment 2B. The results are attached for your review. 1.3 Air samples will'be taken monthly at the four compass points per Attachment 2B and a record kept of the findings. ' EDY hM \ g 1 /,> D 1,7h 3 > W,

D. J. Streniawski, Chief Notice of Violation License No SNM-1461 Dated September 30, 1982 October 29, 1982 Page 2 1.4 Initial compliance was accomplished on October 28, 1 1982 and air monitoring as indicated will continue monthly whenever the licensed facility is in operation and running. (Note: Periodically the licensed facility is shut down due to the lack of contract work). 2.0 Water Effluent (see Attachment 2B) 2.1 There are two sources of water effluent from this facility: 2.1.1 Discharge from the Imhof Septic System which treats sanitary waste. 2.1.2 Discharge from French drain which handles rain water run-off'from the hanger roof and sump water from the facility. Effluent samples were taken from the above locations on October 26, 1982 and shipped to Murry Bolton, Cambridge, MA., 02139 on October 27, 1982. These samples will be analyzed for mass of material and gross alpha. The results will be forwarded to you upon their receipt by CAC. u A program has been established to continue the eff1"ent 2.2 monitoring on a monthly basis whenever the licensed facility is in operation and running and a record of these findings will be kept. 3.0 Attachment I Index 1A. Air Monitor Procedure, Alpha Radiation 1B. Air Monitor Procedure Alpha Radiation - continued IC. Air Monitoring (Radiation Protection Guide) Permissible Limits 1D. Air Monitor Data, Alpha Radiation (Instrumentation and Location) 1E. Unrestricted Area Air Monitoring Data, Alpha Radiation (Instrumentation:and Location) 1F. Alpha Radiation Monitoring Log Sheets (2-26-79 thru thru 10-11-82) IN.

1

 ,                                                                          i D. J. Streniawski, Chief                                               i I

Notice of Violation License No SNM-1461 Dated September 30, 1982 October 29, 1982 Page 2 i 1

10. Unrestricted Area Alpha Radiation Monitoring Results l of 10-27-82 Samples
                                                                            )

4.2 Attachment 2 Index I l l 2A. Restricted Area Air Monitor Locations 2B. Unrestricted Area Air and Water Effluent Monitoring Locations Very truly yours, l GOODYEAR AEROSPACE CORPORATION

                                              & 5N Daniel E. Gleg orn, CSP Administrator Corporate Industrial            j l                                            Hygiene and Safety 1

s Attachments i l l l l l l 1

r ATTACMENT 1 f 1 l 1 Parts of Air Monitoring Manual with Sample results from 2-26-79 thru 10-11-82 3 1 i I l I m 4

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BYPRODUCT MATERIAL LICENSE INFORMATION UPDATE FORM Licensee: h00DYEAe AenOsence_ Coe. r i 4 # 315

       ~

Location: A K RON. OHIO

(City) (State) (zip)

License No.: SNM-146l Docket No.: 0700/#B9 INFORMATION TO BE UPDATED (CIRCLE APPROPRIATE NUMBER (S)) Category and/or priority: From AE To Ed l Last inspection date: From W O e/ 7 8 To 0579 Next inspection date: From 04/79 To 0382

4. Priority program code: From To l
5. Other: (specify)

Reason for update (narrative description of reason for update, such as appropriate Manual Chapter reference, licensee representative contact including date and method l of contact, or other reason for update): l 4/ mL A sWEA C a4AtA L2 uMk ,aw lb ~L~l a aA+.-.si kwu Jn,Jalb a MJ nv9. &~ JJ.c. c, LL h mA. hafa,r flm W,L.F.uL <bk) 4/30/79 nj$nsl1Y .

               'f Section Chief Approval:                        ([Lh G (Initials)

Update placed on license (if appropriate) by: (Initials) Updateenteredonsection'sIBMmasterlistingofregionallicensesby:b6* (Initials) Inspector: C. N Section Chief Chrb

                                                                                           ' ' (Date)
                              ~

(Date) U () l Original to license file cc: MRPS Chief Information Coordinator

      -                                                                                                                    4
 +

NOV 0 3 M g%

              .                                                                                                   P        \

Goodyear Aerospace Corporation License No. SNM-1461 AITN: Mr. Daniel E. Gleghorn, CSP Administrator Corporate Industrial Hygiene & Safety 1210 Massillion Road Akron, Ohio 44315 Gentlemen: Thank you for your letter dated October 29, 1982, informing us of the steps you have taken to correct the noncompliance which we brought to your attention in our letter dated September 30, 1982. Your application Part I, page 47, nor our Notice of Violation dated ( September 30, 1982, specified the methods forming monthly l I environmental surveys. We agree.. impati ges are limited to insidethehangerandtp 1( 4 the air affluent levels in thi dihA a ive actions for water j g', j effi (ff

                                                                     -      eramine these matters during a future          c Your e      eration with us is appreciat64.
                                                                       . Sincerely.

D. J. Sreniawski, Chief Materiafs Radiation Protection Section 2 l l cc w/1tr dtd 10/29/82 1 DMB/ Document Control Desk (RIDS) l

            .8211080225 821103-DR ADOCK 07001                                                         f { h.h. g y                 -                                         DMD IL-o?

omct > 3MT..D: .W . KILL . h. . - - - - - - sumaar > ,slayin'skUcv. . . Sreniawski. . . . .. - - - - - - - oan > 11/3/82 ~ M fp ,, ,, , , ,, l wac conu ais no soi sacu o24o OFFICI AL RECORD COPY g l

s>.s- ,

 \'   ,

s , GOODYEAR AEROSPACE COR PO R ATION a n noN OHl0 4 4 3 0 5 October 29, 1982 I D. J. Streniawski, Chief Materials Radiation Protection Section 2 United States Nuclear Regulatory Commission  ; i Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Not1:e of Violation License No SNM-1461 Dated September 30, 1982

Dear Sir:

l Pursuant to the provisions of 10CFR2.201 we submit the following: 1.0 Air Effluent 1.1 Per Goodyear Aerospace's license application Part I, Page 43, " Air discharges are limited to inside the large hanger, in which this facility is located where monitoring is readily done". The above monitoring has been carried on for a considerable length of time. The attached records, (see Attachment I) since the inspection of March 22, 1979, are attached for your review. Sampler #4 (see Attachment 2A) is the sampler inside the hanger. On August 9, 1982 this sampler was moved to sample at the exit of the exhaust stack from the lab hood in the component preparation and assembly area. The hood is located where the cleaning of con-taminated components is performed and where the greatest contaminate could be expected.

                          ,1,2   We believe we have complied with the terms of our appli-cation as stated above in Part I, Page 43 and the samples which are forty (40) hours long have shown no significant levels of alpha-radiation. We have taken four (4) air S            samples, one at each compass point as shown on Attach-ment 2B. The results are attached for your review.
                         ' l.3    Air samples ylli be taken monthly at the four compass points per Attachment 2B and a record kept of the findings.
                       ~
     "8211d80227 821103                                       ghlM PDR ADOCK 07001489 C                 PDR                                                      15HQ4A    "

DM6 16-07

l .

                                                                                     \

1 D. J. Streniawski, Chief 1 Notice of Violation License No SNM-1461 Dated September 30, 1982 j October 29, 1982 l l Page 2 l l 1.4 Initial compliance was accomplished on October 28, l l 1982 and air monitoring as indicated will continue l l l monthly whenever the licensed facility is in operation  ! and running. (Note: Periodically the licensed facility j is shut down due to the lack of contract work). { l 2.0 Water Effluent (see Attachment 2B) ! 2.1 There are two sources of water effluent from this I facility: 2.1.1 Discharge from the Imhof Septic Svstem which treats sanitary waste. l 2.1.2 Discharge from French drain which handles rain water run-off from the hanger roof and sump j water from the facility. Effluent samples were taken from the above locations on October 26, 1982 and shipped to Murry Bolton, Cambridge, MA., 02139 on October 27, 1982. These samples will be analyzed for mass of material and gross alpha. The results will be forwarded to you upon their receipt by GAC. 2.2 A program nas been established to continue the effluent monitoring on a monthly basis whenever the licensed facility is in operation and running and a record of these findings will be kept. 3.0 Attachment I Index 1A. Air Monitor Procedure, Alpha Radiation 1B. Air Monitor Procedure, Alpha Radiation - continued IC. Air Monitoring (Radiation Protection Guide) Permissible Limits 1D. Air Monitor Data Alpha Radiation (Instrumentation a:u Location) lE. Unrestricted Area Air Monitoring Data, Alpha Radiation ' (Inutrumentation and Location) IF. Alpha Radiation Monitoring Log Sheets (2-26-79 thru thru 10-11-82) IN. 1 l

D. J. Streniawski, Chief Notice of Violation License No SNM-1461 Dated September 30, 1982 October 29, 1982 Page 2

10. Unrestricted Area Alpha Radiation Monitoring Results of 10-27-82 Samples 4.2 Attachment 2 Index 2A. Restricted Area Air Monitor Locations 2B. Unrestricted Area Air and Water Effluent Monitoring Locations Very truly yours, GOODYEAR AEROSPACE CORPORATION U

Daniel E. Gleg orn, CSP Administrator Corporate Industrial Hygiene and Safety a Attachments

t i o 0 l l l ATTACHMENT 1 Parts of Air Monitoring Manual with Sample results from 2-26-79 thru 10-11-82 1 i l 1 i l l l l l l 0 4

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o Air Monitoring (Radiation Protection Guide) Section 3.1 Surveys, contamination released to the environment shall not exceed:

                                                   ~

3.1.1' Air - 2 x 10 p ci/mi Uranium -235

                                           ~                        0 2 x 10     p ci/ml (2.22 x 10 CPM     /p ci)
                                   = 4.44 x 10  -5 CPM /mi = 4.44 x 10" CPM /1 3.1.2      Water - 3 x 10 -5 pei/ml Uranium - 235                        ,

3 x 10 -5 pei/ml (2.22 x 10 CPM /p ci) 6

             '                                  1
                                   = 6.66 x 10 CPM /ml Section 3.2    Personnel Exposure Control a)         maximum concentration in air, based on a 40
                                                                          -10 hour week shall not exceed 1 x 10              ci/ml Uranium -235.
                                           -10 ci/ml (2.22 x 10 CPM 0
                                                                          / p ci)

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                                   = 2.22 x 10       CPM /ml                                       )

b) Average daily concentration for airborne

                                                                        ~11 exposure shall not exceed 1 x 10            p ci/ml Uranium -235 1 x 10" I p ci/ml (2.22 x 10 6CPM / p ci) =

2.22 x 10-5 CPM /ml Section 3.3 Contamination Control Zone, a contamination control zone shall be established when airborne contamination exceeds

                                 -12 y ci/ml Uranium -235 2 x 10
                                 ~                           6                        -6 2 x 10        p ci/ml (2.22 x 10 CPM / p ci)= 4.44 x 10          CPM /ml The inhalation of radioactive materials represented by far the most important source of possible exposure.

Where the probability of air contamination exists and the concentration of airborne materials exceeds the specified limits, a contamination control zone will be l established and protective respiratory equipment will be used. 1 0 1C

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                                                                        -12 A-1            East Point             762 liters      1.7x10     uci/ml A-2            North Point            Void            N.D.
                                                                         -12 A-3           ,West Point             744 liters      1.1x 10     uci/mi A-4             South Point           747 liters      1.1x10" uci/ml
                                                                        -12 A-5             North Point           726 liters      1.2x10     uci/ml Weather Conditions:

I Sky - Sunny Temperature - High of 64*F Wind - C knots 0 200' SW 0 10

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