ML20134E947
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UNITED STATES dM.
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101 MARIETTA STREET.N.W.
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ATLANTA, GEORGI A 30323 2
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gl 251992
. Allen L. Mosbaugh T
Dear Mr. Mosbaugh:
RII-92-A-0072 - QUESTIONABLE ALARA PRACTICES
SUBJECT:
- 1991, This refers to your letter which we received on October 17, in which you expressed a concern related to ALARA practices at the Vogtle Nuclear Plant.
Our inspection regarding this matter has been completed, and our findings are documented in the enclosed allegation summary and l
Based on the information provided, we were inspection report.
able to partially substantiate the allegation.
We This concludes the staff's activities regarding this matter.
appreciate your cooperation and assistance.
Sincerely, s
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org R. Je s, Director Enforcement d Investigation Coordina on Staff
Enclosures:
1.
Allegation Summary 2.
Inspection Report Nos. 50-424 and 425/90-09 3.
Inspection Report Nos. 50-424 and 425/90-22 4.
Inspection Report Nos. 50-424 s
and 425/91-11 i
5.
Inspection Report Nos. 50-424 and 425/92-16 Information in this record was deleted in :ccordance with the freedom of Information 6
Act, exemptions F0IA-9(-1//
i Certified Mail No.
P 258 014 603
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NOV 2 51992 4
With regard to Examples B and C, IR No. 90-09, which documented a health physics inspection conducted during the outage in late March 1990, discussed the chemical decontamination and the related problems mentioned by the CI.
According to the report, dose rates in the RCS did increase due to poor planning and execution of the decontamination.
The report also indicated that 4
the higher dose rate problem was discussed by the ALARA Committee on March 21, 1990, and that methods to itaprove the chemical 4
decontamination process were also discussed.
IR No. 90-22, which also reported on the early 1990 outage, noted that essentially all of the dose goals for each of the major high. dose jobs were met, despite the higher RCS dose rates and indicating that management took an active role in maintaining exposures ALARA during the outage.
The report also indicated that the licensee took the initiative to revise the outage dose goal midway through the outage when it was realized that th'e original goal was unobtainable.
This enabled the licensee to maintain a goal _in which to strive for.
Finally, none of the aforementioned inspection reports noted any significant problenm with the i
licensee's ALARA program, except for the. lack of an ALARA 4
incentive program and lack of participation in the ALARA
)
suggestion program.
This issue has since been addressed and improved significantly, as noted in IR Nos. 91-11 and 92-16.
With regard to ALARA, management commitment and involvement 4
continues and worker involvement is more prevalent than in the past.
Conclusions Based on the inspector's review of pertinent records and other documents, the allegation was substantiated in that (1) an engineer may have been required to be in the vicinity of a RHR valve for six hours in a respirator on March 8, 1990; (2) mistakes and oversights were made in the scheduling and conduct of the RCS chemical cleaning prior to the early 1990 refueling outage, resulting in higher-than-expected RCS dose rates; and (3) total radiation exposures for the outage did exceed initial goals.
However, the allegation was not substantiated in that significant evidence was not found suggesting Vogtle management is using or has ever used reasons of ALARA to justify things such as violations of Technical Specifications and/or other regulations.
Management appears to have been aware of the increased exposure problem early on and responded accordingly to maintain exposures ALARA for the remainder of the outage and beyond.
The licensee applied lessons learned and followed their
' procedures as required.
No regul'atory requirements were
~
violated.
Attachments 1.
Inspection Report (IR) No. 90-09 2.
IR 90-22 3.
IR 91-11 4.
IR 92-16 l
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v ENFORCEMENT CONFERENCE AGENDA U.S. NUCLEAR REGULATORY COMMISSION AND GEORGIA POWER COMPANY JUNE 2, 1994 I.
INTRODUCTION AND OPENING REMARKS E. W. Merschoff, Acting Deputy Administrator II.
DISCUSSION OF THE ENFORCEMENT POLICY B. Uryc, Director Enforcement and Investigation Coordination Staff III. OVERVIEW - Mr. Merschoff IV.
APPARENT VIOLATIONS AND NRC CONCERNS J.
R. Johnson, Acting Director Division of Reactor Projects
-V.
LICENSEE PRESENTATION W., G. Hairston, III, Senior Vice President, Nuclear Operations, Georgia Power Company BREAK * *
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VI.
NRC FOLLOWUP QUESTIONS VII. CLOSING - Mr. Merschoff
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3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Two independent Piping Penetration Area Filtration and Exhaust Systems shall be OPERABLE.
APPLICABILITY:
M0 DES 1, 2, 3, and 4 ACTION:
With one Piping Penetration Area Filtration and Exhaust System inoperable, restore the inocerable system to OPERABLE status within 7 days or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.7.7 Each Piping Penetration Area Filtration and Exhaust System shall be cemonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.
from the control room, flow (FI-12629, FI-12542) through the HEPA filters and enarcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heater control circuit energized; b.
At least once oer 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the system by:
1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria of greater than or equal to 99.95% filter retention while operating the system at a flow rate of 15,500 cfm
! 10% and performing the following tests:
(a) A visual inspection of the piping penetration area filtration and exhaust system shall be made before each 00P test or activated carton adsorber section leak test in accorcance with Section 5 of ANSI NS10-1980.
(b) An in place 00P test for the HEPA filters shall be performed in accordance with Section 10 of ANSI N510-1980.
(c) A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with Section 12 of ANSI N510-1980.
V0GTLE UNITS - 1 & 2 3/4 7-17 Amendment No. 21 (Unit 1)
Amendment No. 2 (Unit 2)
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Biradagham, Alabesia 18301 Desr Mr. Myer:
This is a final response to ERA 94.VAA025 widsh requeuse an evaluation of the Unit 1 Aux 111asy Building Piping Penetration Area Mitration and Eubeust System (FPAp respeet to Ma 2/ o.energland stack exhaust dannpara. The stack exhaust dampers j
d OP%2550B & IP%2$51B) are designed to open to.a preset position when the l
is startadin order to adatain a nessaiw pressure in the piping penstration ates. The j
FPA758 ausasias the area under a negathe pressure to ensure that radiosetiw inssedals lealdag Desa the maatuminal penetraelan roons sad ECC5 equipment are flhered e
i reseblagthe envirvanant.
I Sinos the PPAFB8 la nornmily in mandby, the mask whaus dampers wesid haw been enershed la the eloemi posidea. Whhtheos dampers closed, the FFAFE8 could not amistain the pipins penetreden assa veder a nessiive presses, possmay dewiss siste radionstin mesedalla the arm servedby the PPAPES to esape to the entrearaent without possing through the filter system For the purposes of this evolostion, it is i
assumed that at sirbaras radioendve matenels tem tlw =aakaalant pensenden rooms and ECC8 equipment are reisesed direetlyi o the environneest.
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Pse: asA94.VAA015 Mr. C.3. Myer XdBMG Apru 28,1994 las: 5613803 j
Pages
.i Thalatest sehty evaluation for the PPAFB8 associatad with amendments it and 31 to I
i operating lleenses NFF.64 and 31, assusses ECCS lodine laakses is 2 spa sad la the Art l
presorbed by Reguletory Ocide 1.3, l.a. 91% elemental,4% organie, and 5% particulate.
l Further, the mer ash era asumed a be 90%, 30%, and 90H resputively. The j
esapositeeSeiencythenwouldbe:
(.911.9+.04 c.3+.05x.9) = 876 or approuimately 90%.
l The complete inoperebility of'the PPAF58 iney then Lasrease the acCs leslage omnrihudos.to of-site and control mondones by a fasser of,,. "
"; 10.
j However, the surrertECCS leakage vales based on Toshnical Speeldeados d.7.4 is less then 0.1 spm, and historically the valso has bese less than 0.2 spm, thereAwo the expos f
saures term would be a mater of te less than assumed la the surrent dose smalysis. The not aihetwould be that the EAB, IJz, and Connel Room doses as shone in the BBK l
wouki runnin ennemisty unehenged and wkhin the 10 CFA 100 and GDC 19 aseepianos i
erteoria. This evahasion is senservative he the'hBowing ansons:
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During the period of thna that the mask exhaust dampers were closed, the FFAFB8 l
realmulation/filassion capabikty remained ihnedonal. Whh aussydon of several piping r
! z rooms, ECCS equipment mbject to pose.LOCA restreulation loop leslage le i
lo'essed la rooms not a(asers to direct atmospherte release pedneste i.e. ECC5 leslage would occur in rooms latador to the madBay building and below grade, and would been i
l to be transported through several rooms prior to relean to the essesphem. Leekage through the seateinment isolatlas valves into the piping penewedon rooms le seemn j
leek directly to the atmosphere without proessalag or holdup. Dessues the PPAPBS l
reeiradmienrakredo hneden runaned ihnedonal, ECes takege a the inserior compartments of the auxiliary hunding would be supseted to be futmed prior to transport to other roome n4oommt to semospherisleakage pathways. Leslage which dfBased l
throughma the budding andbypassed the mer unk would havelong tortuous pathways 2 l
maiow and would be adiat a signiscent naarai mmovat procesas siens the (estning, plateout, etc.). hrther, as 1,vaaned in the bases of the Techniest 8 the hesters in the PPAFRS are maisteined tr delses in depth, Thus the expected l
hr tin ruiralstion@rmion fbnodon wadd be in ames of that removal Wodhedisthe the PFAFE8 steek exhmast darnpmeMM In 6 have samhed in amesess the ofr.sim sad essent room den ankadoes et 1o cpm 100 i
sad (WC19 respeedwely.
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e.es sus-sas4 esse aus en vs4e sca e m uscr e.sa Wr. C.R. Myer Fue: REA 94 VAA025 Asitas,1994 X4 BIB 6 hae Las: seassos This evalunden has been wiewed with Mwaans of sNC, Ifyou how any queadons, please contact Ta }Inyes a estansion 6852.
Veryenkyours, Ch 00.1
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3*,
REGloN 11 7
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101 MARIETTA STREET. N.W., SUITE 2900 ATLANTA, GEORGIA 3(%BZH)19B "N.
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MAY l 71994 NOTICE OF SIGNIFICANT MEETING Name of Licensee:
Georgia Power Company Name of Facility: Vogtle Unit I Docket Nos.:
50-424 Date and Time of Meeting: June 2, 1994, at 9:00 a.m.
Location of Meeting:
Region II Office. Atlanta, Georgia Purpose of Meeting: Open Enforcement Conference to Discuss the Extended Degradation of the Unit 1 Piping Penetration Ventilation System RII Cognizant Division: Division of Reactor Projects (DRP) l NRC Attendees:
S. D. Ebneter, Regional Administrator, Region II (RII)
E. W. Merschoff, Deputy Regional Administrator, RII J. R. Johnson, Deputy Director, DRP, RII l
M. V. Sinkule, Chief, Reactor Projects Branch 3, DRP, RII P. H. Skinner, Chief, Reactor Projects Section 3B, DRP, RII D. A. Seymour, Project Engineer, Reactor Project Section 38, DRP, RII D. B. Matthews, Director. Project Directorate 11-3, Office of Nuclear Reactor Regulation (NRR)
D. S. Hood, Project Manager, Project Directorate II-3, NRR B. R. Bonser, Senior Resident Inspector, Vogtle Nuclear Station R. D. Starkey, Resident Inspector, Vogtle Nuclear Station A. F. Gibson, Director, Division of Reactor Safety, RII l
B. Uryc, Jr., Director, Enforcement and Investigation Coordination Staff, RII C. F. Evans, Regional Counsel, RII Licensee Attendees:
H. Hairston, II, Executive Vice President - Nuclear Operations J. Woodard, Senior Vice President - Nuclear Operations, C. McCoy, Vice President - Vogtle Project J. Beasley, General Manager - Nuclear Plant W. Kitchens, Assistant General Manager, Plant Support W. Bunneister, Manager Engineering Support S. Chesnut, Manager Engineering Technical Support M. Griffis, Manager Plant Modifications J. Bailey, Licensing Manager, Vogtle Project Support GP S&Y
MAY
? 1994 Notice of Significant Meeting 2
NOTE:
Attendance by NRC personnel at this meeting should be made known by May 25. 1994. via telepnone call to D. A. Seymour, at (404) 331-4198 or P. H. Skinner at (404) 331-6299.
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I Approved:
!L e t fierce H. ' Skinner, Chief Reactor Projects Section 3B Division of Reactor Projects Distribution:
J. L. Milhoan, Deputy Executive Director for Nuclear Reactor Regulation. Regional Operations and Research H. L. Thompson. Deputy Executive Director of Nuclear Materials Safety, Safeguards and Operations Support l
L. J. Chandler Assistant General Counsel for Hearings and Enforcement J. Lieberman. Director of Enforcement W. T. Russell, Director, Office of Nuclear Reactor Regulation (NRR)
L. A. Reyes. Associate Director for Projects F. R. Miraglia, Associate Director, NRR D. B. Matthews, Director, Project Directorate II-3, NRR G. C. Lainas. Assistant Director, RII Reactors, NRR D. S. Hood, Project Manager, Project Directorate II-3, NRR L. L. Wheeler, Project Manager, Project Directorate II-3, NRR L. R. Plisco, Regional Coordinator, EDO l
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