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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass NUREG-5055, Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-50551990-10-10010 October 1990 Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-5055 ML20059C1331990-08-21021 August 1990 Notification of Enforcement Conference 90-143 W/Util on 900830 to Discuss Violation Noted During Special Security Insp 1999-09-03
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1561998-01-22022 January 1998 Staff Requirements Memo Re SECY-97-244, Waste Classification of Plant Reactor Vessel ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20216F2611997-08-26026 August 1997 Staff Requirements Memo Re SECY-97-164, Shipment of Decommissioned Reactor Vessel,Containing Irradiated Internals,From Trojan Nuclear Plant to Hanford Nuclear Reservation,Richland,Wa ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass 1999-09-03
[Table view] |
Text
. _ _ - _ _ _ _ _ _ _ _ _ _ ._
,. S ~[J - N f JAN 0 71993
.M MEMORANDUM FOR: Richard W. Cooper, Director, DRSS, Region I
/'" J. Philip Stohr, Director, DRSS, Region II 2 Charles E. Norelius, Director, DRSS, Region III L. Joseph Callan, Director, DRSS, . Region IV c_ _
Ross A. Scarano, Director, DRSS, Region V M- LeMoine J. Cunningham, Chief Radiation Protection Branch x Division of Radiation Safety n and Safeguards p Office of the Nuclear Reactor Regulation
( 4.CT: FOLLOW-UP ON A REFJRT OF RESPIRATOR DEFECT Trohn Nuclear Power Plant staff submitted information to us concerning-quality control cence.,as with Mine Safety Appliances Co. (MSA) full face negative pressure respirators (Ultra View and Ultra Twin) with potential 10 ..
i CFR Part 21 implications. We have contacted the National Institute of pJ Occupational Safety and Health (NIOSH) and MSA concerning this matter and_ are providing the following for your information. This is not an official .<
radiation protection branch (PRPB) Part 21 closecut, as the consequences of 3 the raspirator defects do not neet the thrchold requirements of Part 21 (they do not create r 'tantial safety hazard' PRPB contacted NIOSH informing them of Trojan's report of defects (see enclo ure 1). NIOSH then contacted MSA and followed up on the vendor response (see enclosures 2 & 3). MSA responded to NIOSH (see enclosure 4) by >
characterizing the problem as an isolated incident unique to their special order process and not a generic issue. NIOSH concluded that MSA had made satisfactc~ progress toward the resolution of this problem (enclosure 5).
PRPB wanted t3 pursue the special order issue further and after conferring with NIOSH contacted MSA directly to ask what actions were taken to prevent _
any reoccurrence with other special orders. MSA responded.(enclosure 6) that .
it has reviewed its inspection procedures with its production personnel and' have taken steps necessary to prevent occurrences of this type in the future.
Since the vendor's corrective actions appear to be appropriate, PRPB plans no further action in this matter. If you have any questions contact Dan Carter - -
v at (301)504-1848.
Original signed by LeMoine J. Cunningham LeMoine J. Cunningham, Chief 11002-3 Radiation Protection Branch Division of Radiation Safety Q f QOS$ $0f>O344 PDR and Safeguards S
Office of Nuclear Reactor Regulations
Enclosures:
As stated plSTRIBUTION: See next page OFC PRPB:DRSS
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+
NAME DCARTERDL
[f[T0Y [thMbAM ~
~* I DAQl/7/93 b 01/7/93 01/7/93 Of ficial Record Copy' Document Name: :.sa21 1
DISTRIBUTION:
B. Murray, RIV F. Congel E. Butcher
-L. Cunningham
. Central l File,: P1.37 -
F. Combs, 6H3 J. Wigginton PRPB R/F R. Anderson, TTC T. Essig PDR, LL6 L. Norrholm, 904 J. Joyner, RI W. Cline, RII
. C. Pederson, RIII J. Reese, RIV J. Catshall, MSA R. Metzler, NIOSH G. Huey, Trojan L. Kokajko, 13E16
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Enclosure 1 f3 UNITED STATES
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.. i NUCLEAR REGULATORY COMMISSION WASHINoToN D.C. 20666 k~/ muw L
Mr. Richard W. Metzler, Chief Certification and Quality Control Branch National Institute of Occupational Safety and Health Division of Safety Research Room S-105 944 Chestnut Ridge Road j Morgantown, West Virginia 26505-2888 1
SUBJECT:
PROB!. EMS WITH MSA RESPIRATORS i
L Dear Mr. Metzler-I ihis letter is to bring to your attention an issue identified to us by one of j J
our power reactor licensees. This issue (see enclosure)= focuses on quality i control concerns with Mine Safety _ Associates (MSA) full face negative pressure i
respirators (Ultra View and Ultra Twin). These concerns range from-respirator! l microphones being installed upside down, filter gaskets installed. upside down,- J L a missing inhalation valve disc and improperly installed lens ring:: causing.
L distortion of rubber around the lens covers. These deficiencies were-identified by the licensee as part of their incoming quclity control (QC) checks on all new respirato_rs- prior to field use.-
The licensee notified MSA of these problems-and' a-vendor representative was-sent to the reactor site to investigate the matter. The MSA representative p inspected 20 respirators identified as having problems and confirmed that 11 i
had rubber distortion of some matter in the face piece area; the remaining'9 were able to be repaired on site. The 11 respirators with distorted rubber were returned to MSA for evaluation. Two of the 11_respirat' ors' returned failed the vendor DOP testing criteria.
MSA claimed that they did not know how these problems occurred and'said-that) their QC was "as good as always." MSA representatives informed our licensee- 'i I that they did n'ot feel it was necessary to' alert other MSA customerst of these problems unless other customers expressed similar.protlems. If MSA is waiting 3 for feedback from their customers, then we should point out that not many of the thousands of NRC licensees (aside from the 100 cr so power reastor-licensees) have comprehensive, sophisticated-incoaing QA/QC programs which-test 100 percent of the negative pressure respirators. prior to use. We suspect that the vast number of respiratory protection programs across-the country for not. have-formal aggressive incoming QC programs.
Is L
I would like to talk with you about MSA's apparent lack'of wiliingness to '
inform their customers of possible generic problems with their products.
L While this is not a serious worker safety issue at nuclear power reactor
[
L
' facilities, because there respirators are used only in areas of relatively low:
concentrations of radioactive materials,-we are considering issuing ant z
g (h h Cs
.g
,' Mr. Richard W. Metzler ;
information notice to the nucisar industry. The purpose of this industry
~
notice would be to inform our-licensees of this issue so that they might consider expanding the scope of their own QC programs. Please contact me at (301) 504-1007 or Jim Wigginton at (301) 504-1059.
Sincerely, Original signed by LeMoine J. Cunnine^m
. LeMoine J. Cunningham, Chief Radiation Protection Branch _
Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
Enclosure:
As stated
. Distribution:
FCongel
. EButcher LJCunningham -i JWigginton TEssig DCarter FCombs, 6 H3 DCool, NLS 139 Regional BC's RPB R/F Central Files
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DATE 08//Z/92 08// /92 08/it,492 0FFICIAL RECORD COPY DISK \ DOCUMENT HAME: -A:\MSA i
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CORRECTIVE ACTION REQUEST (CAR)
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INITIATION / .
CAR Numbe C- [ tul Datet / M 5everity Level ~~TC ',ul INITIAT0A SECTION til Audit /Suneillance No.
SYST N NLHBERi21 A//A. n0JAN CC".10NENT ID NLHZEAf t) #_J[4 CATE CT DISC 07ERYiss.,g /.f,1,,/,,fd, TIMI OT DISCOVERY!st Nao PLANT MODEtst. _/
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_1%.13 o s v &<r s ' Q o m _ W 6 .e A <-s f % * !" .l1 e _/ rk. // 2cpeart 1992 -
A new shipment of small and large respirators were received at the plant and purchased by Joan and Margaret from the '
varehouse (10 large, lo small). While preparing these '
respirators for use, they noticed the first respirator to have its micretSone upside down and repaired it. Further inspection showed that all 10 of the large and 7 of the small respiraters had problems. The following is a list of the M indications.
[r -3J
- Upside down microphones,
- Inproperly installed lens rings. Some were pinching the i) rubber between the mating portions which caused the rubber to bulge out. One had the lens not eve.n seated in the "
rubbor portion at the bottom of the face piece holder.
Some rings were not lined up with the center lines
- indicated at the top a,nd bottom of the respirator.
- Microphones found installed at the 5 and 8 o' clock {'
positions which were pressing into the rubber. pM m
- Upside down filter gaskets. -7
- Missing inhalatiot, valve disc.
- Gap between the speaker assemblies and the rubber.
- oposition.
rings on the sp5aker assemblies rotated to the wrong .
Joan and Margaret called Dallas somerville to inform him of these problems. Dallas asked thet they bring the respirators from the assembly room to the conference room and he would ca. A MSA. Bob Rucinski of MSA was notified and arrived at the plant at 1200. He inspected all of the 20 respirators and confirmed that all 10 large and i small had the rubber distorted in some manner in the face piece area. The remaining 9 small :espirators were able to be rapaired.
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, C.AQ-Gl95 April 13, 1992 MM-008-92 Paga 3 , ,
A complete inspection of all respirators in-stock at the warehouse was performed with Bob Rueinski.. No problems were found.. A detailed inspection of all respirators purchased since December of 1991 and already in service in cabinets and emergency lockers was also performed, and no problems identified. .
NOTE: 1. Problems with microphones being installed upside down was in both ultra twin and ultra view
~
respirators.
,2. Rubber distortion and missing pieces were isolated to ultra twins only. -
Another meeting will be conducted with representatives from MSA er _ E[
along with Dallas Somerville, ;Toan Thackery, Margaret Brady, 4.
Spike Ford of the compliance group, and myself at the plant on j,
.. April 14, 1992. Items to be discussed will be the lack of ;
quality workmanship recently indicated with the MSA respirators, .
what MSA's results of investigating the problems were, and -
potential reporting issues. .
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c; T. Meek 't -
D. Somerville
- S. Ford J. Thackery-M. Brr.dy e
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.-[ DEPARTMENT OF HEALTH A HUM AN SERVICES Public Health Service
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NIOSH
Reference:
TN-06205 / Qnters for Disease Control National Institute for Occupational Safety and Health - ALOSH 944 Chestnut Ridge Road Morgantown, WV 26505-2838 August 20, 1992 Mr. LeMoine J. Cunningham United States Nuclear Regulatory Commission Was!.ington, D. C. 20555 i
Dear Mr. Cunningham:
The National Institute for Occupational Safety and Health (NIOSH) has received your letter of August 12, 1992, concerning nonconformances with Mine Safety Appliances Company (MSA) Ultraview and Ultratwin negative-pressure facepieces.
The investigation of these reperted nonconformances has been assigned NIOSH Task Number TN-06205. Mr. Jeffrey L. Gutshall of MSA has been contacted, and NIOSH awaits the manufacturer's report of investigation concerning this matter. You will be kept informed of the developments concerning this investigation.
If NIOSH can be of further assistance, feel free to contact this office.
Sincerely yours, O**
Richard W. Metzler, Chief certification and Quality Assurance Branch Division of Safety Research i
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Enclosure 3 1
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DEPARTMENT Of HEALTH & HUM AN SERVICES Public Health Service
'O'*** NIOSH
Reference:
TN-06205 i Centers fot Diseau controt I
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v National Institute for Occupational EWfety and Healm - ALOSH 944 Chestnut Ridge Road Morgantown, WV 26505-2888 August 31, 1992 Mr. Jeffrey L. Gutshall Mine Safety Appliances Company P.O. Box 439 Pittsburgh, Pennsylvania 15230
Dear Mr. Gutshall:
The National Institute for Occupational Safety and Health (NIOSH) has received a report of nonconformances with the MSA Ultraview and Ultratwin negative pressure facepieces. These nonconformances reportedly involve microphones and filter gasket; heing instal-led.
upside down, a missing inhalation valve disc, and improperly .
installed lens rings.
These nonconformances have been reported to NIOSH-by Mr. LeMoine J. Cunningham of the U.S. Nuclear Regulatory Commission.. A copy of the letter initiating this investigation is enclosed.
The investigation and ultimate resolution of this nonconformance investigation have been assigned NIOSH Task Number TN-06205. The MSA report of investigation and proposed corrective action, if cny, should be submitted by September 18, 1992. Special consideration should be given to Mr. Cunningham's concern about notifying other users of the need to closely inspect their own respirators for similar nonconformances.
Please provide this office with a list of all model and certification numbers involved in this investigation.
Sincerely yours,
/ ichard W. Metzler, Chief Certification and Quality Assurance Branch Division of Safety Research Enclosure l cc:
L. Cunningham (NRC)
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I' Ehclosure 4
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A Mine Safety Appliances Company + Safety Products Engineenng
- P.O. Box 439 + Pittsburgh, PA 15230 Telephone:(412) 776 7700 wm asom aom.o-(412) 776-7740 September 17, 1992 Mr. Richard MetzJer Certification Branch NIOSH 944 Chestnut Ridge Road Morgantown, WV 26505 RE: Reported MSA Facepiece Problems TN-06205 MSA REF: NP92-48
Dear Mr. Metzler:
This is in response to your letter dated August 31,1992.
MSA was 'nade aware of this problem through our field representative. A subsequent investigation confirmed that these respirators were not representative of the quality our customers have come to expect from MSA. The subject respirators were repaired and returned to the customer.
These respirators are not stocked equipped with a communications package. This is usually added by the user through the use of a kit. In this instance, a number of respirators were supplied so equipped through a gecial order.
The positioning of the microphone can be changed by the user to suit preference. -If, however, -
the microphone is in the lower quadrant of the facepiece, it can interfere with our DOP test fixturing. This is why it is shown in the 12:00 position on the drawing. Any other position is user determined and is cosmetic.
Gur information confirms this problem is isolated to this special order. It is conceivable that some of these escaped normal Q.C. inspection. , __ _
The lens ring assembly procedures, as well as the valve, gasketing and other installations are monitored by each worker in the work cell. Furthermore, each facepiece is normally 100% DOP inspected and random post production samples are removed and inspected. Q.C. has been alerted to this problem and has reviewed Ge inspection procedures with production personnel.
LOCM'.0a. Waldo Road Cranberry Twp.
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1 MSA sold'over 50,000 Ultra-Twin respirators in 1991. Thousands havc been sold to commercial nuclear users. A greater number were purchased by the D.O.E. No other problems have been reported. This confirms the finding at Trojan that a 100% inspection of their stock found no other defective respirators.
MSA is convinced thtt this is not a generic problem with our products. Our internal review, the customer review, as well as a review of field experience confirm this as an isolated incident.
If you have any questions, picase contact me.
Sincerely,
/ .
Jeffrey L. Outshall Design Engineer, Government Relations Safety Products Division JLG:Ib b
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