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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205C3521988-09-23023 September 1988 Final Response to FOIA Request for Documents Re Plant. Forwards App D Documents.App D Documents Also Available in PDR ML20093K3281984-10-11011 October 1984 Requests Discontinuance of Document Distribution to Offshore Power Sys,Which Closed on 840901 ML20083K7301984-03-27027 March 1984 Responds to IE Bulletin 83-08.Circuit Breakers Not Purchased or Specified for safety-related Applications.No Further Design Activities Planned Prior to Obtaining Customer ML20073B5171983-04-0808 April 1983 Responds to Generic Ltr 83-10D Re Resolution of TMI Action Item II.K.3.5, Study Need for Auto Trip of Reactor Coolant Pumps. Resolution Will Be Initiated When Customer for First FNP Is Attained & Final Design Efforts Begun ML20071E8321983-03-0101 March 1983 Ack Receipt of Generic Ltr 83-07 Re Requirements of Nuclear Waste Policy Act of 1982.Lists Reasons for Not Entering Into Waste Disposal Contract W/Doe ML20072A8671982-12-29029 December 1982 Requests Public Statement Responding to 760615 Testimony Before NRC Re Safety Concerns Associated W/Ops Floating Nuclear Power Plants ML20072A8621982-12-12012 December 1982 Requests Response to Previous Correspondence Opposing OPS Floating Nuclear Power Plants,Heretofore Unacknowledged by Nrc.June 1976 Testimony on SER Encl ML20072A8761982-12-0101 December 1982 Requests Response to ,Mistakenly Directed to Former Chairman Jm Hendrie ML20069G5291982-09-17017 September 1982 Forwards Revisions to Environ Protection Plan Per 820915 Telcon ML20072A8701982-08-14014 August 1982 Lists Reasons for Opposing Issuance of Mfg License to OPS for Floating Nuclear Power Plants ML20054M3461982-06-23023 June 1982 Confirms 820623 Telcon Re Official Closing of Lpdr for Offshore Nuclear Power Plant.Lpdr in Jacksonville,Fl Will Remain Open ML20052G6091982-05-11011 May 1982 Advises of RA Thomas Appointment as Acting Manager of Offshore Power Sys Div.Pb Haga Appointed Director of Engineering.Svc List Encl.Related Correspondence ML20041E5781982-03-0505 March 1982 Advises That OPS Became Div of Water Reactor Div of Westinghouse on 820201.Change Does Not Affect Licensing Process.Svc List Encl ML20041D6861982-02-24024 February 1982 Advises of Westinghouse Nuclear Energy Sys Organizational Changes.Organizational Charts Encl ML20040G3531982-01-29029 January 1982 Requests Public Response to 760615 Testimony ML20039E7421981-12-21021 December 1981 Delegates Authority for Review of Info Sought to Be Withheld from Public to Pb Haga,Director of Power Sys Technology ML20062M2991981-12-11011 December 1981 Forwards Applicant 811211 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision. Document Supersedes Applicant 790601 Proposed Partial Findings of Fact in Form of Proposed Initial Decision ML20038B9601981-12-0202 December 1981 Repts on 811113 Telcon.Aslb Denied Applicant Request That Answers to ASLB 811112 Questions Be Provided Orally at 811204 Hearing.Answers Are to Be Filed in Advance by 811127. Certificate of Svc Encl.Related Correspondence ML20038B5911981-11-12012 November 1981 Submits Info Requested in 811106 Telcon W/Nrc Re Turbine Missile Shield ML20049A7371981-09-17017 September 1981 Confirms 810917 Telcon Re Containment Design Pressure.Util Reluctantly Commits to Design Containment Vessel to Meet ASME Svc Level a Stress Limits for Design Interval Pressure of 25 Psig at Ambient Temp ML20010J3741981-09-10010 September 1981 Submits Addl Info Re Equipment Qualification Modifying 810902 Response Re Generic Issue A-24.Safety-related Equipment Will Be Qualified in Accordance w/NUREG-0588, Category I Requirements ML20010F8661981-09-0404 September 1981 Ack Receipt of NRC 810831 Ltr Re Meeting W/Util to Discuss Facility.Gl Paulson No Longer W/Nj Dept on Environ Protection.A Mclellan Now Assistant Commissioner for Science & Research & Should Replace Paulson on Mailing List ML20010E6101981-08-28028 August 1981 Corrects Date of Ref Cited in 810818 Ltr Responding to NRC Request for Info Re Generic Technical Issues A-2 & A-36 ML20009C8931981-07-22022 July 1981 Advises That Review of Plant Design Rept & Amends for Barge Mounted Floating Nuclear Plant Has Been Completed.Final Approval Will Depend on Successful Plan Review,Insp During Const & Approval by Officer in Charge ML19346A4151981-06-11011 June 1981 Forwards Draft App C to Plant Design Rept, in Response to post-TMI Requirements.App C Will Be Filed Formally at Conclusion of Technical Review & Upon Resolution of NRC Concerns ML20004E5451981-06-0606 June 1981 Requests Name Be Deleted from Mailing List Re Hearings ML20126F4071981-03-10010 March 1981 Forwards Characteristics & Sketch of Floating Nuclear Power Plant & Info Sheets on Floating Nuclear Power Plant & Mfg Facility,On Behalf of Ofc of General Counsil.Requests Insp of Facility & Testimony at 810526 Trial Re Mfg of Plants ML20008F5561981-03-0404 March 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rule Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20008F5621981-03-0303 March 1981 Expresses Concern Re Inclusion of OPS Application in Proposed Rule Currently Under Consideration for near-term Cp/Mfg License Applications ML20008F5671981-02-24024 February 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rulemaking Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20002E3551980-12-16016 December 1980 FOIA Request for All Documents Re OPS Application for License to Mfg Floating Nuclear Plants Containing Statements Re Alternate Land Uses ML19345C2711980-10-29029 October 1980 Requests Info Re Facilities W/Active CPs Pending,License Definitions & Requirements for Floating Nuclear Plants ML19332A0831980-09-0505 September 1980 Requests That Schedule Be Established for Completing Review of Application for Mfg License & That NRC Resources Be Committed for That Purpose.Nrc Should Initiate Review of Util 800715 Responses to NUREG-0660 ML19331C6281980-07-22022 July 1980 Requests Available Info Re Projected Offshore Floating Nuclear Power Plant ML19320D4621980-07-15015 July 1980 Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience ML19329G1971980-05-21021 May 1980 Requests Reply to CT Brown 800407 Ltr Expressing Support for Floating Nuclear Power Plant Project ML19320B7581980-05-16016 May 1980 Ack Receipt of Encl 800407 Ltr to President Carter Re Employment Opportunities Offered by Offshore Floating Nuclear Plant Project.Decisions on Commercial Projects Are Made by Private Sector,W/Nrc Approval ML19323C6321980-05-0606 May 1980 Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for ML19305C4241980-03-18018 March 1980 Forwards Response to NRC 791017 Ltr Requesting Addl Info Re Core Thermohydraulic Effects ML19257A3011979-12-21021 December 1979 Forwards 36A93, Responses to Post-TMI NRC Requirements, Per IE Bulletin 79-06,NRC 791010 & 1109 Ltrs Re TMI Lessons Learned Task Force short-term Requirements & TMI Lessons Learned Task Force Final Rept. ML19210D0981979-11-0707 November 1979 Forwards Response to OPS 790709 Ltr Re Mobilization & Deployment of Coast Guard Vessels in Response to Emergency at Floating Nuclear Power Plant ML19210C9341979-10-18018 October 1979 Responds,On Behalf of Applicant,To NRC 791011 Ltr Addressed to ASLB Re Unavailability of NRC Witness.Requests Scheduling of 791031 or 1101-02 & 05 Hearing Session Re ASLB Questions Pending Since Mar 1979.Urges Publication of SER Schedule ML19253B4191979-10-0505 October 1979 Requests Plan & Schedule for Completion of Review of Application for Mfg License ML19253B5911979-09-26026 September 1979 Agrees to Use McGuire Nodalization Scheme or More Detailed Model for Analyses of Pressure Transient in Steam Generator Encl Following Steam Line Rupture ML19208D5551979-09-21021 September 1979 Forwards Revision 2 to Rept 36A59, Fnp Core Ladle Design & Safety Evaluation. Revision Reflects Sandia Lab Comments Transmitted in NRC 790605 Ltr & Results of 790724 Meeting W/Nrc & Sandia Lab ML19209C9571979-09-20020 September 1979 Protests NRC Recommendation That Floating Nuclear Power Station Not Be Built ML19208B0281979-09-14014 September 1979 Forwards Responses to ACRS Subcommittee 790725 Questions Re Core Ladle & TMI-2.Response Modifies Design Presented in Rept 36A59 Floating Nuclear Plant Core Laddle Design & Safety Evaluation. Requests ACRS Meeting in Oct ML19211A8421979-09-0606 September 1979 Forwards B Peters Ltr Re NRC Decision to Issue License for Const of Floating Nuclear Plants.Requests Comment ML19209B4791979-09-0606 September 1979 Forwards 790806 Ltr from B Peters Expressing Concern About Possible NRC Decision to Issue License for Const of Offshore Nuclear Power Plants.Requests Review & Assistance in Responding to Ltr ML19209B3511979-08-22022 August 1979 Forwards Ltr from PA Nilsson Expressing Concern About Plans to Issue Mfg License.Requests Info in Order to Respond to Constituent Inquiry 1988-09-23
[Table view] Category:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20125A6321979-06-26026 June 1979 Forwards IE Circular 79-10, Pipefittings Mfg from Unacceptable Matl. No Action Required ML20148J0861978-11-0606 November 1978 Forwards IE Circular 78-18 ML20148H8921978-11-0606 November 1978 Forwards Request for Addl Info Re Topical Rept 7270-RP-16A51,Buckling Criteria & Appl of Criteria to Preliminary Design of Containment Shell for the Floating Nuc Plant ML20148H8201978-11-0303 November 1978 Expects Review of Floating Nuc Plant Fire Protec to Be Completed by Mid-Mar,1979.Schedules Meeting for 790130 1979-06-26
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20205C3521988-09-23023 September 1988 Final Response to FOIA Request for Documents Re Plant. Forwards App D Documents.App D Documents Also Available in PDR ML20054M3461982-06-23023 June 1982 Confirms 820623 Telcon Re Official Closing of Lpdr for Offshore Nuclear Power Plant.Lpdr in Jacksonville,Fl Will Remain Open ML20125A6321979-06-26026 June 1979 Forwards IE Circular 79-10, Pipefittings Mfg from Unacceptable Matl. No Action Required ML20204C9411978-11-24024 November 1978 Submits Statement on Actions Re Recommendations Made by Us Comptroller General in Rept Before Licensing Floating Nuc Pwr Plants,Many Answers Are Needed. Forwards NRC Staff Responses,Related Correspondence & NUREG Repts.W/Encl ML20204C9281978-11-24024 November 1978 Submits Statement on Actions Re Recommendations Made by Us Comptroller General in Rept Before Licensing Floating Nuc Pwr Plants,Many Answere Are Needed. Forwards NRC Staff Responses,Related Correspondence & NUREG Repts.W/Encl ML20204C9151978-11-24024 November 1978 Submits Statement on Actions Re Recommendations Made by Us Comptroller General in Rept Before Licensing Floating Nuc Pwr Plants,Many Answers Are Needed.Forwards NRC Staff Responses,Related Correspondence & NUREG Repts.W/Encl ML20204C9001978-11-24024 November 1978 Forwards Statement to Congress on NRC Actions Being Taken Re Gao Recommendation on Floating Nuc Pwr Plants ML20148J0861978-11-0606 November 1978 Forwards IE Circular 78-18 ML20148H8921978-11-0606 November 1978 Forwards Request for Addl Info Re Topical Rept 7270-RP-16A51,Buckling Criteria & Appl of Criteria to Preliminary Design of Containment Shell for the Floating Nuc Plant ML20148H8201978-11-0303 November 1978 Expects Review of Floating Nuc Plant Fire Protec to Be Completed by Mid-Mar,1979.Schedules Meeting for 790130 1988-09-23
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M t ** "8 0 UNIT ED ST ATES
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REGION 11 C d7
- '~' ' c 101 M ARIE TT A ST RE E T , N .W ATL ANT A. GE ORGI A 30303 o, [
% , . .. , [ NCV 9 197E In Reply Refer To:
RII:JP0 50-437 offshore Power Systems Attn: Mr. A. P. Zeche11a, President 8000 Arlington Expressway P. O. Box 8000 Jacksonville, Florida 32211 Centlemen:
The enclosed Circular 78-18 is f orvarded to you f or infomation. No specific action is requested and no written response is required. If you desire additional infomation regarding this matter, please contact this office.
Sincerely,
, /i f4 James P.. O'Reilly
' Director
Enclosures:
- 1. IE Circular 78-18
- 2. List of IE Circulars issued in 1978 7811150/ 6
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 November 6, 1978 IE Circular 78-18 UL FIRE TEST
, Background On September 15, 1978, a fire test of a full-scale vertical cable tray array was conducted at the Underwriters Laboratory (UL) near Chicago, Illinois. It was part of the fire protection research program managed by Sandia Laboratories under NRC contract. The purpose of the test was to demonstrate the effectiveness of area sprinklers and cable tray fire barriers constructed of ceramic fiber blankets in preventing damage to cables as a result of an exposure to a flammable liquid fire. The test resulted in damage to some electrical cables.
Discussion The configuration of the fire test was selected to simulate a section of a plant area with vertical cable trays containing redundant safety divisions arranged such that the redundant divisions could be simul-taneously exposed to a potential fire resulting from an inadvertent spill of flammable liquid in the area. The arrangement of the cable trays and the designation of the redundant tray divisions is shown in Figure 1.
Figure 2 shows the location of the fire detectors and the three groups of sprinklers. Each of the five cable trays contained cable insulated with polyvinyl chloride and was enclosed in a separated ceramic fiber blanket fire barrier from floor to ceiling in accordance with the manu-facturer's recommendations. The sprinkler and detector arrangement was as permit ted by NFPA Code. However, no water was actually used at any time during this test due to the failure of some sprinkler heads to actuate, as explained below.
Each sprinkler location in the test arrangement contained three nominally identical temperature sensing sprinkler heads with fusible links adjacent to an open sprinkler head which was connected to a manual water supply valve. The temperature sensing heads were wired to signal when their links fused. Af ter all three t emperature sensing heads at a given loca-tion activated, then the water supply for the open head was to be manually admitted. The sprinklers were of a type which actuate at the glow end of acceptance for reaction time. The test procedure required that all three temperature sensing heads had to activate before water would be turned on. In this way, it was expected to get some data on variability in the response time of identical sprinklers.
DM l'f - 9 7/ //5000 s-
November 6, 1978 IE Circular 78-18 Test Details The test was started by igniting the two gallons of heptane that was poured into the floor pan. A fully developed fire occurred almost immediately. The ceiling smoke detector alarmed in about 15 seconds.
In about 50-60 seconds, two of the three temperature sensing sprinklers located between the wall and cable trays 1 and 2 activated. The fire between cable trays 1, 2, 3, and 4 appeared most intense, apparently because of a chimney effect between the four trays. The flames between cable trays 3 and 5 did not appear to be so intense. The ceramic fiber blanket absorbed some of the heptane so that after the heptane in the pan burned, most of the flame seemet to come from the bottom outside surface of the ceramic fiber blanket. No additional temperature sensing sprinkler heads at any location activated; thus, the sprinkler water supply was not turned on for any of the three sprinkler locations.
The apparent slow response of the third temperature sensing sprinkler is being investigated, since this was not intended to be a slow response sprinkler.
At about 3 minutes into the test there was an indication of a short circuit in cable tray 3, which was probably caused by the fire. After 5-7 minutes the height of the flames appeared to subside; however, residual flames continued for about 40 minutes.
l Preliminary Results and Analyses Preliminary information indicates that the flacnable liquid or flames penetrated the protective barriers at the bottom of the vertical trays and caused fire damage to the polyvinyl chloride insulation on cables in four of the five trays.
On subsequent 500-volt megger tests, it was found that another cable in tray 2 had also experienced some damage, as evidenced by a conductor to ground short.
The most probable cause of the fire damage in certain cable trays appears to be related to the absorption or seepage of heptane under the ceramic fiber blanket at the juncture with the floor. Once the heptane entered the interior regions of the cable tray, then ignition apparently occurred via the small opening at the floor or through a vaper/ air path within the joints. There is some indication that some cable damage was caused (wicking effect) by absorption of heptane on the inside of the barrier and it s ignition which heated a cable tray ladder rung, causing damage to a cabic in contact with the rung. The ingress of the heptane into the ceramic fiber needs to be further evalusted since this appears to be the most significant failure mode.
4 November 6, 1978 IE Circular 78-18 Tentative Conclusions The test results are still being analyzed, and it would be premature to establish firm conclusions at this time; however, the results now available indicate that the following areas of the fire protection prograe need close consideration:
- 1. To protect against spills of flammable J'. quids, barriers or curbs may be needed to prevent entry of the flammable liquid behind fire barrietc. A wick effect may also need to be considered in the design of fire barriers.
- 2. Some small fires may not actuate sprinkler heads. To reduce this possibility in sprinkler systems to be installed, fast response sprinkler heads should be considered (less than approximately 3 minutes in the L't Standard 199 " Automatic Sprinklers for Fire Protection Service").
- 3. The location of the fire detection devices and the sprinkler heads relative to the fire and components being protected is of great importance. The path of the air movement in the area influences the actuation of such devices and should be considered in the system layout.
The final results of this test will be issued when the analysis of the test is complete.
This circular is being issued for information only. No specific action is requested and no written response is required. If you desire addi-tional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
Attachments:
- 1. Figure 1
- 2. Figure 2
IE Circular No. 78-18 November 6, 1978 LISTING OF IE CIRCULARS ISSUED IN 1978 Circular Subject 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 011 4/20/78 All Holders of for Terry Turbines Reactor OLs or cps 78-03 Packaging Creater Than 5/12/78 All Holders of Type A Quantities of Reactor OLs, cps, Low Specific Activity Fuel Cycle, Radioactive Material Prierity I Material for Transport and Waste Disposal Licenses l
l 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 er 25000 Hydraulic Test cps Stand 78-08 Environmental Qualification 5/31/78 All Holders of of Safety Related Equipment Reactor OLs or cps at Nuclear Power Plants 78-09 Arcing of General Electric 6/5/78 All Holders of cps Company Size 2 Contactors Enclosure Page 1 of 2
s IE Circular No. 78-18 November 6, 1978 LISTING OF IE CIRCULARS ISSUED IN 1978 Circular Subject Date of Issued to No. Issue 78-30 Control of Sealed 6/14/78 All Medical Sources Used in Licensees in Radiation Therapy Categories C and C1 78-13 Recirculation M-C 6/15/78 All Holders of Set Overspeed Stops BW. Ot s or CP s 78-12 HPCI Turbine Control 6/30/78 All Holders of Valve Lift Rod Bending B'a'R OL s o r CP s 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, AM, CA, FL, CA, LA, VS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of BW Chamber Hold Down Bolting OLs or cps for plants with a HPCI Terry Turbine except ing Duane Arnold and Monticelle 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 ,;, ,
Actuators Reactor OLs or cps
.]
78-17 Inadequate Guard Training / 10/13/78 All Holders of Qualification and Falsified and applicants l Training Records for Reactor OLs.
Enclosure Page 2 of 2 l
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