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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20202D4861998-02-12012 February 1998 Ack Receipt of & Check in Amount of $55,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insps IR 05000485/19960241997-03-0505 March 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/96-24 IR 05000485/19850711986-06-17017 June 1986 Ack Receipt of 851204 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/85-71 ML18037A3791982-05-27027 May 1982 Forwards Annual Financial Repts 1981 for Niagara Mohawk Power Corp,Ny State Electric & Gas Corp,Lilco,Rochester Gas & Electric Corp & Central Hudson Gas & Electric Corp ML17258A1861981-09-22022 September 1981 Forwards Endorsements 73 & 74 to ANI Policy NF-170 ML20003G2671981-04-22022 April 1981 Forwards Second Draft Safety Evaluation of Snupps 10.1,10.2, 10.3,10.4.1 & 10.4.4, Steam & Power Conversion Sys. ML17258A7951981-02-10010 February 1981 Forwards Summary of Actual Cash Flow for 1980,projected Cash Flow for 1981 & Financial Statement for 3 & 12 Months Ended 801231.Info Supports Util Guarantee to Pay Retrospective Premiums Required by Secondary Financial Protection Sys ML17258A7371981-01-14014 January 1981 Forwards Public Version of Upgraded Evacuation Time Estimates for Facilities in Response to NRC 801209 Ltr ML17250A7161980-10-29029 October 1980 Informs of Changes in Organizational Structure Per FE Drake Retirement as Board Chairman & Chief Executive Officer. Corporate Organization Chart,Effective 801001,encl ML19338C4601980-08-11011 August 1980 Requests Info Re Basis for Denial of Certificate for Facility ML19320A5831980-06-16016 June 1980 Responds to IE Bulletin 80-09, Hydramotor Actuator Deficiencies. Two safety-related Uses of Itt General Controls Models AH-90 & NH-90 Series Hydramotor Actuators Have Been Identified.Itt Is Testing Actuators ML17250A3321980-06-12012 June 1980 Comments on 800506 Presentation to NRC Commissioners Re Status of SEP & Description of Difficulty as Lack of Aggression by Licensees.Nrc Has Not Provided Guidelines. Issues W/Higher Priorities Have Arisen ML19323H2791980-06-0606 June 1980 Responds to IE Bulletin 80-05 Re Vacuum Condition Resulting in Damage to Chemical Vol Control Sys Holdup Tanks.Tank Damage Due to Vacuum Conditions Precluded by Design Provisions or Suitable Vent Connections ML19318C1861980-06-0202 June 1980 Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Top Cover Gaskets on Switches W/Applicable Date Codes Will Be Replaced on Valves Listed in Encl ML17249A9111980-04-30030 April 1980 Forwards Response to IE Bulletin 80-04. Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Flow Becomes Dominant Factor in Determining Duration & Magnitude of Steam Flow Transient ML20003H9601980-04-18018 April 1980 Advises That Licensee Considers 800320 Deficiency Rept Final.No Addl Action Planned Unless Required by New Info ML19309G0821980-03-20020 March 1980 Responds to IE Bulletin 80-03 Re Charcoal Tray Adsorber Cells.Design & Manufacturer of Adsorber Cells Planned to Be Used Are Different than Type Described in Bulletin ML19305C3721980-03-20020 March 1980 Informs That Snupps Utils Are Investigating Hardware Changes to Preclude Need for Tests to Correct Deficiency in Engineered Safety Features Actuation Sys.Tests Will Be Made Part of Plant Procedures If Changes Are Not Feasible ML19305D5111980-03-20020 March 1980 Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Utils Are Investigating Hardware Changes That May Preclude Further Testing,Provided That Changes Are Feasible.Otherwise,Tests Will Continue ML19305C3751980-03-20020 March 1980 Informs That C-E 791026 Amend to Rept on IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, Should Be Considered Part of Util Bulletin Response ML19323D2451980-03-20020 March 1980 Responds to IE Bulletins 78-12,12A & 12B, Atypical Weld Matl in Reactor Pressure Vessel Welds. Util 790629 Ltr & C-E 791026 Ltr to NRC Constitutes Response to Bulletin ML19323C4271980-03-0606 March 1980 Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Identification of Switches Has Required More Time than Anticipated.Util Will Respond as Soon as Possible ML19309D3451980-03-0606 March 1980 Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches,Identification in Snupps Design & Development of Plans for Corrective Action Requires More Time than Anticipated.Will Forward Response Later ML19294B1451980-02-22022 February 1980 Disagrees W/Nrc Plans Re ATWS Issue.New Plans May Not Serve Best Interests of Public Health & Safety.Nrc Should Not Impose Requirements Before Thorough Review of Mass of Technical Info Supplied Last Year ML19296C5711980-02-19019 February 1980 Responds to NRC 800204 Ltr Received 800213 Re NRC 800208 Meeting W/Snupps Representatives to Discuss Snupps QA Program.Requests NRC Reschedule Meeting & Provide State Public Svc Commission Sufficient Time to Participate ML19294B8661980-02-14014 February 1980 Forwards Ny State Board on Electric Generation Siting & Environ 800211 Opinion & Order Vacating Previously Granted Certificate.Denies Application & Closes Proceeding ML19260D5621980-02-0505 February 1980 Forwards Supplemental Deficiency Rept Re Qualification of Control Sys ML19309B5491980-02-0505 February 1980 Forwards Supplemental Rept on Potential Deficiency Re Qualification of Control Sys Discussed in Util 790928 Ltr.No Unresolved Safety Concerns Re Pressure Controllers & Main Steam Line Atmospheric Relief Valve ML19296D9961980-02-0101 February 1980 Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches for Snupps Facilities Not Complete.Investigation Results & Corrective Actions Will Be Submitted in 3-4 Wks ML19294B1891980-01-30030 January 1980 Notifies That Ny State Board on Electric Generation Siting & Environ Voted on 800123 to Rescind Approval of Plant Const & Operation.No Decision Can Be Made Re Continuation of NRC Proceedings Until Util Has Received Formal Opinion ML19260E0561980-01-30030 January 1980 Notifies of Ny State Board on Electric Generation Siting & Environ 800123 Decision to Rescind Prior Approval of Const & Operation of Facility.No Date Set for Formal Opinion. Certificate of Svc Encl ML19296B9801980-01-18018 January 1980 Forwards RO Pohl Testimony on Radon Emissions from U Mill Tailings Piles ML19308C9981980-01-18018 January 1980 Responds to IE Bulletin 79-25.Westinghouse Bfd/Nbfd Relays Are Not Included in safety-related Portions of Design ML19211D2751980-01-14014 January 1980 Discusses NRC Delay in Review of FSAR & OL Application. Review Schedule Should Be Established Promptly ML19257B8871980-01-0404 January 1980 Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Such Relays Have Been Identified.Will Advise Further in Two Wks ML19291C3061980-01-0303 January 1980 Responds to IE Bulletin 79-02,Revision 2.Initial Response Satisfies Requirements of Revision 1.Facility Does Not Use Concrete Expansion Anchor Bolts to Support Seismic Category I Piping ML19296D7051980-01-0303 January 1980 Responds to IE Bulletin 79-02,Revision 1.Initial 790705 Response Resolves NRC Concerns Re Use of Concrete Expansion Anchor Bolts for Pipe Support Base Plates.Util Does Not Use Expansion Anchors in Concrete or Structural Steel Members ML19262C4241980-01-0303 January 1980 Responds to IE Bulletin 79-02,Revision 2, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. Expansion Anchors in Concrete Block Walls Not Used.Util 790705 Response Need Not Be Modified or Amended ML17249A4551980-01-0202 January 1980 Supplements 791212 Ltr Listing Six Suits Against Util. Seventh,Ew Garrett Vs Util,Received ML19262B5671979-12-20020 December 1979 Responds to NRC 791018 Request for Addl Info Re Snupps Fire Protection Sys.Detailed Responses to Requests Will Be Included in FSAR Revision.Clarification of Sys Description Will Show Design in Compliance W/Nrc Requirements ML19262B5831979-12-14014 December 1979 Discusses Potential Deficiency,Per 791116 Telcon to Nrc. Westinghouse Review Reveals That Dropped Rod Safety Analysis Deficiency May Affect Four Addl Loop Plants.Further Info Will Be Provided by FSAR Revision ML19253C9361979-12-0606 December 1979 Notifies of Corrective Action for Potential Deficiency Re Engineered Safety Features Actuation Sys.Test Sequence to Detect Failure Will Be Incorporated Into Appropriate Procedures ML19260C9481979-11-29029 November 1979 Forwards Final Deficiency Rept Re Gulf & Western Preassembly Formations ML19305B9591979-11-0707 November 1979 Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Failure of P-4 Permissive Circuit in Both Redundant Protection Trains Could Result in Failure of Sys to Automatically Initiate Protective Function.Details Encl ML19210C1331979-11-0707 November 1979 Confirms That Snupps FSAR Should Be Considered Tendered by Util.Snupps FSAR Will Be Incorporated by Formal Amend to License Application ML19211A4241979-11-0101 November 1979 Submits Generic Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Seismic Analysis Input Info Conforms to Actual as-built Configuration of safety-related Sys ML19254F2061979-11-0101 November 1979 Requests NRC Concurrence on Usage of ASME Section III Code Case N-240, Hydrostatic Testing of Open-Ended Piping, Section Iii,Div 1. ML19253C5961979-10-26026 October 1979 Responds to IE Bulletin 79-23 Re Potential Failure of Emergency Diesel Generator Field Exciter Transformer.Problem Not Applicable to Snupps Diesel Generators ML20125B3041979-10-18018 October 1979 Forwards Request for Addl Info Re QA Aspects of Fire Protection Sys for Snupps Portion of Facilities ML19253C7981979-10-15015 October 1979 Forwards Interim Deficiency Rept Re Qualification of Control Sys.Supplemental Rept in Approx Three Months 1998-02-12
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000485/19850711986-06-17017 June 1986 Ack Receipt of 851204 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/85-71 ML20125B3041979-10-18018 October 1979 Forwards Request for Addl Info Re QA Aspects of Fire Protection Sys for Snupps Portion of Facilities ML20062H0921979-03-19019 March 1979 Forwards IE Bulletin 78-12B, Atypical Weld Matl in Reactor Pressure Vessel Welds ML20062F1351978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20062E4211978-11-21021 November 1978 Notice of Seminar on 781208 on New Model Radiological Effluent Tech Specs for Nuc Pwr Plants.Requests Advance Submission of Seminar Specific Questions.W/Encl Seminar Info Sheet,Proposed Agenda & Maps ML20062G5591978-11-15015 November 1978 Forwards IE Inspec Rept 50-485/78-01 on 781023-25 During Which No Items of Noncompliance Were Noted ML20062D7021978-11-0606 November 1978 Forwards IE Circular 78-18,UL Fire Test.W/Encl ANO: 7811150002 ML20062A6421978-09-29029 September 1978 Forwards IE Bulletin 78-12 Atypical Weld Matl in Reactor Pressure Vessel Welds Requesting Action in 60 Days.List of Bulletins Issued in 1978 Encl 1986-06-17
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20202D4861998-02-12012 February 1998 Ack Receipt of & Check in Amount of $55,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insps IR 05000485/19960241997-03-0505 March 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/96-24 IR 05000485/19850711986-06-17017 June 1986 Ack Receipt of 851204 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/85-71 ML20125B3041979-10-18018 October 1979 Forwards Request for Addl Info Re QA Aspects of Fire Protection Sys for Snupps Portion of Facilities ML20062H0921979-03-19019 March 1979 Forwards IE Bulletin 78-12B, Atypical Weld Matl in Reactor Pressure Vessel Welds ML20062G1631978-12-12012 December 1978 Ack Ltr of 781207 Forwarding Petition for Review of Decision ALAB-507.Ltr & Petition Are Being Forwarded by Aslab to Comm for Latter'S Consideration ML20062F1351978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20062E4211978-11-21021 November 1978 Notice of Seminar on 781208 on New Model Radiological Effluent Tech Specs for Nuc Pwr Plants.Requests Advance Submission of Seminar Specific Questions.W/Encl Seminar Info Sheet,Proposed Agenda & Maps ML20062G5591978-11-15015 November 1978 Forwards IE Inspec Rept 50-485/78-01 on 781023-25 During Which No Items of Noncompliance Were Noted ML20062D7021978-11-0606 November 1978 Forwards IE Circular 78-18,UL Fire Test.W/Encl ANO: 7811150002 ML20062A6421978-09-29029 September 1978 Forwards IE Bulletin 78-12 Atypical Weld Matl in Reactor Pressure Vessel Welds Requesting Action in 60 Days.List of Bulletins Issued in 1978 Encl 1998-02-12
[Table view] |
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. ,- . l s.Smafoo, UNITED STATES
+ %, NUCLEAR REGULATORY COMMISslON
,'i 7I E REGION 1 3 35 -
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C 631 PAR K AVENUE KING OF PRUS$1 A, PENNSYLVANI A 19404
..... 1 November 6, 1978 Docket No. 50-485 Y U
Rochester Gas & Electric Corporation ATTN: Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, NY 14649 Gentlemen:
The enclosed IE Circular No. 78-18 is forwarded to you for informa-tion. No specific action it requested and no written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
,/ M-oyce H. Grier Director
Enclosures:
- 1. IE Circular No. 78-18
- 2. List of IE Circulars Issued in 1978 cc w/encls:
C. R. Anderson, Manager, QA Lex K. Larson, Esquire N. A. Petrick, Executive Director, SNUPPS Gerald Charnoff, Esquire 7811290/9Y 6'
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 IE Circular 78-18 Date: November 6, 1978 Page 1 of 3 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 salected 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 manufacturer's recommendations. The sprinkler and detector arrangement was as permitted 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. After all three temperature 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 slow end of acceptance for reaction time. The test procedure required that all
"ee 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.
'l 1
IE Circular 78-18 Date: November 6, 1978 Page 2 o? 3 i
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 aln.ast imediately. 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 seemed 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.
Preliminary Results and Analyses Preliminary information indicates that the flammable 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.
l 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 vapor / air path within 4
the joints. There is some indication that some cable damage was caused by absorption of heptane on the inside of the barrier (wicking effect) and its ignition which heated a cable tray ladder rung, causing damage
! to a cable in contact with the rung. The ingress of the heptane into the ceramic fiber needs to be further evaluatad since this appears to be the most significant failure mode.
, . _ _ - _ _ __ , _ _ .._m - _-, _ _ m
IE Circular 78-18 Date: November 6, 1978 Page 3 of 3 i
Tentative Conclusions l'
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 program need close consideration:
- 1. To protect against spills of flamable liquids, barriers or curbs may be needed to prevent entry of the flammable liquid behind fire barriers. 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 UL Standard 199 " Automatic Sprinklers for Fire ProtectionService").
- 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
. . l IE Circular No. 78-18 Date: November 6, 1978 Page 1 of 2 ENCLOSURE 2 LIST OF IE CIRCULARS ISSUED IN 1978 Circular Subject First Date Issued To No. of Issue 78-01 Loss of Well Logging 4/14/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating 011 4/20/78 All Power Reactor for Terry Turbines Facilities with an Operating License (0L) or Construction Permit (CD) 78-03 Packaging Greater Than 5/12/78 All Power Reactor Type A Quantities of Facilities with an Low Specific Activity OL or CP; and all Radioactive Material Fuel Cycle, Priority I for Transport Materials and Waste Disposal Licensees 78-04 Installation Errors That 5/18/78 All Power Reactor Could Prevent Closing Facilities with an of Fire Doors OL or CP 78-05 Inadvertent Safety 5/26/78 All PWR Power Injection During Reactor Facilities Cooldown with an OL or CP 78-06 Potential Common Mode 5/31/78 All Power Reactor Flooding of ECCS Facilities with an Equipment Rooms at OL or CP BWR Facilities 78-07 Daraged Components on a 5/31/78 All Power Reactor Bergen-Paterson Series Facilities with an 25000 Hydraulic Test Stand OL or CP 78-08 Environmental Qualifica- 5/31/78 All Power Reactor tion of Safety-Related Facilities with an Electrical Equipment at OL or CP Nuclear Power Plants i
IE Circular No. 78-18 '
Date: November 6, 1978 Page 2 of 2 ENCLOSURE 2 (Continued)
LIST OF IE CIRCULARS ISSUED IN 1978 Circular Subject First Date Issued To No. of Issue 78-09 Arcing of General Electric 6/8/78 All Power Reactor Company NEMA Size 2 Facilities with an Contactors OL or CP 78-10 Control of Sealed Sources 6/14/78 All Institutional Used in Radiation Therapy Medical Licensees 78-11 Recirulation M-G Set 6/15/78 All BWR Power Reactor Overspeed Stops Facilities with an OL or CP 78-12 HPCI Turbine Control 6/30/78 All Power Reactor Valve Lift Rod Facilities with an Bending OL or CP having a HPCI Terry Turbine 78-13 Inoperability of 7/10/78 All Power Reactor Multiple Service Facilities with an Water Pumps OL or CP 78-14 HPCI Turbine Re- 7/17/78 All Power Reactor versing Chamber Facilities with an Hold Down Bolting OL or CP having a HPCI Terry Turbine excepting Duane Arnold and Monticello Tilting Disk Check 78-15 7/24/78 All Power Reactor Valves Fail to Close Facilities with an with Gravity in Vertical OL or CP Position 78-16 Limitorque Valve 7/26/78 All Power Reactor Actuators Facilities with an OL or CP 78-17 Inadequate Guard 10/13/78 - All Power Reactor Training / Qualification Facilities with an and Falsified Training OL; Susquehanna 1 & 2, Records Shoreham, and Salem 2