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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20235B3081987-09-21021 September 1987 Responds to FOIA Request for Documents,Including AEC to ACRS Forwarding Safety Evaluation Re Zimmer.App a Documents Cannot Be Located.App B Documents in Pdr.App C & D Documents Withheld (Ref 10CFR2.790) ML20235M4251987-07-13013 July 1987 Partial Response to FOIA Request for Documents Re Acrs. Forwards Documents for Categories One & Three of FOIA Request.Review of 21 Addl ACRS Documents Continuing ML20126L3111985-07-22022 July 1985 Provides Further Update to 840330 Submission Re Soil Erosion Control & Stabilization Projects Per Insp Rept 50-363/80-02. Revegetation of Banks of Oyster Creek Divided Into Two Portions,W/Eastern Portion Completed in 1984 ML20087P5531984-04-0202 April 1984 Forwards Responses to 840307 Questions Re full-term OL Conversion Environ Review. Effects of Salt Drift on Land Dwelling Vertebrates & Terrestrial Environ Program Annual Rept,Mar 1978 - Feb 1979 Encl ML20084M2941984-03-30030 March 1984 Updates 820728 Response to NRC Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions: Stabilization & Revegetation of Dredge Spoil Slope North of Firepond Completed on 830615 ML20077J0861983-07-20020 July 1983 Forwards Amended Complaint Filed in New Jersey Middlesex Superior Court by Jf Laird,Et Al & Companion Suit Filed by M Ginda & B Keene,Et Al Re Alleged Injuries Resulting from Identical Radiation Exposures ML20083P0791983-01-20020 January 1983 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Soil Erosion Control Project at Barge Unloading Facility Completed ML20076B8331982-10-0404 October 1982 Forwards Info Resolving 14 Tech Spec Open Items Discussed at 820913 meeting.Marked-up Tech Specs Encl IR 05000363/19800021982-08-0909 August 1982 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Rept 50-363/80-02 ML20062H7921982-07-28028 July 1982 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/82-02.Corrective Actions:Soil Stabilization Work Began 820504 & Should Be Complete by 820830 ML20004C7751981-04-23023 April 1981 FOIA Request for Psar,Drawings & Specs Re Facility ML20003G3121981-02-27027 February 1981 Responds to NRC 810203 Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Slope to Be Regraded & Contoured to Decrease Erosion Potential & Amount of Concentrated Rainwater Runoff Washing Slope ML20003A8131981-02-0505 February 1981 Submits Fee for Class III Request Re Delay on One Fire Protection Mod ML20003A9041981-02-0404 February 1981 Responds to NRC 810114 Ltr Re SEP Lead Topic Approach Proposed by SEP Owners Group.Licensee May Not Have Adequate Time to Comment on Safety Evaluation.Written Notification Will Be Provided to Request Addl Time ML19327A3271980-07-14014 July 1980 Informs That IE Bulletins,Circulars & Notices Requiring Review &/Or Response for Facility Are on Hold Due to Postponement of Const Activities.Current Action Files Maintained.Schedule of Responses Will Be Forwarded ML19309D0151980-04-0303 April 1980 Forwards Supplementary Financial Info in Support of TMI-1 Restart Proceedings ML20126D4901980-03-21021 March 1980 Responds to & 800104 Petition to NRC for Public Hearing Re Application for Extension of Cp.Opportunity for Public Hearing Should Be Afforded.Fr Notice of Opportunity Will Be Forwarded Upon Publication ML19320C8141980-03-11011 March 1980 Requests Documents Containing Info Needed for Fuel Cost Study ML19322E6141980-03-11011 March 1980 Responds to IE Bulletin 80-03 Re Visual Insps of Charcoal Adsorber Cells.Equipment of This Type Has Not Been Purchased to Date ML19296E0101980-03-0505 March 1980 Responds to IE Bulletin 79-28 Re Replacement of Top Cover Gaskets on Stem Mounted Limit Switches.Namco EA180 Switches Not Installed in safety-related Equipment Inside or Outside Containment.Assigned Electrical Equipment Being Purchased ML19294B1421980-02-20020 February 1980 Responds to NRC 791226 Ltr Re Estimated Evacuation Time for Plume Exposure Pathway Around Util.Evacuation Time Essentially Same as Oyster Creek,Submitted on 800131. Evacuation Time Estimate of 13.9-h Conservative ML19305C0101980-01-25025 January 1980 Opposes Protracted & Expensive Study of Jcp&L Financial Condition,W/Followup Hearings & Court Battles.Study Would Block Constructive Activity for Yrs.Consumers Will Pay for Delays.Ltr Dtd 800125 to Nj Ofc of Public Advocate Encl ML19257C1711979-11-28028 November 1979 Responds to NRC 791026 Ltr Re Violation Noted in IE Insp Rept 50-363/79-08.Corrective Actions:Venting of Air Bldg Per FSP-1-12,Revision 1,immediately Reinstituted.Field Personnel Instructed to Follow All Approved Procedures Until Revised ML19256F2701979-11-14014 November 1979 Responds to IE Bulletin 79-25, Reactor Trips at Turkey Point Units 3 & 4. No Electrical Equipment Purchased W/ Installed Westinghouse Bfd Relays.Will Request Ae to Identify Type Relays If Bfd Relays Selected ML19256E8251979-11-0707 November 1979 Requests Expansion of Environ Monitoring Program to Include Intensive Mortality Studies of Impinged & Entrained Organisms & Reduced Efforts Re Species Composition & Abundance Sampling ML19210D7121979-10-22022 October 1979 Responds to IE Bulletin 79-24, Frozen Lines. Heat Tracing & Freeze Protection Sys Design Incomplete ML19309H0281979-10-22022 October 1979 Requests Info Re Encl Freeholder RA Gasser 791009 Ltr Discussing s Van Ness Request to Suspend CP ML19254E8341979-09-28028 September 1979 Responds to IE Bulletin 79-23.Emergency Diesel Generator Field Exciter Transformer Not Yet Purchased.When Equipment Is Purchased,Util Will Ensure Design & Testing Meets Items 1 & 2 of Bulletin ML19254D1331979-09-27027 September 1979 Notifies That De Facto Continuation of CP Has Served to Exempt Facility from Complying W/Most up-to-date Safety Sys. Requests Public Hearings Re Safety Issues & Financial Qualifications ML19249D8641979-09-20020 September 1979 Responds to 790821 Ltr Re QA Program for Preservation of safety-related Equipment,Components & Structures During Suspension of Const Activities.Program Will Be in Accordance W/General Requirements of QA Plan ML19254E0631979-09-20020 September 1979 Responds to NRC 790823 Ltr Re Violations Noted in IE Insp Rept 50-363/79-07.Corrective Actions:Preventative Svc & Storage Program Procedures & QA Surveillance Program Procedures Revised ML19249D5201979-08-24024 August 1979 Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Facility Design Currently Employs Vertical Turbine Pumps in Nuclear Svc Water Sys only.As-built Vendor Data Not Yet Available ML20126C5091979-08-16016 August 1979 Opposes Restart of TMI-1,const of Nuclear Plants in Nj & Nuclear Accidents Due to Health Hazards & Risks to Public Safety ML19242A7021979-07-30030 July 1979 Requests Deferment of NRC Action on 780831 Request for Extension of Facility Completion Date.Financial Effects Stemming from TMI-2 Incident Will Preclude Recommencement of Const ML19249A4981979-07-30030 July 1979 Responds to IE Bulletins 79-02 & 79-02 Revision 1,re Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.Pipe Support Base Plate Designs Are Not in Use at Plant ML19242C7061979-07-30030 July 1979 Responds to IE Bulletin 79-14 Re Seismic Analysis for as-built safety-related Piping Sys.No safety-related Piping Sys at Plant ML19225A8601979-07-13013 July 1979 Confirms 790713 Telcon Requesting Summary of NRC Meeting W/Util Re Renewal of Facility CP ML19242B2051979-06-29029 June 1979 Forwards C-E 790608 Ltr Responding to IE Bulletins 78-12, 12A & 12B Re Atypical Weld Matl in Reactor Pressure Vessel Welds ML19242B2921979-06-25025 June 1979 Responds to IE Bulletin 79-11 Re Use of Westinghouse DB-50 & DB-75 Circuit Breakers in safety-related Sys.No Circuit Breakers of This Type Have Been Purchased ML19242B2141979-06-0808 June 1979 Forwards C-E Rept, Info Requested by IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, & Certification That All Matls Used in Reactor Vessel Fabrication Are Discussed in Rept ML19241A7901979-06-0606 June 1979 Responds to IE Bulletin 79-07.Version of Adlpipe Computer Program Which Includes Algebraic Summation Technique Has Been Used for Final Design of Support for Containment Spray Sys ML19246B9371979-06-0606 June 1979 Partially Responds to IE Bulletin 78-12B Re Atypical Weld matl.C-E Will Submit Generic Rept to NRC by 790608.Final Response Will Be Provided by 790629 ML19242B4201979-05-29029 May 1979 Responds to IE Bulletin 79-03 Re Weld Defects in 304 or 312 Stainless Steel Pipe Spools.Spools Used in Containment Penetrations M-43 & M-44.Corrective Actions:Welds Radiographed & Defects Repaired ML19289F4581979-05-0101 May 1979 Responds to IE Bulletin 79-04.Swing Check Valves Not Installed in Facility ML19289F4571979-05-0101 May 1979 Responds to IE Bulletin 79-09.No GE Type AK-2 Circuit Breakers Purchased to Date ML19289F6141979-04-20020 April 1979 Responds to NRC 790312 Ltr Re Violations Noted in IE Insp Rept 50-363/79-02.Corrective Actions:Initiation of Program for Daily Monitoring of Equipment Pressurized W/Inert Gas ML19256F4131979-04-0909 April 1979 Notifies of Concern Over Use of Nuclear Generation & Operating Similarities in Design of TMI-2 & Other Nuclear Units.Requests Meeting W/Nrc to Identify Strategy to Reduce Probability of TMI-incident at Facility ML19289F2061979-03-15015 March 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Rept 50-363/78-15.Corrective Actions:Theodolite Was Serviced & Two Tachometers Sent for Recalibr ML20104A7271979-03-0505 March 1979 Forwards Design Info,Submittal 2,Structural Reorientation, W/Current Design Features Reflecting New Licensing Concerns of post-CP Period 1999-06-25
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000363/19800021982-08-0909 August 1982 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Rept 50-363/80-02 IR 05000363/19780121978-11-29029 November 1978 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted During Inspec 50-363/78-12. W/Encl ANO:7812120241,7812120245 & 781212048 ML20147B1631978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20148R5681978-11-16016 November 1978 Lists Staff Review Categories 2,3 & 4 for Consideration in Preparation of FSAR & Lic Review.W/Encl Descriptions of Categories 2,3 & 4 ML20204C3641978-11-0606 November 1978 Forwards IE Circular 78-18,UL Fire Test.W/Encl ANO: 7811150002 ML20150B6591978-10-16016 October 1978 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted During Inspec 50-363/78-10 ML20204B1841978-09-29029 September 1978 Forwards IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds. Action Requested in 60 Days.List of Bulletins Issued in 1978 Also Encl ML20148A0161978-09-12012 September 1978 Forwards Insp Rept 50-363/78-11 on 780829-30.No Noncompliance Noted ML20150B6841978-08-22022 August 1978 Forwards IE Inspec Rept 50-363/78-10 on 780808-09 & Notice of Violation 1982-08-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20235B3081987-09-21021 September 1987 Responds to FOIA Request for Documents,Including AEC to ACRS Forwarding Safety Evaluation Re Zimmer.App a Documents Cannot Be Located.App B Documents in Pdr.App C & D Documents Withheld (Ref 10CFR2.790) ML20235M4251987-07-13013 July 1987 Partial Response to FOIA Request for Documents Re Acrs. Forwards Documents for Categories One & Three of FOIA Request.Review of 21 Addl ACRS Documents Continuing IR 05000363/19800021982-08-0909 August 1982 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Rept 50-363/80-02 ML20126D4901980-03-21021 March 1980 Responds to & 800104 Petition to NRC for Public Hearing Re Application for Extension of Cp.Opportunity for Public Hearing Should Be Afforded.Fr Notice of Opportunity Will Be Forwarded Upon Publication IR 05000363/19780121978-11-29029 November 1978 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted During Inspec 50-363/78-12. W/Encl ANO:7812120241,7812120245 & 781212048 ML20147B1631978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20148R5681978-11-16016 November 1978 Lists Staff Review Categories 2,3 & 4 for Consideration in Preparation of FSAR & Lic Review.W/Encl Descriptions of Categories 2,3 & 4 ML20204C3641978-11-0606 November 1978 Forwards IE Circular 78-18,UL Fire Test.W/Encl ANO: 7811150002 ML20150B6591978-10-16016 October 1978 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted During Inspec 50-363/78-10 ML20204B1841978-09-29029 September 1978 Forwards IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds. Action Requested in 60 Days.List of Bulletins Issued in 1978 Also Encl ML20148A0161978-09-12012 September 1978 Forwards Insp Rept 50-363/78-11 on 780829-30.No Noncompliance Noted ML20150B6841978-08-22022 August 1978 Forwards IE Inspec Rept 50-363/78-10 on 780808-09 & Notice of Violation 1987-09-21
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UNITED STATES gf
,,* 9 p* *'00,7'g NUCLEAR REGULATORY COMMISslON
.~f;. REGION 1
- g 631 PARK AVENUE KING OF PAUSSI A, PENNSYLVANI A 19406 November 6, 1978 Docket No. 50-363 i
E Jersey Central Power & Light Company ATTN: Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Gentlemen:
The enclosed IE Circular No. 78-18 is forwarded to you for informa-
. tion. No specific action is requested and no written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Y
Boyce H. Grier
!n
)
[" Director 1 l
Enclosures:
- 1. IE Circular No. 78-18 l
- 2. List of IE Circulars Issued in 1978 cc w/encls: ,
M. K. Pastor, Project Manager l l
l
'I 7811290/fd
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 IE Circular 78-18 Date: November C, 1978 Page 1 of 3 UL FIRE TEST Background i 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 flamable 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 manufacturer's recommendations. The sprinkler and detector arrangement was as permitted by NFPA Code. Hewever, 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 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.
l l
IE Circular 78-18 Date: November 6, 1978 Page 2 of 3 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 inmediately. 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.
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 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 evaluated since this appears to be the most significant failure mode.
IE Circular 78-18 Date: November 6, 1978 Page 3 of 3 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 program need close consideration:
- 1. To protect against spills of flammable 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
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 (CP) 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 Damaged 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
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 cf General Electric 6/8/78 All Power Reactor Facilities with an Company NEMA Size 2 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 78-15 Tilting Disk Check 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,
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Records Shoreham, and Salem 2