|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20149G9861994-11-0404 November 1994 Special Rept:On 941006,Unit 1 Fuel Storage Pool Conductivity Exceeded 10 Micro/Mho/Cm TS Limit & Returned to within TS on 941010.Caused by Decomposition of Biological micro-organisms in Fuel Storage Pool.Temporary Demineralizer Restarted ML20069E5351983-03-15015 March 1983 RO 83-014:on 830219,contaminated Demineralized Water Released Into Condenser,Allowing 0.7 Mci to Steam Out of Vent.Caused by Personnel Error.Operator Opened Valve MO-3-1301-10 Instead of Valve MO-3-4399-74 ML20069A3561983-03-0909 March 1983 RO 83-016:on 830207,contaminated Water from Drain & Refill of 2/3A Heating Boiler Inadvertently Released to Storm Sewer Sys.Caused by Operator Not Realizing Floor Drain Led to Storm Sewer Sys,Not Radwaste Sys.Tech Specs Not Violated ML20054F7971982-06-0909 June 1982 RO 82-027:on 820511,excessive Radioactive Contamination Identified in Two Areas of Offsite Dump.Caused by Inadequate Control of Dump Access & Failure to Survey Large Loads of Matl Thoroughly.Area Cleaned Up & Procedure 12-5 Revised ML20084R9011977-03-23023 March 1977 Telecopy Ro:On 770322,while Completing Operability Surveillance Following Maint on Sys Air Compressors,Diesel Generator Field Failed to Flash & Diesel Generator 2/3 Failed to Start on First Attempt.Cause Unknown ML20084A0611976-12-20020 December 1976 Telecopy Message of Ro:On 761220,empty Spent Fuel Cask Areas Found W/Removable Contamination ML20084L7821976-12-15015 December 1976 RO 50-237/1974-27A update.Three-yr Study of Use of phosphorus-bronze in Place of Teflon as Bushing Matl in torus-to-drywell Vacuum Breakers Provides No Justification for Replacement of Teflon Bushings ML20084A0991976-12-15015 December 1976 Telecopy Message of Ro:On 761215,4% Reduction Made in Allowable Maplhgr.Caused by Error in GE ECCS Analysis ML20084A2151976-12-13013 December 1976 RO 50-237/76-66:on 761113,HPCI Sys Injection Valve 2-2301-8 Failed.Valve Repairs to Be Completed at Next Outage ML20084A1391976-12-0606 December 1976 Telecopy Message of Ro:Empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084A1811976-12-0202 December 1976 Telecopy Message of Ro:On 761202,empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084R9111976-11-19019 November 1976 Telecopy Ro:On 761119,potential HPCI Design Error Discovered Which Could Cause Failure of HPCI Valve MO3-2301-8 During Certain Postulated Conditions.Caused by Design Wiring Problem.Valve Placed out-of-svc in Open Position ML20084R9181976-09-20020 September 1976 Telecopy Ro:On 760914,during Reactor Power Operation, Primary Containment Oxygen Content Found Greater than 4%. Caused by Terminated Unit Shutdown After Sys Min Load Problems Developed ML20084R5841976-06-15015 June 1976 Suppl Rept to ROs 50-249/75-10A,11A & 33A:motors Replaced on Valves 3-1402-4A & 3-1501-5A & Original Motors Sent to Manufacturer for Evaluation.Valve Trips Occurred Due to Undersized Overload Heaters.Mods Initiated ML20090E3751976-03-25025 March 1976 Telecopy Ro:On 760325,through-wall Crack Indication Found on HPCI Steam Supply Line safe-end.Cause Not Stated ML20084S0111976-03-0303 March 1976 Telecopy Ro:On 760303,emergency Electrical Feed to 2/3 Standby Gas Treatment Sys B Unavailable While Sys a out-of- Svc for Filter Replacement.Caused by Diesel Generator out- of-svc Due to Loose Connection in Manual Control Circuit ML20084R9381976-02-18018 February 1976 Follow-up RO 50-249/74-29A:on 740924,through-wall Crack Discovered on Torus/Drywell Purge Line.Probably Caused by Slight Preloading,Resulting in Strain on Piping.Pipe Examined for Other Cracks & Repair Program Initiated ML20084N6301975-12-0808 December 1975 Telecopy Ro:On 751208,Bergen-Patterson Piping Restraint on Cleanup Sys 8-inch Supply Line Inside Drywell Failed Due to Loss of Hydraulic Fluid.Caused by Faulty Zirc Fitting.Zirc Fitting Replaced ML20084N6411975-12-0404 December 1975 Telecopy Ro:On 751204,intermediate Range Monitor 12 Instrument Setpoint Drifted Above Tech Spec Limit.Setpoint Corrected ML20084N6641975-12-0202 December 1975 Telecopy Ro:On 751201,offgas Activities Increased During Steady State Operations.Probably Caused by Fuel Degradation. Testing in Progress ML20090E4351975-11-17017 November 1975 Telecopy Ro:On 751116,quarterly Closure Time of IC MSIV Found Below Tech Spec Limit.Valve Repaired ML20090E4381975-11-0303 November 1975 Telecopy Ro:On 751103,torus Level Exceeded Tech Spec Limits. Caused by Water Being Pumped from Storage Tank to Torus During HPCI Surveillance Check ML20084N6691975-10-17017 October 1975 Ro:On 751008,portable Fuel Loading Chamber Containing 2 G SNM Declared Lost.Caused by Lack of Proper Storage.Rev of Nuclear Procedures Will Be Initiated ML20084N6791975-09-29029 September 1975 Telecopy Ro:On 750928,leak Discovered in Feedwater Heater 3D3 Normal Drain Line at Weld Attachment to 4 Inch Pipe Support.Caused by Undercut Weld During Original Installation ML20090E4551975-09-29029 September 1975 Telecopy Ro:On 750929,pressurizing 21-2 D/W Went to 3 Psig. Caused by Excess Nitrogen Added Through Normally Closed Manual Bypass Valve ML20090E4521975-09-29029 September 1975 Telecopy Ro:On 750929,HPCI Turbine Failed to Shut Down. Caused by Damaged Trip Solenoid Coil ML20090E4721975-09-11011 September 1975 Telecopy Ro:On 750911,diesel Generator Cooling Water Pump Breaker on Bus 28-3 Tripped ML20084N7031975-09-0808 September 1975 Telecopy Ro:On 750908,five of Eight Intermediate Range Monitoring Instrument Channels Failed to Respond During Reactor Startup.Caused by Open Cables Due to Personnel Contact ML20090E4951975-09-0202 September 1975 Telecopy Ro:On 750830,diesel Generator Tripped,Following Generator Cooling Water Pump Failure.Investigation Continuing ML20084N8591975-08-28028 August 1975 Telecopy Ro:On 750828,scram Bypass Switches PS3-263-51A & 51B Showed Instrument Drift Above Allowable Limit.Probably Caused by Inactivity Due to Refueling Outage ML20084N8611975-08-28028 August 1975 Telecopy Ro:On 750826,pressure Switches PS3-263-53A,53B & 53C Drifted Above Tech Spec Limit.Probably Caused by Inactivity Due to Refueling Outage ML20084N8531975-08-28028 August 1975 Telecopy Ro:On 750826,isolation Condenser Pressure Switches PS3-263-53A,53B & 53C Setpoints Above Tech Spec Limit. Probably Caused by Setpoint Drift Due to Inactivity During Refuel Outage ML20084N7411975-08-28028 August 1975 Telecopy Ro:On 750828,reactor Pressure Scram Bypass Switches PS3-263-51A & 51B Drifted Above Tech Spec Limit.Caused by Inactivity of Switches During Refueling Outage ML20084N9011975-08-27027 August 1975 RO 50-249/75-33:on 750728,suction Valve for LPCI Pump MO-3-1501-5A Tripped Twice on Thermal Overload.Caused by Defective Motor.Motor Replaced ML20084N8021975-08-25025 August 1975 Telecopy Ro:On 750824,during Instrument Surveillance,Scram Switches PS3-263-55A,B & C Found to Have Drifted.Apparently Caused by Inactivity ML20084N8741975-08-21021 August 1975 Telecopy Ro:On 750821,main Feed Breaker to Bus 34-1 Failed to Trip During Trip Testing.Cause Not Stated.Investigation Underway ML20084N8901975-08-0808 August 1975 Telecopy Ro:On 750808,isolation Condenser Condensate High Flow Switches 3-1349A & 3-1349B Failed to Trip within Tech Spec Limit.Apparently Caused by Instrument Setpoint Drift. Switches Reset ML20084N9111975-07-22022 July 1975 Telecopy Ro:On 750722,location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers Determined During Tv Exam of Jet Pumps 6 & 17.Cause Not Stated.Tack Welds Will Be Rewelded Under Water ML20084N9471975-06-27027 June 1975 Telecopy Ro:On 750627,during Overhaul Operations,Cracks Found on Collet Housing Portion of Control Rod Drive Housing Outer Tube.Cause Not Stated.Control Rod Drive Manufacturer Contacted to Determine Extent of Problems ML20084N9841975-06-0505 June 1975 Telecopy Ro:On 750605,actuation of Standby Liquid Control Sys Pump Discharge Release Valve Below Tech Spec Limit. Caused by Procedural Inadequacy ML20084P8051975-06-0202 June 1975 Telecopy of Ro:On 750330,during Refueling Outage Surveillance,Excessive Leakage Through Primary Containment Feedwater Isolation Check Valves 3-220-58B & 3-220-62B Observed.Caused by Failed Valve Disc Seal ML20084D3501975-05-16016 May 1975 Telecopy Ro:From 750421-23,personnel Were within Line of Sight of Core During Rod Withdrawal.Caused by Personnel Error.Operation Terminated When Violation Became Known ML20084D3921975-05-0808 May 1975 Ro:On 750507,control Rod Drive Return Line Check Valve Failed to Pass Local Leak Rate Test.Valve to Be Repaired Prior to Startup ML20084R4041975-04-29029 April 1975 Telecopy Ro:On 750429,HPCI High Temp Isolation Switches Drifted During Operations Exceeding Tech Spec Limit.Caused by Drift of 12 Sensors Found During Refueling Outage.Sensors Will Be Replaced W/Capillary Type Switches ML20084R4061975-04-28028 April 1975 Telecopy Ro:On 750428,HPCI High Temp Isolation Switches Drifted During Operations,Exceeding Tech Spec Limit.Caused by Drift of 12 Sensors Found During Refueling Outage. Switches Will Be Replaced W/Capillary Type Switches ML20085J9881975-04-23023 April 1975 Telecopy Ro:On 750423,during Refuel Outage Surveillance, Feedwater Check Valves 3-220-58A & 62A & Feedwater Line 3A Failed to Pass Leak Rate Test.Cause Not Stated ML20084R4431975-04-17017 April 1975 Telecopy Ro:On 750417,main Steam Line D Drywell Penetration X105D Failed to Pass Containment Local Leak Rate Tests. Caused by Broken Testline Which Penetrates Bellows Type Penetration Between Primary & Secondary Bellows ML20084T0331975-04-0404 April 1975 RO 50-249/75-18:on 750324,during Surveillance Testing,Core Spray Valve 3-1402-4A Failed to Close Electrically.Caused by Fault in Motor Operator.Valve Closed Manually ML20084R5631975-04-0303 April 1975 ROs 50-249/75-18,17 & 16:on 750304,LPCI Valve 3-1501-5A Experienced Thermal Trip After Going Closed.Cause Unknown. Valve Returned to Open Position ML20084E0571975-03-21021 March 1975 Telecopy Ro:On 750319,field Failed to Flash on Diesel Generator While Trying to Return Generator to Svc.Cause Not Stated.Investigation in Progress 1994-11-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With ML20154L3681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20154N4131998-09-30030 September 1998 1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20153C5061998-09-21021 September 1998 SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1 ML20151Y2711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248M3021998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F3391998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20216E2531998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station ML20202F7831998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20198P5321997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station ML20198P7021997-12-31031 December 1997 Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept ML20203F8781997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station ML20199B0701997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station ML20217H7201997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual ML20216J3781997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for DNPS ML20210H5511997-07-31031 July 1997 Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02 1999-09-30
[Table view] |
Text
.
APR 8 1983
' Docket flos, 50-325/324 Mr. E. E. Utley Executive Vice President Carolina Power & Light Conpany P. O. Box 1551 Raleigh, North Carolina 27602
Dear Mr. Utley:
SUBJECT:
CLARIFICATION OF ENVIRONf1 ENTAL QUALIFICATION SAFETY EVALUATION Re: - Brunswick Steam Electric Plant, linits 1 and 2 On Decenber 20, 1982 the NRC staff issued a Safety Evaluation (SE) for Brunswick Stean Electric Plant, Units 1 and 2 on the environnental qualification of safety-related electrical equipnent. The SE was based on a Technical Evaluation Report (TER) prepared by our contractor, Franklin Research Center (Franklin).
Appendix D of the above TER provides a technical review of the licensee's state-nents regarding the justification for continued operation (JCO) that was sub .
nitted in the 90-day response to an earlier staff safety evaluation (published in mid-1981). Appendix D is not necessarily applicable to the deficiencies identified in the enclosed TER. You should review all JCOs subnitted to date to ensure that a JC0 exists for all equipnent which nay not be qualified.
The thirty (30) day response required by the current SE should address equipnent itens in NRC Categories I.b, II.a and IV (note that Category IV was not nentioned in the previous SE) for which justification for continued operation was not pre-viously subnitted to the NRC or Franklin. Guidelines for justification for continued operation are provided in paragraph (1) of 10 CFR 50.49. These guide-lines should be utilized in developinq your justification for continued operation.
'If your thirty (30) day response has already been subnitted to NRC, you are requested to review your response in accordance with this clarification and notify the NRC of any changes. The due date of these responses as stated in the above referenced SE are revised and are now due within thirty (30) days J$
geva.
of receipt of this letter.
The staff has developed a special procedure to address equipnent presented 3n in the TER which is classified as Category II.h (Equipment Not Qualified).
O These itens must be resolved as soon as possible. For the Category II.b N:s: itens, justification for continued operation nust be provided or the technical 88 issua, which has placed the equipnent in Category II.h nust be resolved within
@ ten (10) days of receipt of this letter. Should your plant have equipnent in
.e Category II.b, telephone contacts regardinq this special procedure should be
@@ exnected from the IRC Project flanager. Should issues or conflicts exist, which
'o)a.cl prohibit a response in a tinely nanner, a 10 CFR 50.54(f) letter will be issued.
C FFICE) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . .
suaame > . . . . . . . . . . . . . . . . . . . . ..................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...............
om) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
une ronu sia coan nacu oua OFFIClAL RECORD COPY usom mi-mm
Upon completion of the plant specific review for all plants, a cross-reference of non-qualified equipment existing in any plant will be conducted by the NRC staff to detemine if the same equipnent exists on other plants and has been declared qualif_ied. Should the cross-reference indicate that they do exist in your plant, the staff will contact you to reconfim the qualification of these itens for your plant.
The' ninety (90) day response required by the above referenced SE transmittal letter regarding the schedule for accomplishing proposed corrective actions has been superseded by the requirenents of 10 CFR 50.49. Paragraph (g) of the rule requires that by May 20, 1983, licensees identify electrical equipnent important to safety. within the scope of the rule, that is already qualified, and submit a schedule for the qualification or replacenent of the remaining electrical equipment within the scope of the rule in accordance with the qualification deadline specified in paragraph.(g). The subnittal required by the rule should specifically indicate whether your previous submittals comply with paragraphs (a) and (b) of 10 CFR 50.49. In addition, you are requested to describe in your submittal the nethods used to identify the equipment covered by paragraph 10 CFR 50.49(b)(2) and to establish any qualification prograns not previously described for such equipment.
The Technical Evaluation Report contains certain identified infomation which you have previously clained to be proprietary. tie request that you infom us as indicated in the proprietary review section of the Safety Evaluation whether any pnrtions of the identified pages still require proprietary protection. It should be noted that the NRC's policy on proprietary infomation, as specified in SECY 81-119 is that sunnary data on equipnent qualification testing will not be treated as proprietary by the NRC. This infomation shall be snhnitted within thirty (30) days of receipt of this letter. A general guideline is enclosed.
Tho reporting and/or recordkeeping requirements contained in this letter af fect fewer than ten respondents; therefore, OM8 clearance is not required under P.L.96-511.
. Sincerely, ORIGINAL SIGHED BY Donenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Enclosure:
t Proprietary Review Infomation i cc wo/ Enclosure See next page DISTRIBUTION: Docket File NRC PDR LPDR Gray ORB #2 Rdg DEisenhut
. JHeltemes-AE00 SNorris S acKay OELD NSIC JMTaylor ACRS-10 g ,)CMao YS> vow >lw DLpBS 'DL:( R'B#2 D .:018#2 EQB omce> .................g3,g .g. .... .......ggc ggy..p.g........D rsrralm .
PSh an t" - -- - - - ~ ~ - - - --~~~~~
suRme) .... ......... 4 j n fga... .... 4/.y /83.___. .... 4 yf../83........... 4/.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
omy . . . . . . . . . . . . . . . . ........................ . . . . . . . . . . . . . . . . . ...................... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
NRC FORM 318 (10-80) NRCM ONO OFFICIAL RECORD COPY usceo.im _ m..
fir. E. E. ' Utl ey Carolir.a Power & Light Company cc:
Richard E. Jones,' Esquire .
Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 .
George F. Trowbridge, Eso.uire Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C. 20036 Mr. Charles R. Dietz Plant Manager P. O. Box 458 Southport, North Carolina 28461 Mr. Franky Thomas, Chairman ~
Board of Com:issioners P. O. Sox 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget & Management ,
116 West Jones Street Raleigh, North Carolina 27603 U. S. Environmental Protection Agency Region IV Office Regional Radiation Representative 345 Courtland Street, N. W.
Atlanta, Georgia 30308 L
i Resident Inspector '
- U. S. Nuclear Regulatory Commission P. O. Box 1057 Southport, North Carolina 28461 -
(
James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 :1arietta Street, Suite 3100 Atlanta, Georgia 30303 i
~ l l
PR')?RIETARY REVIEW GUIDELINES It is the pMicy of the Nuclear Regulatory Commission that the records of, the agency are available for inspection and copying in the ERC public -
Document Room, except for matters that'are exempt from public. disclosure pursuant to the nine exemptions of the Freedom of Infomation Act.
(See 10 C.F.R. 2.790)
Recently, the NRC has had'its contrattor Franklin Research Center (FRC),
prepare Technical Evaluation Reports. for all 10 CFR Part 50 licensees. -
These reports evaluate and comment upon the references cited by the licensee as evidence of qualification in accordance with the documentatib6 reference instructitons' established by IE Bulletin 79' 01B. -
In. a typical evaluation, FRC generates a report of approximately 750 pages.
Any page which mentions or comments upon a licensee's referenced' material
.that was marked or claimed to be proprietary is marked at the top of the page wi,th the legend " Proprietary Infomation". FRC has used this marking in a liberal manner and has not fully investigated the licensee's claim to detemine,whether portions of pro,prietary reports that they reproduced or ~ "
m'entioned were in fact " proprietary". A report typically contains 15 to 25 pages that are marked " Proprietary Infomation", Usually, no more than
.4 licensee proprietary references are so discussed. In order td make any of the reports available to the public FRC has produced two versions of each: those containing proprietary in,fomation and those having the pro-prieta ry'.informatica removed.
Th.e NRC now seeks the assistance of licensees in reviewing the proprietary versions of the FRC reports to detemine whether still more information can be made available to the public.
For this reason, each licensee has been sent the Staff Equipment Qualification SER-and 3 copy of the proprietary version of the FRC Technical Evaluation Report. It is believed that the licensee can review the few pages containing proprietary information in a relatively short period of t-ime. The licensee is to send the third party owner of the reference report, which has been ciaimed to be proprietary, a copy of those pages from the FRC report that relates to its test report. The third party owner can quickly revi,ew these pages and determine whether the infomatien claimed to be proprietary must still be so categorized. All reviewers should be aware of the NRC's policy, as specified in SECY-81-119, that sumary data on Equipment Qualification ~ testing will not be treated as proprietary by the NRC. If the review identifies no data that requires protection, the NRC should'be notified and that portion of the report will be placed.in the Public feu ent ?cra. If. 6 ever, the licensee identifies to the N.RC portions that are still ciaired to require prcorietary pretection, then compliance
.. n oe ::.a a wi t$ tr.e riq.,i re.:.tr.:s for withhol dir g ur.dir 10 C.F.R. 2.790.
This can be accomplished in two ways: (1) If the reference proprietary .
rpport has previously been submitted to the NRC pursuant to 10 C.F.R. 2.790 and the NRC has made a detemination that portions are proprietary, then
~
tr.:se sac.e ' portions can be. protected again simply by notifying the NRC that this reteriti is covered in the NRC's acceptance letter of a given date.
If the reference proprietary report has not previously been submitted to the NRC pursdent to 10 C.F.R. 2.790, then the licensee and the proprietary owner must at this time make such an application and request for withholding from -
'public dis closure.
The NRC recognizes that this proprietary review places an administrative burden Upon its licensees and any third party owners. However, it is the-policy of the NRC ta make.all non.-pr.oprietary information public, and the only way to protect the owner of proprietary information is to insure that the Franklin reports have been ' appropriately scrutinized.
.The NRC will grant extensions of time for' these reviEds if necessary, on a case-by-case basis. If you have any fu~r ther questions regarding this review, please contact either Edward Shomaker, OELD, at 492-8553 or.
Heal Abrams, Patent Counsel, at 492-8662.. --
i f
e l
l