Safety Evaluation Re Environ Qualification of safety-related Electric Equipment.Licensee Must Identify All Assumptions Used to Determine Qualification Values.Proprietary Review Guidances EnclML20204F274 |
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Pilgrim |
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Issue date: |
04/13/1983 |
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From: |
Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20204F270 |
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References |
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NUDOCS 8304290239 |
Download: ML20204F274 (7) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20137D0511997-03-20020 March 1997 Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for Relief ML20134K2621997-02-10010 February 1997 Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01 ML20129H3901996-10-30030 October 1996 Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal Flood ML20129F4031996-09-27027 September 1996 Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for Relief ML20059C3751993-12-29029 December 1993 Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 ML20058G2781993-11-29029 November 1993 Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) ML20056F5301993-08-11011 August 1993 Safety Evaluation Re Licensee Response to Reg Guide 1.97, BWR Neutron Flux Monitoring. Criteria of NEDO-31558, Acceptable for Current BWR Operating License & Const Permit Holders ML20127P5431993-01-25025 January 1993 Safety Evaluation Supporting Amend 145 to License DPR-35 ML20126F8121992-12-23023 December 1992 Safety Evaluation Accepting Facility Design W/Respect to RG 1.97 ML20244C2901989-06-0606 June 1989 Draft Safety Evaluation of Util Compliance W/Atws Rule (10CFR50.62) Re Alternate Rod Injection & Recirculation Pump Trip Sys.Alternate Rod Injection Sys Not in Compliance W/Atws Rule Re Diversity ML20235V7341989-03-0303 March 1989 Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station ML20154P6611988-09-28028 September 1988 SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4) ML20151D0551988-07-18018 July 1988 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20151E2041988-07-15015 July 1988 Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test ML20154J9101988-05-17017 May 1988 Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities ML20155F8871988-03-24024 March 1988 Safety Evaluation Concluding That Internal Smoke Seals for Conduits Passing Through Fire Barriers from One Fire Area to Another Consistent W/Branch Technical Position 9.5-1 & Acceptable,Per Util 880203 Submittal ML20236Y3991987-11-10010 November 1987 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input Encl ML20236V3081987-10-28028 October 1987 Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 Encl ML20235M1611987-09-30030 September 1987 Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing ML20236Y3591987-07-22022 July 1987 Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also Encl ML20206G8141987-03-26026 March 1987 Safety Evaluation Re Util Requests for Relief from Inservice Insp Requirements for Surface & Volumetric Exam of RHR Sys HX Nozzles & Exam of 100% Required Vol for nozzle-to-vessel Welds.Requests Granted W/Listed Conditions ML20215H9581987-03-17017 March 1987 Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input Encl ML20212L8941987-01-15015 January 1987 Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses ML20236Y3501986-09-0303 September 1986 Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl ML20212N8401986-08-22022 August 1986 SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation ML20155F8931986-08-20020 August 1986 Safety Evaluation Accepting Util 831116 Request for Four Exemptions from 10CFR50,App R,Section Iii.G.Level of Fire Safety in Listed Fire Zones Equivalent to Safety Achieved by Compliance W/Requirements ML20206L9511986-08-12012 August 1986 Safety Evaluation on Util Response to Generic Ltr 83-28, Items 3.1.1,3.1.2,.3.2.1,3.2.2 & 4.5.1 Re Maint & Test Procedures for safety-related Equipment & on-line Functional Testing of Reactor Trip Sys.Responses Acceptable ML20205C0621986-07-31031 July 1986 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl ML20236Y3361986-07-10010 July 1986 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability ML20199L2541986-07-0101 July 1986 Safety Evaluation Supporting Amend 96 to License DPR-35 ML20206D1741986-06-0606 June 1986 Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall Design ML20203N3801986-04-30030 April 1986 Safety Evaluation Supporting Util 840625,1204,06,850521 & 1011 Responses to Generic Ltr 86-04 Concerning Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii).Facility Does Not Require Recombiner Capability ML20236Y3711986-04-0101 April 1986 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components,Respectively. SALP Input Also Encl ML20137V7621986-02-12012 February 1986 SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping ML20135E5211985-09-11011 September 1985 Safety Evaluation Supporting post-trip Review Program & Procedures ML20134H3571985-08-13013 August 1985 Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining Welds ML20140G1431985-07-0505 July 1985 Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs ML20129C6901985-05-16016 May 1985 Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1 ML20206K6161985-03-13013 March 1985 SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl 1999-09-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
Text
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ENCLOSURE 1
-. UNITED STATES
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i NUCLEAR REGULATORY COMMISSION ~
7 W$F[,/ f WASHINGTON. D. C. 20555
\'^.....#%' SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION BOSTON EDISON COMPANY
.. PILGRIM NUCLEAR POWER STATION !
DOCKET N0. 50-293 i
ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC EQUIPMENT INTRODUCTION General
- Design Criteria 1 and 4 specify that safety-related electrical equipment in nuc. lear facilities must be capable of performing its safety-related function under environmental conditions associated with all normal, abnormal, and accident plant operation. In; order to ensure compliance with the criteria, the NRC staff required all licensees of operating reactors to submit a re-evaluation of the qualification of safety-related electrical equipment which may be exposed to a harsh environment.
BACKGROUND .
On February 8, 1979, the NRC Office of Inspection.and Enforcement (IE) issued to all licensees of operating plants (except those included in the systematic evaluation program (SEP)) IE Bulletin (IEB) 79-01, " Environ-mental Qualification of Class IE Equipment." This Bulletin, together with IE Circular 78-08 (issued on May 31,1978), required the licensees
~ e to perform reviews to assess the adequacy of their environmental qualifica-tion programs.
On January 14, 1980, NRC issued IE Bulletin 79-01% which included the 00R guidelines and NUREG-0588 as attachments 4 and 5, respectively. .
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sl Subsequently, on May 23, 1980, Commission Memorandum and Order CLI-80-21 wasissuedandstatedthe00RguidelinesandportionsofNUREG-0588 form the requirements that licensees must meet regarding environmental qualific,ation of safety-related electrical equipment in order to satisfy those aspects of 10 CFR 50, Appendix A, General Design Criterion (GDC) 4.
Supplements to IEB 79-01B were issued, for further clarification and definition of the staff's needs. These. supplements were issued on February 29, September 30, and October 24, 1980.
In addition, the staff issued orders dated August 29, 1980 (amended in
. September 1980) and October 24, 1980 to atl licensees. The August order. .
required that the licensees pro'idev a report, by November 1,1980, docu-menting the qualification of safety-related electrical equipment. The October order # required the establishment of a central file location for the maintenance of all equipment qualification records. The central file was mandated to be established by December 1, 1980. The staff subsequently issued Safety Evaluation Reports (SERs) on enviromental qualification of safety-related electrical equipment to licensees of all operating plants in mid-1981. These SERs directed licensees to "either provide documentation of the missing qualification information which demonstrates that safety-related equipment meets the DOR G,uide- ;
lines or NUREG-0588 requirements or commit to a corrective action (re qualification, replacement (etc.))." Licensees were required to
- respond to NRC within 90 days of receipt of the SER. In' response T.o 1:
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e thestaffSERissuedbune3,1981,thelicenseesubmittedadditional infcNation regarding the qualification of safety related electrical '
equipment.
EVALUATION The acceptability of the licensee's equipment e,nvironmental qualification program was resolved for the Division of Engineering by the Franklin Research Center ('FRC) as part of the NRR Technical Assistance Program in support of NRC operating reactdr licensing actions. The consultant's ,
review is documented in the report "13eview of Licensees' Resolutions of Outstanding Issues from NRC Equipment Environmental Qualification Safety - -
Evaluation Reports," which is attached.
Wehavereviewedtheevaluationperformedbyourconsultantcontainedin the enclosed Technical Evaluation Report (TER) 'and concur with its bases and findings.
CONCLUSIONS Based on the staff's review of the enclosed Technical Evaluation Report, the following conclusions are made regarding the qualification of safety-related electrical equipment.
The staff is continuing to review the licensee's environmental qualification program. If any additional qualification deficiencies were identified
' ~
during the course of this review,- the licensee would be requir d to reverify the justification for continued operation. 'The staff will review this information to ensure that continued operation, until completion of .
the licensee's environmental qualification program, will not present undue risk to the public health and safety.
The-licensee must provide the. plans
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. scnecule for accomplisning its prop:se: corrective action in accordance witt, iC CFR 50.49. .
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The major qualification deficiencies that have been identified in the enclosed FRC TER (Tables-4-1, 4-2, 4-3 and 4-4) must be resolved by the licensee. Items requiring special attention by the licenseg are summarized below: .- ,
o Submission of information within thirty.(30) days for items - .
in NRC categories I.b, II.a. II.b and IV for which justification ,,
for continued operation was not previously submitted to NRC or FRC .
o The staff has reviewed the p'ressure and temperature profile -
inside containment (Section 4.3.3.1 of the FRC TER) and finds it acceptable, _
o Resolution of the staff concern regarding the pressure and temperature profile outside containment (Section 4.3.3.2 of the'FRC TER),
o Resolution of the staff concern regarding the radiation dose inside and outside containment (Sedtion 4.3.3.3 of the FRC
'TER). As a result of the staff review, we conclude that the licensee must show that all equipment'inside containment is
" qualified ~toradiationvaluesinexcessof1.8x10kRads gamma (for beta shielded components) or 2 x 108 (beta + gamma) for unshielded components, or that the iadiation values inside the Pilgrim containment are less than the' staff estimates.
- . If the licensee elects to demonstrate that a smaller radiation. .
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service condition is appropriate, all assumptions used in the do's'e evaluation and a sample calculation for the dose at the containment centerline from all sources must be provided.
l' Further, the licensee has not provided the radiation environ- .
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ment for equipment located outside containment as identified j in the June 1,1981 SER. The licensee must provide either a 4
j reference for this information or identify all the assumptions j used in determining the qualification values and a sample calcu-lation for one piece of equipment.
'! PROPRIETARY REVIEW ,,
i Enclosed in the FRC Technical Evaluation Report (TER) are certain identi-i i
fied pages on which the information is claimed to be procrietary.
1 During the preparation of the enclosed TER, FRC used test reports and f
.i other documents supplied by the licensee that included material claimed k
i to be proprietary. NRC is now preparing to publicly release the FRC
! TER and it is incumbent on the agency to seek review of all claimed
- proprietary material. As such, the licensee is requested to review I the enclosed TER and notify NRR whether any portions of the identified
~
, , pages still require proprietary protection. If so,.the licensee must ,'
clearly identify this information and the specific, rationale an.1 justi-fication for the protection from public disclosure, detailed in a written
. . - g response. The level of specificity necessary for such continued protection
^
should be' consistent with the criteria enumerated in 10 CFR 2.790(b) of
. . i'
- the Commission's regulations.
Principal Contributor: P. Shemanski, ., ,
Date: April 13,1983 v w , , ,
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j PRPRIETARY REVIE'n' GUI DELINES It is the pMicy of the Nuclear Regulatory Commission that the records of, the agency are avaiTable for inspection and copying in the NRC ou blic Encument Room, except for matters that'are exempt from public. disclosure l pursuant to the nine exemptions of the Freedom of Information Act.
(See 10 C.F.R. 2.790) i Recently, the NRC has had'its contractor Franklin Research Center (FRC),
l prepare Technical Evaluation Reports. for all 10 CFR Part 50 licensees. -
i These reports evaluate and comment upon the references cited by the I licensee as evidence of qualification in accordance with the docanentatib6 reference instruct! ions' established tiy IE Bulletin 79-018.
i In. a typical evaluation, FRC generates a report of approximately 750 pages.
} Any page which mentions or comments upon a licensee's referenced' material j
i that was marked or claimed to be proprietary is marked at the top of the page with the legend " Proprietary Infomation". FRC has used this marking i
in a liberal manner and has not fully investigated the licensee's claim to i
detemine whether portions of pro,prietary reports that they reproduced or '" ~
' m'entioned were in fact " proprietary".- A report t.ypically contains 15 to 25 pages that are marked " Proprietary Infomation", Usually, no more than i
i A licensee proprietary references are so discussed. In order td make any of the reports available to the public FRC has produced two versions of l each: those containing proprietary information and those having the pro-
!, prietary' information removed.
The NRC now seeks the assistance of licensees in reviewing the proprietary versions of the FRC reports to determine i
whether still more information can be made available to the public.
i For this reason, each licensee has been sent the Staff Equipment Q'ualification SEP and 2 copy of the proprietary version of the FRC Technical Evaluation
! Report. It is believed that the licen:;ee can review the few pages containing proprietary information in a relatively short period of time. 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 information claimed to be proprietary must still be so . categorized. All reviewers should be aware of the NRC's polic ji Quali.y, as specified fication ' testing in willSECY-81-119, not be treatedthat as sumary databyonthe proprietary Equipment NRC. If the review identifies no data that requires protection, the NRC should'be notified and that portien of the report will be placed.in the Public D:cu-ent Roo n. If. ha efer, the licensee identifies to' the NRC portions
' that are still clai ed to rapire proprietary protection, their compliance
... , ::4 ma:6 with tr.E ripire.:.ar.ts for withholcing. unde ~r 10 C.F.R. 2.790.
This can be accomplished in two ways: (1) If the reference proprietary r; port has previously been submitted to the NRC pursuant to 10 C.F.R. 2.790 i-
, and the NRC, has made a detemination that portions are proprietary, then I
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- n:se sar,e portions can oe. protected again simply by notifying the NRC that this r:ater il.1 it covered in the NRC's acceptance letter of a given date.
If the reference' proprietary report has not previously been submitted to the NRC p;rs J ant 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 disclosure.
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 to. make .all non.-pr.oprietary information public, and the only way to protect the owner of proprietary'information is to insure 1
that the Franklin reports have been appropriately scrutinized, i
The NRC will grant extensions of time for'these reviews if necessary, on a case-by-case basis. If you have any fu'r ther questions regarding this review, please contact either Edward Shomaker, DELD, at 492-8653 or.
. , Neal Abrams, patent Counsel, at 492-8662. -
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