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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20237B8081998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20126F4161992-12-18018 December 1992 Notification of 930107 Meeting W/Util in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in Highhead Pressure Safety Injection Sys ML20128D2701992-11-25025 November 1992 Notification of 921210 Meeting W/Dl in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in High Pressure SIS ML20125C9761992-11-25025 November 1992 Notification of Canceled Meeting on 921210 in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in high-pressure Safety Injection Sys 1999-07-12
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20212F5401999-09-24024 September 1999 Staff Requirements Memo Re 990924 Affirmation Session Concerning SECY-99-236, Firstenergy Nuclear Operating Co, Local 29 Petition to Waive Time Limits in 10CFR2.1305 & Suppl Comments ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff ML20237B8081998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20126F4161992-12-18018 December 1992 Notification of 930107 Meeting W/Util in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in Highhead Pressure Safety Injection Sys ML20128D2701992-11-25025 November 1992 Notification of 921210 Meeting W/Dl in Rockville,Md to Discuss Design & Operability of Alternate Min Recirculation Path in High Pressure SIS 1999-09-24
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p W to v uq% UNITED STATES
[
5
}p NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555
%*"**/ v AUG 2 7 g ff/V Docket No. 50-412 MEMORANDUM F0R: 4AtwtetEr Division of Licensing FROM: William V. Johnston, Assistant Director Materials, Chemical & Environmental Technology Division of Engineering
SUBJECT:
SAFETY EVALUATION REPORT FOR BEAVER VALLEY POWER STATION, UNIT No. 2 Plant Name: Beaver Valley Power Station, Unit No. 2 ,
Suppliers: Westinghouse Electric Corporation; Duquesne Light Company l Licensing Stage: OL l Docket No.: 50-412 Responsible Branch and Project Manager: LB #3; M. Ley Reviewers: J. Wing, B. Turovlin Description of Task: Operating License Review Status: SER Complete - Two open items In our Draft Safety Evaluation Report, we concluded that Sections 6.1.1, 6.1.2, 9.1.2, 9.1.3, 9.3.2A, 9.3.4, 10.3.5, 10.4.1, 10.4.6 and 10.4.8 were acceptable. Section 9.3.2B (Post-Accident Sampling) met seven of the eleven criteria in Item II.B.3 of NUREG-0737. ,
By letter dated April 18, 1984, the applicant provided additional information.
Enclosed is our safety evaluation. Based on our evaluation, we now conclude that nine of the eleven criteria in Item II.B.3 of NUREG-0737 are met. Section 9.3.2B should be replaced with the attached evaluation. All other sections l in the draft safety evaluation remain unchanged. l Input for the SALP process is also enclosed.
William V. Johnston, Assistant Director Materials, Chemical & Environmental '
Technology Division of Engineering
Enclosures:
As stated
Contact:
J. Wing B. Turovlin x27278 x28556 {
cc: See next page hNSIC[6 [k ,
Thomas M. Novak cc: R. Vollmer D. Eisenhut V. Benaroya C. McCracken G. Knighton T. Sullivan
'S. Pawlicki M. Ley J. Weeks (BNL)
- 8. Turovlin J. Wing I
s e
Safety Evaluation Report by the Office of Nuclear Reactor Regulation for Duquesne Light Company Beaver Valley Power Station, Unit No. 2 Docket No. 50-412 9.3.2 Process and Post-Accident Sampling Systems B. Post-Accident Sampling System (NUREG-0737, II.B.3)
Introduction In our draft safety evaluation, we concluded that the post-accident sampling system met seven of the eleven criteria in Item II.B.3 of NUREG-0737. The four criteria which were unresolved are:
(2) Provide a plant specific procedure to estimate the extent of core damage.
(8) Provide backup sampling capability via grab samples.
(9) Provide capability to measure radionuclide concentrations in the range of 1 pCi/g to 10 Ci/g with an error of a factor of 2.
(10) Provide information on the accuracies, sensitivities, and performance of the PASS instrumentation and analytical procedures in the post-accident water chemistry and radiation environment. Provide the frequency for l demonstrating operability of procedures and instrumentation and retraining of operators on semi-annual basis. I 1
By letter dated April 18, 1984, the applicant provided additional information.
Evaluation Criterion (2):
The applicant shall establish an onsite radiological and chemical analysis capability to provide, within the three-hour time frame established above, quantification of the following:
^
a) certain radionuclides in the reactor coolant and containment atmosphere that may be indicators of the degree of core damage (e.g., noble gases, iodines and cesiums, and non-volatile isotopes);
b) hydrogen levels in the containment atmosphere; c) dissolved gases (e.g., H g ), chloride (time allotted for analysis subject to discussion below), and boron concen-tration of liquids; d) alternatively, have in-line monitoring capabilities to perform all or part of the above analyses.
The PASS provides for in-line analysis of the reactor coolant and containment sump samples for total dissolved gas and oxygen, pH, chloride and boron concen-trations, and gross radioactivity. Hydrogen and oxygen in containment air are analyzed by in-line instrumentation. Radionuclide gamma spectrum analysis will be performed via grab samples at the onsite emergency response facility laboratory.
i The applicant will adopt the Westinghouse Owners Group post-accident core damage assessment methodology.
We determined that these provisions partially meet Criterion (2) of Item II.B.3 in NUREG-0737. The applicant should provide a plant-specific procedure for estimating the degree of core damage.
Criterion (8):
If in-line monitoring is used for any sampling and analytical capa-bility specified herein, the applicant shall provide backup sampling through grab samples, and shall demonstrate the capability of analyzing
the samples. Establishedplanningforanalysisatoffsitefacilities is acceptable. Equipment provided for backup sampling shall be capable of providing at least one sample per day for 7 days following onset c
of the accident and at least one sample per week until the accident condition no longer exists.
i d.
The PASS provides in-line analyses for gross radioactivity, boron, chloride,
'S.
dissolved gases, and pH in reactor coolant and containment sump, and hydrgoen ct and oxygen in containment air. Backup sampling capability through grab samples is available for these in-line analyses.
L'-
We find that these provisions meet Criterion (8) and are, therefore, acceptable.
Criteion (9):
Theapplicant'sradiologicalandchemicalsampleanalysisc$pa'bility shall include provisions to:
r a) Identify and quantify isotopes of the nuclide categories' discussed above to levels corresponding to the source term given in Regulatory Guides 1.3 or 1.4 and 1.7. Where necessary and practicable, the j ability to dilute samples to provide capability for measdrement and l reduction of personnel exposure should be provided. Sensitivity of onsite liquid sample analysis capability should be such as to permit measurement of nuclide concentration in the range from approximately 1 pCi/g to 10 Ci/g.
b) Restrict background levels of radiation in the radiologic'al and chemical analysis facility from sources such that thd sample analysis will provide results with an acceptably smell error (approximately a factor of 2). This can be accomplished through the use of sufficient shielding around samples and outside sources, and by the use of a ventilation system design which will control the presence of airborne radioactivity.
. 1 O
U l'
l The radionuclides in both the primary coolant and the containment atmosphere :
will be identified and quantified. Provisions are available for diluted reactor coolant samples to minimize personnel exposure. The PASS can perform !l 1
radioisotopes analyses at the levels corresponding to the source terms 1 given in Regulatory Guides 1.4, Rev. 2 and 1.7. These analyses will be [
accurate within a factor of two. We find that these provisions meet d l
Criterion (9) and are, therefore, acceptable. I Criterion (10): l I,
Accuracy, range, and sensitivity shall be adequate to provide pertinent data to the operator in order to describe radiological and chemical status of the reactor coolant system.
I The accuracy, range, and sensitivity of the PASS instruments and analytical procedures are consistent with the recommendations of Regulatory Guide 1.97, j Rev. 3, and the clarifications of NUREG-0737, Item II.B.3, Post-Accident Sampling Capability, transmitted to the applicant on August 31, 1983. l Therefore, they are adequate for describing the radiological and chemical f status of the reactor coolant. Equipment used in post-accident sampling j and analyses will be calibrated or tested at least every six months.
Retraining of operators for post-accident sampling is scheduled at a frequency of once every six months. We determined that these provisions partially meet Criterion (10). The applicant should provide information on the performance of the PASS instrumentation and analytical procedures !
in the post-accident water chemistry and radiation environment. ,
i Conclusion '
I We conclude that the post-accident sampling system meets nine of the eleven j
criteria in Item II.B.3 of NUREG-0737. The following two criteria are l unresolved: l l
l I
1
(2) Provide a plant specific procedure to estimate the extent of core damage.
(10) Provide information on the performance of the PASS instrumentation and analytical procedures in the post-accident water chemistry and radiation environment.
s.. r Input to the SALP Process A. Functional Area: Chemical Technology
- 1. Management involvement in assuring quality Throughout the review process, the applicant's activities exhibited evidence of prior planning. Policies for quality assurance of protective coating systems were adequately stated and understood.
Rating: Cateogry 2 l I
- 2. Approach to resolution of technical issues from a safety standpoint The applicant's approach to resolution of the post-accident sampling capability and secondary water chemistry displayed clear understanding I of our concern. Conservatism was generally exhibited. The issues were resolved in a viable and sound manner.
Rating: Category 2
- 3. Responsiveness to NRC initiatives The licensee frequently requires extensions of time to respond to our request for additional information. There are still a number of unresolved issues.
I Rating: Category 3 P
_ _ . . _ . _