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| | issue date = 02/22/1988 | | | issue date = 02/22/1988 |
| | title = Requests Exemption from 10CFR20,App A,Footnote d-2 to Allow Credit for Radioiodine Protection Factor in Employing Use of MSA 466220 GMR-I Canister for Respiratory Protection.Fee Paid | | | title = Requests Exemption from 10CFR20,App A,Footnote d-2 to Allow Credit for Radioiodine Protection Factor in Employing Use of MSA 466220 GMR-I Canister for Respiratory Protection.Fee Paid |
| | author name = MILTENBERGER S | | | author name = Miltenberger S |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
| | page count = 6 | | | page count = 6 |
| | | project = |
| | | stage = Other |
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| =Text= | | =Text= |
| {{#Wiki_filter:Public Service Electric and Gas Company Steven E. Miltenberger Vice President | | {{#Wiki_filter:Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Vice President - |
| -Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Nuclear Operations February 22, 1988 NLR-N88024 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
| | Nuclear Operations February 22, 1988 NLR-N88024 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: |
| 10CFR20 IODINE ABSORBENT CANISTER EXEMPTION REQUEST SALEM GENERATING STATION UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION DOCKET NOS. 50-272, 50-311 AND 50-354 Pursuant to 10CFR20.103(e) and 10CFR20.501, Public Service Electric and Gas Company (PSE&G) hereby applies for exemption to 10CFR20, Appendix A, footnote d-2 (c) to allow credit for a radioiodine protection factor in employing the use of MSA 466220 GMR-I canister for respiratory protection. | | 10CFR20 IODINE ABSORBENT CANISTER EXEMPTION REQUEST SALEM GENERATING STATION UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION DOCKET NOS. 50-272, 50-311 AND 50-354 Pursuant to 10CFR20.103(e) and 10CFR20.501, Public Service Electric and Gas Company (PSE&G) hereby applies for exemption to 10CFR20, Appendix A, footnote d-2 (c) to allow credit for a radioiodine protection factor in employing the use of MSA 466220 GMR-I canister for respiratory protection. This exemption is desiiable since it will enable us to reduce our workers' total radiation exposures. This is consistent with PSE&G's commitment to keep exposures ALARA. |
| This exemption is desiiable since it will enable us to reduce our workers' total radiation exposures. | | 10CFR20, Appendix A, "Protection Factor for Respirators" does not recognize the use of air-purifying respirators for protection against radioiodine and footnote d-2 (c) specifically prohibits this practice. However, PSE&G is aware of research sponsored by the USNRC - Occupational Radiation Protection Branch, reported in NUREG-CR3403, that has been accomplished to certify air-purifying respirators against radioiodine. To be consistent with this, NUREG-CR3403 position, PSE&G will implement the following limitations and precautions in its Radiological Program and associated procedures when protection against iodine is implemented: |
| This is consistent with PSE&G's commitment to keep exposures ALARA. 10CFR20, Appendix A, "Protection Factor for Respirators" does not recognize the use of air-purifying respirators for protection against radioiodine and footnote d-2 (c) specifically prohibits this practice. | | : 1. A protection factor equal to 50, as a maximum, will be assigned to the GMR-I canister. |
| However, PSE&G is aware of research sponsored by the USNRC -Occupational Radiation Protection Branch, reported in NUREG-CR3403, that has been accomplished to certify air-purifying respirators against radioiodine. | | : 2. The canister allowable service life of eight hours will be calculated from the time of unsealing the canister, including periods of non-exposure. |
| To be consistent with this, NUREG-CR3403 position, PSE&G will implement the following limitations and precautions in its Radiological Program and associated procedures when protection against iodine is implemented: | | |
| : 1. A protection factor equal to 50, as a maximum, will be assigned to the GMR-I canister. | | Document Control Desk 2 02-22-88 |
| : 2. The canister allowable service life of eight hours will be calculated from the time of unsealing the canister, including periods of non-exposure. | | : 3. Canisters will not be used in the presence of organic solvent vapors. Painting or the use of organic substances will be prohibited while the GMR-I canister is in use. |
| Document Control Desk 2 02-22-88 3. Canisters will not be used in the presence of organic solvent vapors. Painting or the use of organic substances will be prohibited while the GMR-I canister is in use. 4. Canisters will be used only with a full facepiece respirator proven capable of providing the individual with a protection factor greater than 100 by a quantitative respirator fit test in accordance with the existing procedure. | | : 4. Canisters will be used only with a full facepiece respirator proven capable of providing the individual with a protection factor greater than 100 by a quantitative respirator fit test in accordance with the existing procedure. |
| : 5. A whole body count will be given to individuals who exceed the level specified by procedure, prior to their next entry into a radioiodine atmosphere. | | : 5. A whole body count will be given to individuals who exceed the level specified by procedure, prior to their next entry into a radioiodine atmosphere. |
| : 6. Function and proper usage of the MSA GMR-I canister will be added to respirator protection training courses. 7. Prior to issue, each canister will be inspected in accordance with the appropriate procedure. | | : 6. Function and proper usage of the MSA GMR-I canister will be added to respirator protection training courses. |
| The estimated dose savings for a typical task at Hope Creek is given in Attachment | | : 7. Prior to issue, each canister will be inspected in accordance with the appropriate procedure. |
| : 1. The results show a net dose savings of approximately 1000 person-mrem for a reactor vessel head lift when using a full face respirator with GMR-I canisters instead of a SCBA or air line respirator.
| | The estimated dose savings for a typical task at Hope Creek is given in Attachment 1. The results show a net dose savings of approximately 1000 person-mrem for a reactor vessel head lift when using a full face respirator with GMR-I canisters instead of a SCBA or air line respirator. |
| PSE&G realizes that the use of the GMR-I canisters are in addition to engineering controls for minimizing iodine exposures. | | PSE&G realizes that the use of the GMR-I canisters are in addition to engineering controls for minimizing iodine exposures. Engineering controls will continue to be emphasized for exposure reduction. Presently, the following measures are employed to minimize airborne iodine: |
| Engineering controls will continue to be emphasized for exposure reduction. | | : 1. Engineering Controls: |
| Presently, the following measures are employed to minimize airborne iodine: 1. Engineering Controls: | | Negative pressure ventilation blowers are used when needed to reduce airborne contamination in general work areas where the reactor coolant system (RCS) is breached. Upon shutdown for an outage, the containment purge system may be operated to reduce general airborne contamination to as low as practical. At Hope Creek, mechanical vacuum pumps are also used to reduce airborne activity in the condenser bay. |
| Negative pressure ventilation blowers are used when needed to reduce airborne contamination in general work areas where the reactor coolant system (RCS) is breached. | | Barrier fuel at Hope Creek is the primary defense against radioiodine buildup in reactor coolant. |
| Upon shutdown for an outage, the containment purge system may be operated to reduce general airborne contamination to as low as practical. | | : 2. Degasification: |
| At Hope Creek, mechanical vacuum pumps are also used to reduce airborne activity in the condenser bay. Barrier fuel at Hope Creek is the primary defense against radioiodine buildup in reactor coolant. 2. Degasification: | | At Salem, normal shutdown procedures require degasification of the RCS by venting the pressurizer vapor space and educting the reactor vessel head. Both processes remove and reduce radioactive gas concentrations including iodine. At Hope Creek the primary system is continuously vented; thus maintaining iodine concentrations at a minimum. |
| At Salem, normal shutdown procedures require degasification of the RCS by venting the pressurizer vapor space and educting the reactor vessel head. Both processes remove and reduce radioactive gas concentrations including iodine. At Hope Creek the primary system is continuously vented; thus maintaining iodine concentrations at a minimum. | | |
| .. Document Control Desk 3 02-22-88 3. Decay Schemes: Maintenance planning for outage items includes consideration of decay times for nuclides of concern, particularily iodine, prior to major breaches of primary systems. If practical, time is allowed for reduction by decay prior to work commencement.
| | Document Control Desk 3 02-22-88 |
| | : 3. Decay Schemes: |
| | Maintenance planning for outage items includes consideration of decay times for nuclides of concern, particularily iodine, prior to major breaches of primary systems. If practical, time is allowed for reduction by decay prior to work commencement. |
| : 4. System and Area Decontamination: | | : 4. System and Area Decontamination: |
| Prior to commencing outage maintenance, time is allotted to decontaminate affected areas. Surveys are conducted frequently during maintenance activities and cleanup/decontamination is conducted accordingly. | | Prior to commencing outage maintenance, time is allotted to decontaminate affected areas. Surveys are conducted frequently during maintenance activities and cleanup/decontamination is conducted accordingly. At the end of each outage, time is allotted for decontamination of maintenance areas as well as for overall decontamination of containment surfaces. |
| At the end of each outage, time is allotted for decontamination of maintenance areas as well as for overall decontamination of containment surfaces. | | In accordance with 10CFR170.12, enclosed is the required application fee of $450.00. |
| In accordance with 10CFR170.12, enclosed is the required application fee of $450.00. If you have any questions regarding this matter, do not hesitate to contact us. Sincerely, Attachment C Mr. G. w. Rivenbark USNRC Licensing Project Manager -Hope Creek Mr. R. w. Borchardt USNRC Senior Resident Inspector | | If you have any questions regarding this matter, do not hesitate to contact us. |
| -Hope Creek Mr. D. c. Fischer USNRC Licensing Project Manager -Salem Mr. T. J. Kenny USNRC Senior Resident Inspector | | Sincerely, Attachment C Mr. G. w. Rivenbark USNRC Licensing Project Manager - Hope Creek Mr. R. w. Borchardt USNRC Senior Resident Inspector - Hope Creek Mr. D. c. Fischer USNRC Licensing Project Manager - Salem Mr. T. J. Kenny USNRC Senior Resident Inspector - Salem |
| -Salem Document Control Desk 4 C Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 02-22-88 | | |
| .. STATE OF NEW JERSEY COUNTY OF SALEM ) ) ) SS. Steven E. Miltenberger, being duly sworn according to law deposes and says: I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated February 22, 1988 , concerning our response to NRC Compliance Bulletin 87-02, are true to the best of my knowledge, information and belief. Subscribed and Sworn to before me of , 1988 ,_
| | Document Control Desk 4 02-22-88 C Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 |
| Notary Public of New Jersey My _Cp!Jl.m-ission expires on EILEEN M. OCHS NOTARY PUBLIC OF NEW JERSEY My Commission Expires July 16, 1992 jJ ' ' | | |
| * Respirator SCBA/ AIRLINE GMR-I NONE ATTACHMENT l TABLE I -HOPE CREEK VESSEL HEAD LIFT WHOLE BODY DOSE RATE (Cavity) 200 rnR/hr Respiratory Task Time Protection Whole Body Thyroid (Person-hrs) | | STATE OF NEW JERSEY ) |
| Factor (person-rnrern) (person-rnrern) 10 2000 2000 0.075 5 50 1000 1.5 3 1 600 45 Total Savings vs. SCBA/AIRLINE (person-rnrern) | | ) SS. |
| ----998 1335}}
| | COUNTY OF SALEM ) |
| | Steven E. Miltenberger, being duly sworn according to law deposes and says: |
| | I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated February 22, 1988 , concerning our response to NRC Compliance Bulletin 87-02, are true to the best of my knowledge, information and belief. |
| | Subscribed and Sworn to before me this~L_day of 1~ , 1988 |
| | ~ |
| | ~JYl~O~ |
| | EILEEN M. OCHS Notary Public of New Jersey NOTARY PUBLIC OF NEW JERSEY My Commission Expires July 16, 1992 My _Cp!Jl.m-ission expires on |
| | |
| | jJ ' ' |
| | * ATTACHMENT l TABLE I - HOPE CREEK VESSEL HEAD LIFT WHOLE BODY DOSE RATE (Cavity) 200 rnR/hr Total Savings Respiratory vs. |
| | Task Time Protection Whole Body Thyroid SCBA/AIRLINE Respirator (Person-hrs) Factor (person-rnrern) (person-rnrern) (person-rnrern) |
| | SCBA/ 10 2000 2000 0.075 ---- |
| | AIRLINE 5 50 1000 1.5 998 GMR-I 3 1 600 45 1335 NONE}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999
Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5)
ML20217M2101999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20217H8471999-10-18018 October 1999
Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs
ML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML20217K8441999-10-15015 October 1999
Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station
ML20217H9771999-10-13013 October 1999
Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML20217C4391999-10-0606 October 1999
Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011
ML18107A5501999-10-0505 October 1999
Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station
ML18107A5521999-10-0505 October 1999
Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys
ML18107A5591999-10-0505 October 1999
Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2
ML20217A9601999-10-0404 October 1999
Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR
ML20217A6861999-10-0101 October 1999
Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs
LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999
Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review
IR 05000272/19990071999-09-28028 September 1999
Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML18107A5421999-09-22022 September 1999
Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl
ML20217K7781999-09-16016 September 1999
Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
ML20212B4021999-09-13013 September 1999
Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes
ML18107A5321999-09-13013 September 1999
Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources.
ML18107A5331999-09-13013 September 1999
Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML18107A5351999-09-13013 September 1999
Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
ML18107A5231999-09-0808 September 1999
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML20211N5421999-09-0808 September 1999
Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual
LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999
Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5061999-08-26026 August 1999
Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151
ML18107A5181999-08-26026 August 1999
Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML20211B5341999-08-20020 August 1999
Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr
ML18107A4861999-08-19019 August 1999
Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML20210R4911999-08-11011 August 1999
Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML20210H9241999-07-26026 July 1999
Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys
ML20210F3271999-07-22022 July 1999
Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek
ML18107A4531999-07-20020 July 1999
Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection
ML20210D3971999-07-16016 July 1999
Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection
05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999
Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl
ML20209G2831999-07-14014 July 1999
Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant
LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999
Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML20217K8441999-10-15015 October 1999
Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML18107A5591999-10-0505 October 1999
Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2
ML18107A5521999-10-0505 October 1999
Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys
ML18107A5501999-10-0505 October 1999
Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station
ML20217A9601999-10-0404 October 1999
Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR
LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999
Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
ML20212B4021999-09-13013 September 1999
Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes
ML18107A5321999-09-13013 September 1999
Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources.
ML18107A5351999-09-13013 September 1999
Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments
ML18107A5331999-09-13013 September 1999
Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML18107A5231999-09-0808 September 1999
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999
Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5181999-08-26026 August 1999
Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A5061999-08-26026 August 1999
Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML20210H9241999-07-26026 July 1999
Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys
05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999
Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl
LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999
Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
ML18107A4181999-06-30030 June 1999
Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl
ML18107A4131999-06-25025 June 1999
Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC
ML18107A4061999-06-21021 June 1999
Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
ML20209B6441999-06-21021 June 1999
Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01
ML20196E6471999-06-21021 June 1999
Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted
ML20196E9631999-06-17017 June 1999
Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5
LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999
Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511
05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999
Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER
ML18107A3691999-06-11011 June 1999
Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990
Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown
ML18095A4901990-09-13013 September 1990
Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request
ML20059H5391990-09-10010 September 1990
Forwards Data Re Bailey Solid State Logic Modules (Sslm) Reliability Program for Period Ending June 1990.Quarterly Summaries of Sslm Data Will Be Provided to End of June 1991
ML20059E6821990-09-0404 September 1990
Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld
ML20059E6791990-09-0404 September 1990
Forwards Security Upgrade Project Status Rept,Per Regulatory Effectiveness Review.Rept Withheld (Ref 10CFR73.21)
ML18095A4621990-08-31031 August 1990
Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned
ML18095A4641990-08-31031 August 1990
Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage
ML20059E7021990-08-30030 August 1990
Forwards RERR-9, Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 11 to Odcm.Summary of Change to ODCM & Rationale Provided in Part G of RERR-9.W/o Rev 11 to ODCM
ML20059D2531990-08-30030 August 1990
Forwards Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept RERR-9 for Jan-June 1990 & Rev 11 to ODCM for Hope Creek Generating Station
ML18095A4431990-08-30030 August 1990
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm.
ML18095A4531990-08-30030 August 1990
Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM
ML18095A4391990-08-29029 August 1990
Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances
ML18095A4421990-08-28028 August 1990
Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75
ML20059D2191990-08-27027 August 1990
Provides Change to Schedule for Implementing Generic Ltr 88-11.Revised pressure-temp Curves Will Be Submitted Prior to Completion of Second Refueling Outage.Existing pressure- Temp Curves Conservative to 32 EFPY
ML20059D2491990-08-24024 August 1990
Requests Regional Waiver of Compliance from Tech Specs 4.0.3 & 4.8.1.1.2.f.2.Waiver Allows Sufficient Time to Perform Surveillance Requirement W/O Requiring Unit Shutdown.Request Involves No Irreversible Environ Consequencies
ML20059C3051990-08-24024 August 1990
Notifies of Minor Structural Enhancements to Spent Fuel Racks Issued by Util 891101 Proposed Change to Tech Spec 5.6.3
ML20059B6611990-08-22022 August 1990
Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced
ML20059C2861990-08-21021 August 1990
Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates
ML18095A4151990-08-10010 August 1990
Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418
ML18095A4091990-08-0909 August 1990
Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr
ML18095A4061990-08-0808 August 1990
Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated
ML18095A3861990-07-30030 July 1990
Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment
ML18095A3761990-07-26026 July 1990
Forwards Decommissioning Repts & Certification of Financial Assurance for Plants
ML18095A3661990-07-26026 July 1990
Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations
ML18095A3721990-07-24024 July 1990
Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75
ML18095A3611990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount.
ML18095A3621990-07-18018 July 1990
Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521
ML18095A3741990-07-18018 July 1990
Provides Supplemental Info Re Facility sub-cooling Margin Monitor
ML18095A3751990-07-18018 July 1990
Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon
ML20055G1571990-07-17017 July 1990
Requests Waiver of Compliance from Tech Spec 6.3.1 Re Requirement That Facility General Manager (Gm) Hold Senior Operator License.Waiver Will Temporarily Allow Individual to Fill Position While Gm Attends off-site Mgt Program
ML18095A3591990-07-13013 July 1990
Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items
ML18095A3471990-07-11011 July 1990
Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets
ML20055G4721990-07-11011 July 1990
Requests Extension Until Sept 1990 to Submit Level 1 Analysis,Per Generic Ltr 88-20 Re Individual Plant Exam Completion
ML18095A3451990-07-10010 July 1990
Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation
ML18095A3461990-07-10010 July 1990
Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors
ML18095A3481990-07-10010 July 1990
Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS
ML18095A3491990-07-10010 July 1990
Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002
ML18095A3441990-07-0909 July 1990
Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification
ML20055E5181990-07-0303 July 1990
Suppls Request for Noncode Temporary Repair of Svc Water Sys.Ultrasonic Exam of Area Surrounding Patch Will Include Samples,In Accessible Areas,Out to Diameter of 14 Inches
ML18095A3281990-07-0202 July 1990
Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development
ML18095A3301990-07-0202 July 1990
Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl
ML18095A3391990-06-29029 June 1990
Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13
ML18095A3241990-06-28028 June 1990
Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr
ML18095A3231990-06-28028 June 1990
Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits
ML18095A3221990-06-28028 June 1990
Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table
ML18095A3211990-06-26026 June 1990
Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout
ML20055D0351990-06-26026 June 1990
Forwards Addl Info Re Svc Water Sys Noncode Temporary Repair,Per 900621 Application.Util Will Perform Ultrasonic Testing of Pipe Wall Adjacent to Fillet Weld Repair & on Patch.Insps Will Be Performed at 90-day Intervals
ML18095A3141990-06-25025 June 1990
Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III
ML18095A3161990-06-25025 June 1990
Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613
ML18095A3201990-06-25025 June 1990
Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated
1990-09-04
[Table view] |
Text
Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Vice President -
Nuclear Operations February 22, 1988 NLR-N88024 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
10CFR20 IODINE ABSORBENT CANISTER EXEMPTION REQUEST SALEM GENERATING STATION UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION DOCKET NOS. 50-272, 50-311 AND 50-354 Pursuant to 10CFR20.103(e) and 10CFR20.501, Public Service Electric and Gas Company (PSE&G) hereby applies for exemption to 10CFR20, Appendix A, footnote d-2 (c) to allow credit for a radioiodine protection factor in employing the use of MSA 466220 GMR-I canister for respiratory protection. This exemption is desiiable since it will enable us to reduce our workers' total radiation exposures. This is consistent with PSE&G's commitment to keep exposures ALARA.
10CFR20, Appendix A, "Protection Factor for Respirators" does not recognize the use of air-purifying respirators for protection against radioiodine and footnote d-2 (c) specifically prohibits this practice. However, PSE&G is aware of research sponsored by the USNRC - Occupational Radiation Protection Branch, reported in NUREG-CR3403, that has been accomplished to certify air-purifying respirators against radioiodine. To be consistent with this, NUREG-CR3403 position, PSE&G will implement the following limitations and precautions in its Radiological Program and associated procedures when protection against iodine is implemented:
- 1. A protection factor equal to 50, as a maximum, will be assigned to the GMR-I canister.
- 2. The canister allowable service life of eight hours will be calculated from the time of unsealing the canister, including periods of non-exposure.
Document Control Desk 2 02-22-88
- 3. Canisters will not be used in the presence of organic solvent vapors. Painting or the use of organic substances will be prohibited while the GMR-I canister is in use.
- 4. Canisters will be used only with a full facepiece respirator proven capable of providing the individual with a protection factor greater than 100 by a quantitative respirator fit test in accordance with the existing procedure.
- 5. A whole body count will be given to individuals who exceed the level specified by procedure, prior to their next entry into a radioiodine atmosphere.
- 6. Function and proper usage of the MSA GMR-I canister will be added to respirator protection training courses.
- 7. Prior to issue, each canister will be inspected in accordance with the appropriate procedure.
The estimated dose savings for a typical task at Hope Creek is given in Attachment 1. The results show a net dose savings of approximately 1000 person-mrem for a reactor vessel head lift when using a full face respirator with GMR-I canisters instead of a SCBA or air line respirator.
PSE&G realizes that the use of the GMR-I canisters are in addition to engineering controls for minimizing iodine exposures. Engineering controls will continue to be emphasized for exposure reduction. Presently, the following measures are employed to minimize airborne iodine:
- 1. Engineering Controls:
Negative pressure ventilation blowers are used when needed to reduce airborne contamination in general work areas where the reactor coolant system (RCS) is breached. Upon shutdown for an outage, the containment purge system may be operated to reduce general airborne contamination to as low as practical. At Hope Creek, mechanical vacuum pumps are also used to reduce airborne activity in the condenser bay.
Barrier fuel at Hope Creek is the primary defense against radioiodine buildup in reactor coolant.
- 2. Degasification:
At Salem, normal shutdown procedures require degasification of the RCS by venting the pressurizer vapor space and educting the reactor vessel head. Both processes remove and reduce radioactive gas concentrations including iodine. At Hope Creek the primary system is continuously vented; thus maintaining iodine concentrations at a minimum.
Document Control Desk 3 02-22-88
- 3. Decay Schemes:
Maintenance planning for outage items includes consideration of decay times for nuclides of concern, particularily iodine, prior to major breaches of primary systems. If practical, time is allowed for reduction by decay prior to work commencement.
- 4. System and Area Decontamination:
Prior to commencing outage maintenance, time is allotted to decontaminate affected areas. Surveys are conducted frequently during maintenance activities and cleanup/decontamination is conducted accordingly. At the end of each outage, time is allotted for decontamination of maintenance areas as well as for overall decontamination of containment surfaces.
In accordance with 10CFR170.12, enclosed is the required application fee of $450.00.
If you have any questions regarding this matter, do not hesitate to contact us.
Sincerely, Attachment C Mr. G. w. Rivenbark USNRC Licensing Project Manager - Hope Creek Mr. R. w. Borchardt USNRC Senior Resident Inspector - Hope Creek Mr. D. c. Fischer USNRC Licensing Project Manager - Salem Mr. T. J. Kenny USNRC Senior Resident Inspector - Salem
Document Control Desk 4 02-22-88 C Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
Steven E. Miltenberger, being duly sworn according to law deposes and says:
I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated February 22, 1988 , concerning our response to NRC Compliance Bulletin 87-02, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me this~L_day of 1~ , 1988
~
~JYl~O~
EILEEN M. OCHS Notary Public of New Jersey NOTARY PUBLIC OF NEW JERSEY My Commission Expires July 16, 1992 My _Cp!Jl.m-ission expires on
jJ ' '
- ATTACHMENT l TABLE I - HOPE CREEK VESSEL HEAD LIFT WHOLE BODY DOSE RATE (Cavity) 200 rnR/hr Total Savings Respiratory vs.
Task Time Protection Whole Body Thyroid SCBA/AIRLINE Respirator (Person-hrs) Factor (person-rnrern) (person-rnrern) (person-rnrern)
SCBA/ 10 2000 2000 0.075 ----
AIRLINE 5 50 1000 1.5 998 GMR-I 3 1 600 45 1335 NONE