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| {{#Wiki_filter:Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430-7373 Production | | {{#Wiki_filter:Frederick W. Schneider Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430- 7373 Vice President Production August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region.I 631 Park Avenue King of Prussia, Pa. 19406 |
| * August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region.I 631 Park Avenue King of Prussia, Pa. 19406
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| ==Dear Mr. Grier:== | | ==Dear Mr. Grier:== |
| NRC INSPECTION 50-272/80-28 UNIT NO. 1 SALEM GENERATING STATION Our letter of March 13, 1981, responded to Inspection No. 50-272/80-28. | | |
| We are now providing supplemental information, as requested,which is based upon further analyses, investigations, and changes implemented following the inspection. | | NRC INSPECTION 50-272/80-28 UNIT NO. 1 SALEM GENERATING STATION Our letter of March 13, 1981, responded to Inspection No. |
| *rnspe*ctio*n Report Details F'ue'l' Tra*nsfe*r* | | 50-272/80-28. We are now providing supplemental information, as requested,which is based upon further analyses, investigations, and changes implemented following the inspection. |
| Tube Event Personnel Intake Estimates | | *rnspe*ctio*n Report Details F'ue'l' Tra*nsfe*r* Tube Event Personnel Intake Estimates |
| *c5*0'-272/80-'28-0l). | | *c5*0'-272/80-'28-0l). of your report states: |
| of your report states: The licensee has indicated an intake evaluation is to be submitted to the Director, Region I. This evaluation will include evaluation ef possible beta and alpha emitter intakes which are not readily detected by whole body counting. | | The licensee has indicated an intake evaluation is to be submitted to the Director, Region I. This evaluation will include evaluation ef possible beta and alpha emitter intakes which are not readily detected by whole body counting. |
| An evaluation for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed. | | An evaluation for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed. |
| The evaluation, which consisted of an examination of analyses J!>erf,ormed on primary coolant samples and resin samples of primary coolant derriineralizers, indicated that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant doses to the personnel involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable. | | The evaluation, which consisted of an examination of analyses J!>erf,ormed on primary coolant samples and resin samples of primary coolant derriineralizers, indicated that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant doses to the personnel involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable. We will continue to examine and quantify the |
| We will continue to examine and quantify the alpha and beta emitters for possible dose contribution to workers . Any s*ignificant differences between our find in gs and those that might result from this review will be reported to your office. ,/8110090237 810929\ ADOCK I | | * alpha and beta emitters for possible dose contribution to workers . |
| * Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Fuel Trans*fer Tube Event Personnel Radiation Exposure (50-272/80'-'28-02) of your report states: The licensee is to submit personnel exposure estimates in a. report to the Director, Region I. Re*spohse:
| | Any s*ignificant differences between our find in gs and those that might result from this additiona~ review will be reported to your office. |
| The personnel exposure estimates have been revised. The dose commitments to their skin, eyes, GI-tract, and lungs are summarized below. Details on the methodology and assumptions are available at the Salem Station. As*s i'gned no*s*e* Commitments Individual A Individual Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10) bf your report states: Licensee's representatives indicated .action will be taken to ensure that the equivalent to Form 5 will reflect incomplete previous history for those individuals who do not have an date exposure history. *Re*st>on:se: | | ,/8110090237 810929\ |
| The station's equivalent of Form NRC-5 has been revised to reflec't incomplete previous history for those individuals who do not have an*up-to-date exposure history. * (5'0'-272/80:-2s-111 o*f your report states: | | ~DR ADOCK 05000~b~ I |
| radiation protection representatives indicated all contractor resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed | | |
| * B | | Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Fuel Trans*fer Tube Event Personnel Radiation Exposure (50-272/80'-'28-02) of your report states: |
| * Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Response: | | The licensee is to submit personnel exposure estimates in a. |
| | report to the Director, Region I. |
| | Re*spohse: |
| | The personnel exposure estimates have been revised. The dose commitments to their skin, eyes, GI-tract, and lungs are summarized below. Details on the methodology and assumptions are available at the Salem Station. |
| | As*s i'gned no*s*e* Commitments Individual A Individual B Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10) bf your report states: |
| | Licensee's representatives indicated .action will be taken to ensure that the equivalent to Form 5 will reflect incomplete previous history for those individuals who do not have an up-to~ |
| | date exposure history. |
| | *Re*st>on:se: |
| | The station's equivalent of Form NRC-5 has been revised to reflec't incomplete previous history for those individuals who do not have an*up-to-date exposure history. |
| | * (5'0'-272/80:-2s-111 o*f your report states: |
| | Licen~ee radiation protection representatives indicated all contractor resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed * |
| | * Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 |
| | |
| | ===Response=== |
| All contractor resumes are reviewed upon arrival of contractor on site. This review assures that the individual meets the time and experience requirements for which he was hired. | | All contractor resumes are reviewed upon arrival of contractor on site. This review assures that the individual meets the time and experience requirements for which he was hired. |
| of your report states: Licensee representatives indicated action will be taken to ensure routine entry permits will not be used.for entries into areas with significant radiological hazard potential and the control of access sign in forms. Response: | | *c5*0*~272/8ff-28-T3}. of your report states: |
| A review of Procedure PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be for entries into areas with significant radiological hazard potential, has*been completed. | | Licensee representatives indicated action will be taken to ensure routine entry permits will not be used.for entries into areas with significant radiological hazard potential and the control of access sign in forms. |
| Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection for HP, Chemistry Operations, and Station QA", was used for routine as well as non-routine entries. This REP had specific requirements for survey points outside the biological shield. It also had specific requirements for entries inside the biological shield where workers were required to be accompanied oy' a heal th physics technician. | | |
| The title of this REP may-have been misleading but the functional role of REP was correct. At Salem, an EREP is used for routine entries. Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector discussions with the* entry party personnel did indicate that the individuals had signed i.n and out, however, the sign-in form apparently had been misplaced. | | ===Response=== |
| This occurrence is considered to be an isolated case and present controls are adequate. | | A review of Procedure PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be us~d for entries into areas with significant radiological hazard potential, has*been completed. Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection for HP, Chemistry Operations, and Station QA", was used for routine as well as non-routine entries. This REP had specific requirements for survey points outside the biological shield. It also had specific requirements for entries inside the biological shield where workers were required to be accompanied oy' a heal th physics technician. The title of this REP may- have been misleading but the functional role of REP was correct. At Salem, an EREP is used for routine entries. |
| The REP rooin supervisor has Been made aware of the continued need for control of access si:gn-in forms. Sincerely, cc D.trector, Off,i;ce of :i:nspection and Enforcement Nuclear Regulatory Commission Wash;tngton, DC. 20555 IA | | Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector discussions with the* entry party personnel did indicate that the individuals had signed i.n and out, however, the sign-in form apparently had been misplaced. This occurrence is considered to be an isolated case and present controls are adequate. The REP rooin supervisor has Been made aware of the continued need for control of access si:gn-in forms. |
| * STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK | | Sincerely, cc D.trector, Off,i;ce of :i:nspection and Enforcement |
| : w. SCHNEIDER, being duly sworn according to law deposes and says: I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection report 50-272/80-28 are true to the best of my knowledge, information and belief. ;FREDERICK W. SCHNEIDER Subscril5ed and sworn to before me th+/-s.JtfYA-day , 1981 Jersey My Commission expires on (flet.0 /91'-:J'}}
| | :Uc;.~s. Nuclear Regulatory Commission Wash;tngton, DC. 20555 |
| | * IA |
| | * STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK w. SCHNEIDER, being duly sworn according to law deposes and says: |
| | I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection report 50-272/80-28 are true to the best of my knowledge, information and belief. |
| | ;FREDERICK W. SCHNEIDER Subscril5ed and sworn to before me th+/-s.JtfYA-day of*~ , 1981 Jersey My Commission expires on (flet.0 /91'-:J'}} |
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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 ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 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 ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld 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 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 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 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 ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 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 ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor 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 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 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 ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 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 ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification 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 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 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 ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 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 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 ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
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Text
Frederick W. Schneider Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430- 7373 Vice President Production August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region.I 631 Park Avenue King of Prussia, Pa. 19406
Dear Mr. Grier:
NRC INSPECTION 50-272/80-28 UNIT NO. 1 SALEM GENERATING STATION Our letter of March 13, 1981, responded to Inspection No.
50-272/80-28. We are now providing supplemental information, as requested,which is based upon further analyses, investigations, and changes implemented following the inspection.
- rnspe*ctio*n Report Details F'ue'l' Tra*nsfe*r* Tube Event Personnel Intake Estimates
- c5*0'-272/80-'28-0l). of your report states:
The licensee has indicated an intake evaluation is to be submitted to the Director, Region I. This evaluation will include evaluation ef possible beta and alpha emitter intakes which are not readily detected by whole body counting.
An evaluation for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed.
The evaluation, which consisted of an examination of analyses J!>erf,ormed on primary coolant samples and resin samples of primary coolant derriineralizers, indicated that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant doses to the personnel involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable. We will continue to examine and quantify the
- alpha and beta emitters for possible dose contribution to workers .
Any s*ignificant differences between our find in gs and those that might result from this additiona~ review will be reported to your office.
,/8110090237 810929\
~DR ADOCK 05000~b~ I
Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Fuel Trans*fer Tube Event Personnel Radiation Exposure (50-272/80'-'28-02) of your report states:
The licensee is to submit personnel exposure estimates in a.
report to the Director, Region I.
Re*spohse:
The personnel exposure estimates have been revised. The dose commitments to their skin, eyes, GI-tract, and lungs are summarized below. Details on the methodology and assumptions are available at the Salem Station.
As*s i'gned no*s*e* Commitments Individual A Individual B Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10) bf your report states:
Licensee's representatives indicated .action will be taken to ensure that the equivalent to Form 5 will reflect incomplete previous history for those individuals who do not have an up-to~
date exposure history.
The station's equivalent of Form NRC-5 has been revised to reflec't incomplete previous history for those individuals who do not have an*up-to-date exposure history.
- (5'0'-272/80:-2s-111 o*f your report states:
Licen~ee radiation protection representatives indicated all contractor resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed *
- Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81
Response
All contractor resumes are reviewed upon arrival of contractor on site. This review assures that the individual meets the time and experience requirements for which he was hired.
- c5*0*~272/8ff-28-T3}. of your report states:
Licensee representatives indicated action will be taken to ensure routine entry permits will not be used.for entries into areas with significant radiological hazard potential and the control of access sign in forms.
Response
A review of Procedure PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be us~d for entries into areas with significant radiological hazard potential, has*been completed. Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection for HP, Chemistry Operations, and Station QA", was used for routine as well as non-routine entries. This REP had specific requirements for survey points outside the biological shield. It also had specific requirements for entries inside the biological shield where workers were required to be accompanied oy' a heal th physics technician. The title of this REP may- have been misleading but the functional role of REP was correct. At Salem, an EREP is used for routine entries.
Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector discussions with the* entry party personnel did indicate that the individuals had signed i.n and out, however, the sign-in form apparently had been misplaced. This occurrence is considered to be an isolated case and present controls are adequate. The REP rooin supervisor has Been made aware of the continued need for control of access si:gn-in forms.
Sincerely, cc D.trector, Off,i;ce of :i:nspection and Enforcement
- Uc;.~s. Nuclear Regulatory Commission Wash;tngton, DC. 20555
- STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK w. SCHNEIDER, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection report 50-272/80-28 are true to the best of my knowledge, information and belief.
- FREDERICK W. SCHNEIDER Subscril5ed and sworn to before me th+/-s.JtfYA-day of*~ , 1981 Jersey My Commission expires on (flet.0 /91'-
- J'