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| {{#Wiki_filter::j . Public Service Electric and Gas Company A1ey LaBruna | | {{#Wiki_filter:. |
| -Nuclear Operations
| | :j Public Service Electric and Gas Company A1ey LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 |
| Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 | | ~resident - Nuclear Operations rMR 10 1989 NLR-N89043 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: |
| rMR 10 1989 NLR-N89043 | | RESPONSE TO NOTICE OF VIOLATION NRC COMBINED INSPECTION REPORT NO. 50-272/88-25 AND 50-311/88-25 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) has received the subject inspection report dated February 8, 1989, which included a Notice of Violation regarding failure to implement radiation protection procedures. Pursuant to the requirements of 10CFR2.201, our response is provided in the attachment to this letter. |
| United States Nuclear Regulatory | | Should you have any questions on this transmittal, do not hesitate to callg Sincerely, Attachment 9903210170 a~g55g72 PDR ADOCK 0 PNU G |
| Commission | | |
| Document Control Desk Washington, D.C. 20555 Gentlemen: | | Document Control Desk 2 MAR lo 1889 NLR-N89043 |
| RESPONSE TO NOTICE OF VIOLATION | | * c Mr. J. c. stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuc1*ear Engineering CN 415 Trenton, NJ 08625 |
| NRC COMBINED INSPECTION | | |
| REPORT NO. 50-272/88-25 | | I' |
| AND 50-311/88-25 | | '{ |
| SALEM GENERATING | | ATTACHMENT PUBLIC SERVICE ELECTRIC AND GAS SALEM GENERATING STATION UNIT NOS. 1 AND.2 RESPONSE TO NOTICE OF VIOLATION Your letter of February 8, 1989, transmitted NRC Combined Inspection Report No. 50-272/88-25; 50-311/88-25 for Salem Units 1 and 2 which included a Notice of Violation. The specific items identified in the violation and our related responses are presented below. |
| STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) has received the subject inspection | | Technical Specification 6.11, Radiation Protection Program, requires, in part, that procedures for personnel radiation protection shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. |
| report dated February 8, 1989, which included a Notice of Violation | | : 1. Administrative Procedure AP-24, Radiation Protection Program, requires in part in section 5.4, that Radiation Work Permits be adhered to. Radiation Protection Procedure RP 202, Radiation Work Permits, requires in part in section 7.3.12, that applicable check lists from applicable radiation protection procedures be incorporated into the RWP. The applicable Hot Particle Check list from Radiation Protection Procedure 808, incorporated into RWP No. |
| regarding | | 88-2S-00979, Revision 1, requires Masslin surveys of the entire work area every four hours. |
| failure to implement | | Contrary to the above, on October 18, 1988 and for an undetermined period of time prior to this date, the Hot Particle Check list incorporated into RWP No. |
| radiation | | 88-2S-00979, Revision 1, was not adhered to during work performed under this RWP in that contamination surveys of the 21/23 Steam Generator platforms, part of the work area, were performed only once per shift rather than every 4 hours and were performed with paper disc smears rather than Masslin. |
| protection | | : 2. Administrative Procedure AP-24, Radiation Protection Program, requires in part in section 6.1.3, that personnel shall be denied access to the Radiological Controlled Area (RCA) unless they are entering under the provisions of a valid radiation work permit (RWP). |
| procedures. | | Contrary to the above, on October 5 and 6, 1988, an individual was not denied access to the RCA even though it was known by Radiation Protection Supervision that he could not enter under the provisions of a valid RWP due to dose restrictions. The individual entered the RCA and performed work involving frisking of equipment for contamination. |
| Pursuant to the requirements | | NLR-N89043 |
| of 10CFR2.201, our response is provided in the attachment | | |
| to this letter. Should you have any questions | | I, RESPONSE - ITEM 1 |
| on this transmittal, do not hesitate to callg Attachment | | : 1. ROOT CAUSE The root cause of this violation was inadequate training of Radiation Protection personnel in the new survey techniques utilized in hot particle zones, and a lack of supervisory oversight in not ensuring procedural adherence. |
| 9903210170 PDR ADOCK 0 PNU G Sincerely, | | : 2. CORRECTIVE ACTIONS IMPLEMENTED The Radiation Protection supervisors involved with Steam Generators were counselled on strict compliance with RWP and procedural requirements. They ensured that 4 hour surveys of the platform areas using Masslin cloths were being done in accordance with the Hot Particle Check List and RP 808. |
| * , . * Document Control Desk NLR-N89043
| | : 3. LONG TERM CORRECTIVE ACTIONS TO AVOID FURTHER VIOLATIONS As committed to in our response to NRC Combined Inspection Report No. 50-272/88-18; 50-311/88-18, critical procedures are being taught to appropriate Radiation Protection personnel prior to the start of the next refueling outage, currently scheduled for April 15, 1989. Procedure adherence, RP 808, and hot particle controls are included in these training sessions. The training is being conducted from January through March 1989 and is on schedule. |
| c Mr. J. c. stone Licensing | | In addition, RP 808 was reviewed for procedural adequacy. It was determined that the procedure adequately addressed hot particle control and associated requirements and that no changes to the procedure were necessary. |
| Project Manager Ms. K. Halvey Gibson Senior Resident Inspector | | Supervisory oversight is being stressed for the upcoming Unit 1 Eighth Refueling Outage. |
| 2 Mr. w. T. Russell, Administrator
| | : 4. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The training sessions will be completed prior to the start of the next refueling outage, presently scheduled for April 15, 1989. |
| Region I Ms. J. Moon, Interim Chief New Jersey Department | | NLR-N89043 |
| of Environmental | | * RESPONSE - ITEM 2 |
| Protection | | : 1. ROOT CAUSE The root cause of this violation was inadequate guidance on the precise location of the RCA boundary in the Control Point area. |
| Division of Environmental | | : 2. CORRECTIVE ACTION IMPLEMENTED The individual was removed from the RCA and his dosimetry was checked to ensure that there was no significant exposure. The supervisor responsible for permitting the individual to enter the RCA without being on a valid RWP was counselled. Night orders were issued to management and technicians re-emphasizing the RCA boundaries and the AP-24 requirement to be on a valid RWP to enter the RCA. The importance of this issue was discussed with all Radiation Protection personnel. |
| Quality Bureau of Nuc1*ear Engineering | | : 3. LONG TERM CORRECTIVE ACTIONS TO AVOID FURTHER VIOLATIONS Clarifying instructions have been conspicuously posted at the entrance to the RCA and will be incorporated into the Radiation Worker Training sessions conducted for all personnel. |
| CN 415 Trenton, NJ 08625 MAR lo 1889 | | The Radiation Protection procedures which contain guidance for RCA access were reviewed for clarity. Minor changes (Advanced Change Notices) were initiated for two procedures to clarify the RWP requirement when entering the RCA. These changes will be incorporated into these procedures by March 31, 1989. |
| .. I' '{ ATTACHMENT
| | This incident and its associated corrective actions are being included in the special procedure training for Radiation Protection personnel as previously discussed. |
| PUBLIC SERVICE ELECTRIC AND GAS SALEM GENERATING | | : 4. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The special procedure training will be completed prior to the start of the next refueling outage, presently scheduled for April 15, 1989. |
| STATION UNIT NOS. 1 AND.2 RESPONSE TO NOTICE OF VIOLATION | | NLR-N89043}} |
| Your letter of February 8, 1989, transmitted | |
| NRC Combined Inspection | |
| Report No. 50-272/88-25; | |
| 50-311/88-25 | |
| for Salem Units 1 and 2 which included a Notice of Violation. | |
| The specific items identified | |
| in the violation | |
| and our related responses | |
| are presented | |
| below. Technical | |
| Specification | |
| 6.11, Radiation | |
| Protection | |
| Program, requires, in part, that procedures | |
| for personnel | |
| radiation | |
| protection | |
| shall be approved, maintained | |
| and adhered to for all operations | |
| involving | |
| personnel | |
| radiation | |
| exposure. | |
| 1. Administrative | |
| Procedure | |
| AP-24, Radiation | |
| Protection | |
| Program, requires in part in section 5.4, that Radiation | |
| Work Permits be adhered to. Radiation | |
| Protection | |
| Procedure | |
| RP 202, Radiation | |
| Work Permits, requires in part in section 7.3.12, that applicable | |
| check lists from applicable | |
| radiation | |
| protection | |
| procedures | |
| be incorporated | |
| into the RWP. The applicable | |
| Hot Particle Check list from Radiation | |
| Protection | |
| Procedure | |
| 808, incorporated | |
| into RWP No. 88-2S-00979, Revision 1, requires Masslin surveys of the entire work area every four hours. Contrary to the above, on October 18, 1988 and for an undetermined | |
| period of time prior to this date, the Hot Particle Check list incorporated | |
| into RWP No. 88-2S-00979, Revision 1, was not adhered to during work performed | |
| under this RWP in that contamination | |
| surveys of the 21/23 Steam Generator | |
| platforms, part of the work area, were performed | |
| only once per shift rather than every 4 hours and were performed | |
| with paper disc smears rather than Masslin. 2. Administrative | |
| Procedure | |
| AP-24, Radiation | |
| Protection | |
| Program, requires in part in section 6.1.3, that personnel | |
| shall be denied access to the Radiological | |
| Controlled | |
| Area (RCA) unless they are entering under the provisions | |
| of a valid radiation | |
| work permit (RWP). Contrary to the above, on October 5 and 6, 1988, an individual | |
| was not denied access to the RCA even though it was known by Radiation | |
| Protection | |
| Supervision | |
| that he could not enter under the provisions | |
| of a valid RWP due to dose restrictions. | |
| The individual | |
| entered the RCA and performed | |
| work involving | |
| frisking of equipment | |
| for contamination. | |
| NLR-N89043 | |
| I, '* -2-RESPONSE -ITEM 1 1. ROOT CAUSE The root cause of this violation | |
| was inadequate | |
| training of Radiation | |
| Protection | |
| personnel | |
| in the new survey techniques | |
| utilized in hot particle zones, and a lack of supervisory | |
| oversight | |
| in not ensuring procedural | |
| adherence. | |
| 2. CORRECTIVE | |
| ACTIONS IMPLEMENTED | |
| The Radiation | |
| Protection | |
| supervisors | |
| involved with Steam Generators | |
| were counselled | |
| on strict compliance | |
| with RWP and procedural | |
| requirements. | |
| They ensured that 4 hour surveys of the platform areas using Masslin cloths were being done in accordance | |
| with the Hot Particle Check List and RP 808. 3. LONG TERM CORRECTIVE | |
| ACTIONS TO AVOID FURTHER VIOLATIONS | |
| As committed | |
| to in our response to NRC Combined Inspection | |
| Report No. 50-272/88-18; | |
| 50-311/88-18, critical procedures | |
| are being taught to appropriate | |
| Radiation | |
| Protection | |
| personnel | |
| prior to the start of the next refueling | |
| outage, currently | |
| scheduled | |
| for April 15, 1989. Procedure | |
| adherence, RP 808, and hot particle controls are included in these training sessions. | |
| The training is being conducted | |
| from January through March 1989 and is on schedule. | |
| In addition, RP 808 was reviewed for procedural | |
| adequacy. | |
| It was determined | |
| that the procedure | |
| adequately | |
| addressed | |
| hot particle control and associated | |
| requirements | |
| and that no changes to the procedure | |
| were necessary. | |
| Supervisory | |
| oversight | |
| is being stressed for the upcoming Unit 1 Eighth Refueling | |
| Outage. 4. DATE WHEN FULL COMPLIANCE | |
| WILL BE ACHIEVED The training sessions will be completed | |
| prior to the start of the next refueling | |
| outage, presently | |
| scheduled | |
| for April 15, 1989. NLR-N89043 | |
| .. -:-;:-*. _ ..
| |
| * RESPONSE -ITEM 2 1. ROOT CAUSE -3-The root cause of this violation | |
| was inadequate | |
| guidance on the precise location of the RCA boundary in the Control Point area. 2. CORRECTIVE | |
| ACTION IMPLEMENTED | |
| The individual | |
| was removed from the RCA and his dosimetry | |
| was checked to ensure that there was no significant | |
| exposure. | |
| The supervisor | |
| responsible | |
| for permitting | |
| the individual | |
| to enter the RCA without being on a valid RWP was counselled. | |
| Night orders were issued to management | |
| and technicians | |
| re-emphasizing | |
| the RCA boundaries | |
| and the AP-24 requirement | |
| to be on a valid RWP to enter the RCA. The importance | |
| of this issue was discussed | |
| with all Radiation | |
| Protection | |
| personnel. | |
| 3. LONG TERM CORRECTIVE | |
| ACTIONS TO AVOID FURTHER VIOLATIONS | |
| Clarifying | |
| instructions | |
| have been conspicuously | |
| posted at the entrance to the RCA and will be incorporated | |
| into the Radiation | |
| Worker Training sessions conducted | |
| for all personnel. | |
| The Radiation | |
| Protection | |
| procedures | |
| which contain guidance for RCA access were reviewed for clarity. Minor changes (Advanced | |
| Change Notices) were initiated | |
| for two procedures | |
| to clarify the RWP requirement | |
| when entering the RCA. These changes will be incorporated | |
| into these procedures | |
| by March 31, 1989. This incident and its associated | |
| corrective | |
| actions are being included in the special procedure | |
| training for Radiation | |
| Protection | |
| personnel | |
| as previously | |
| discussed. | |
| 4. DATE WHEN FULL COMPLIANCE | |
| WILL BE ACHIEVED The special procedure | |
| training will be completed | |
| prior to the start of the next refueling | |
| outage, presently | |
| scheduled | |
| for April 15, 1989. NLR-N89043 | |
| }} | |
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Encl Withheld 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 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 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 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 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 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 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 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 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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- j Public Service Electric and Gas Company A1ey LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800
~resident - Nuclear Operations rMR 10 1989 NLR-N89043 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
RESPONSE TO NOTICE OF VIOLATION NRC COMBINED INSPECTION REPORT NO. 50-272/88-25 AND 50-311/88-25 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) has received the subject inspection report dated February 8, 1989, which included a Notice of Violation regarding failure to implement radiation protection procedures. Pursuant to the requirements of 10CFR2.201, our response is provided in the attachment to this letter.
Should you have any questions on this transmittal, do not hesitate to callg Sincerely, Attachment 9903210170 a~g55g72 PDR ADOCK 0 PNU G
Document Control Desk 2 MAR lo 1889 NLR-N89043
- c Mr. J. c. stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuc1*ear Engineering CN 415 Trenton, NJ 08625
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ATTACHMENT PUBLIC SERVICE ELECTRIC AND GAS SALEM GENERATING STATION UNIT NOS. 1 AND.2 RESPONSE TO NOTICE OF VIOLATION Your letter of February 8, 1989, transmitted NRC Combined Inspection Report No. 50-272/88-25; 50-311/88-25 for Salem Units 1 and 2 which included a Notice of Violation. The specific items identified in the violation and our related responses are presented below.
Technical Specification 6.11, Radiation Protection Program, requires, in part, that procedures for personnel radiation protection shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
- 1. Administrative Procedure AP-24, Radiation Protection Program, requires in part in section 5.4, that Radiation Work Permits be adhered to. Radiation Protection Procedure RP 202, Radiation Work Permits, requires in part in section 7.3.12, that applicable check lists from applicable radiation protection procedures be incorporated into the RWP. The applicable Hot Particle Check list from Radiation Protection Procedure 808, incorporated into RWP No.
88-2S-00979, Revision 1, requires Masslin surveys of the entire work area every four hours.
Contrary to the above, on October 18, 1988 and for an undetermined period of time prior to this date, the Hot Particle Check list incorporated into RWP No.
88-2S-00979, Revision 1, was not adhered to during work performed under this RWP in that contamination surveys of the 21/23 Steam Generator platforms, part of the work area, were performed only once per shift rather than every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and were performed with paper disc smears rather than Masslin.
- 2. Administrative Procedure AP-24, Radiation Protection Program, requires in part in section 6.1.3, that personnel shall be denied access to the Radiological Controlled Area (RCA) unless they are entering under the provisions of a valid radiation work permit (RWP).
Contrary to the above, on October 5 and 6, 1988, an individual was not denied access to the RCA even though it was known by Radiation Protection Supervision that he could not enter under the provisions of a valid RWP due to dose restrictions. The individual entered the RCA and performed work involving frisking of equipment for contamination.
NLR-N89043
I, RESPONSE - ITEM 1
- 1. ROOT CAUSE The root cause of this violation was inadequate training of Radiation Protection personnel in the new survey techniques utilized in hot particle zones, and a lack of supervisory oversight in not ensuring procedural adherence.
- 2. CORRECTIVE ACTIONS IMPLEMENTED The Radiation Protection supervisors involved with Steam Generators were counselled on strict compliance with RWP and procedural requirements. They ensured that 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> surveys of the platform areas using Masslin cloths were being done in accordance with the Hot Particle Check List and RP 808.
- 3. LONG TERM CORRECTIVE ACTIONS TO AVOID FURTHER VIOLATIONS As committed to in our response to NRC Combined Inspection Report No. 50-272/88-18; 50-311/88-18, critical procedures are being taught to appropriate Radiation Protection personnel prior to the start of the next refueling outage, currently scheduled for April 15, 1989. Procedure adherence, RP 808, and hot particle controls are included in these training sessions. The training is being conducted from January through March 1989 and is on schedule.
In addition, RP 808 was reviewed for procedural adequacy. It was determined that the procedure adequately addressed hot particle control and associated requirements and that no changes to the procedure were necessary.
Supervisory oversight is being stressed for the upcoming Unit 1 Eighth Refueling Outage.
- 4. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The training sessions will be completed prior to the start of the next refueling outage, presently scheduled for April 15, 1989.
NLR-N89043
- 1. ROOT CAUSE The root cause of this violation was inadequate guidance on the precise location of the RCA boundary in the Control Point area.
- 2. CORRECTIVE ACTION IMPLEMENTED The individual was removed from the RCA and his dosimetry was checked to ensure that there was no significant exposure. The supervisor responsible for permitting the individual to enter the RCA without being on a valid RWP was counselled. Night orders were issued to management and technicians re-emphasizing the RCA boundaries and the AP-24 requirement to be on a valid RWP to enter the RCA. The importance of this issue was discussed with all Radiation Protection personnel.
- 3. LONG TERM CORRECTIVE ACTIONS TO AVOID FURTHER VIOLATIONS Clarifying instructions have been conspicuously posted at the entrance to the RCA and will be incorporated into the Radiation Worker Training sessions conducted for all personnel.
The Radiation Protection procedures which contain guidance for RCA access were reviewed for clarity. Minor changes (Advanced Change Notices) were initiated for two procedures to clarify the RWP requirement when entering the RCA. These changes will be incorporated into these procedures by March 31, 1989.
This incident and its associated corrective actions are being included in the special procedure training for Radiation Protection personnel as previously discussed.
- 4. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The special procedure training will be completed prior to the start of the next refueling outage, presently scheduled for April 15, 1989.
NLR-N89043